Text

Forwards Advanced FSAR Change Re Clarification of Radiation Monitor Parameters,Including Related Ser/Sser Pages & Index Page for Bullets
	ML20247F670
Person / Time
Site:	Comanche Peak
Issue date:	08/31/1989
From:	William Cahill; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TXX-89636, NUDOCS 8909180238
	Download: ML20247F670 (59)
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'1 M Log # TXX-89636

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= r 1UELECTRIC August 31, 1989 William J. Cahill, Jr.

Erecutive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR CHANGE SUBMITTAL CLARIFICATION OF RADIATION MONITOR PARAMETERS Gentlemen:

The enclosure to this letter provides an advanced submittal of FSAR changes that clarify certain aspects of radiation monitor parameters.

In order to facilitate NRC staff review of this submittal, supporting information related to these changes is organized as follows:

1. Draft revised FSAR pages, with changed portions identified by a revision bar in the margin (denoted as " DRAFT"), as they are to appear in a future amendment.

2. Line-by-line descriptions / justifications of each revised FSAR item together with their group and classification designations, as well as an indication of whether the change impacts the SER/SSER.

3. A copy of related SER/SSER sections.

4. An index page containing the title " bullets" which consolidate and categorize similar individual FSAR changes by subject and related SER section.

l 5. A discussion of each " bullet" which includes:

- The line-by-line description / justification for each FSAR item related to the " bullet" which has been screened as a group 1 or 2 item or a group 3 or 4 item that impacts the existing SER/SSERs. (The discussion of these groups is contained in TU Electric letter TXX-88467 dated June 1, 1988).

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FDR ADOCK0500kg5 400 North Olive Street LB 81 Dallas, Texas 73201

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TXX-89636 August 31', 1989

Page 2 of 2 The bold / overstrike version of the revised FSAR pages referenced by the description / justification for each. item-

. identified above. The bold / overstrike version .f acilitates revies of the revisions by-highlighting each addition of new.

text in bold type font and overstriking with a slash ~(/)'the; portion-of the. text that is deleted. In~some' cases, where the bold overstrike version is unavailable, a hand marked-up version will be provided.

TU Electric requests that the NRC perform an expedited review of:this: FSAR change package and' inform us of its acceptability.

Sincerely, Y 171 )

William J. Cahill, Jr.

By: *Ct41 k k[

Roger T. Walker Manager, Nuclear Licensing RLA/vid Enclosure c -Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) a _ = _ _ ___ _ ____-_-

~ Enclosure to TXX-89636

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- Aygust 31. 1989 Page.1 of 58-l(

Advance FSAR Change Related to the Clarification of Radiation Monitor Parameters Sub.iect Pigg Item-1 Draft Revised Pages 2

. Item 2 Description / Justification for A11' FSAR Changes 33 Item 3 Related SER/SSER Pages 39 Item 4 Index Page for Bullets 46 Item 5 Description / Justification for Bullets and 47 Associated Bold /0verstrike Pages p

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' Enclosura to'TXX-87636 i 'Ad'gu s t 31,-1989

. Paga 2 of 58 CPSES/FSAR 9.3.4.2.5.4 Level Level in the Recycle Holduo Tanks Instrumentation is provided to give an . indication of the water level of' each recycle holdup tank. Both high level and low level alarms are provided by this instrumentation at the,8RS panel. If, after reaching the low level alare setpoint, the recycle evaporator feed pumps are not stopped, the holdup tank level will continue to decrease until a second low level point is reached and a level actuated control circuit stops the pumps.

9.3.4.2.5.5 Radiation Radiation Level of Recycle Evanorator Condensate Instrumentation is. provided to give an indication in the Control Room of the radiation level in the recycle evaporator condensate. Upon a high level signal, this system.causes a three-way valve to divert flow back to the recycle evaporator feed dominera111ers. This DRAFT instrumentation also has an alert radiation level alarm on the BRS panel and in the main control room on the RMS console.

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g. Safeguard Building vent duct monitors (1 per unit) 27

h. Plant vent stack monitors (2/ stack, common) 76

2. Process and Effluent Monitors 27

a. Auxiliary steam condensate monitor (1, common) 27

b. Boron recycle monitor (1, common) l27

'c. Component cooling water monitors (3 per unit) 27

d. Service water monito,rs (2 per unit) 27

e. Spent fuel pool cooling water monitors (2, common) DRAFT

f. Steam generator blowdown sample monitors (1 per unit) 27

g. Steam generator blowdown monitors (1 per unit) 27

h. Turbine Building drain effluent monitors (1 per unit) 27

1. Liquid waste effluent monitor (1, common) ORAFT

j. Waste gas monitor (1. common) 27

k. Condenser off-gas monitors (1 per unit) 27

1. Spent fuel pool demineralized monitor (2, common) DRAFT

m. Failed-fuel monitors (1 per unit) 27

n. Main Steam line monitors (4 per unit) 27 l

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11.5-3 Draft Version

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'AuQust 31, 1989 CPSES/FSAR Paga 4 of 58 The condenser off-gas and waste gas effluent.are monitored by 46 ,

beta-sensitive detectors enroute to the primary plant ventilation system and plant vent stack where they are ultimately monitored and discharged. I 52 Wi,en the Liquid Waste Processing System is in the proper valve a

configuration, liquid can be discharged to the Circulating Water 1 System and will be monitored by a gamma-sensitive detector before release to the circulating water discharge tunnel. Turbine 76 Building drain effluent is monitored by gamma-sensitive monitors prior to release to the environment via the Low Volume Waste Treatment Facilities or sampled and released on a batch basis to the circulating water discharge tunnel via the co-current waste treatment facilities.

11.5.2 SYSTEM DESCRIPTION 11.5.2.1 Desion Criteria - Continuous Monitorino The following criteria govern the design of the PRMS:

1. To facilitate compliance with applicable regulations (e.g., 30 CFR Part 20), monitors and detectors have sensitivities and ranges compatible with radiation levels anticipated at specific detector locations.

2. The alarm setpoints and other important database parameters are 76 controlled by approved plant procedures utilizing designed supervisory control features inherent to the process monitors.

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3. The detected radiation levels of the monitored process and DRAFT effluent systems are indicated and daily averages recorded on demand on printers for up to 28 days in the Control Room and annunciated on the RMS consoles.

11.5-5 Draft Version

Enclosure to TXX-89636

' August 310 1989

- .Page 5 of 58- CPSES/FSAR operation including anticipated operational occurrences should be monitored." In accordance with this guide, the points to be-monitored are those that provide data on effluent releases to the plant i environs: these monitoring points are indicated schematically on diagrams referenced in Table 11.5-1. Monitors are provided for the following:

-1. Process streams that normally discharge low-level activity directly to the environment.

76 2. Continuous process streams that discharge directly to the environment but do not normally carry radioactive material.

Such monitoring indicates ,1,f any radioactive leaks into these process lines have occurred.

3. Process lines which contain radioactivity but do not normally discharge to the environment. Such monitoring indicates if process malfunctions have occurred.

52 11.5.2.3 Exoected Radioactivity Concentrations and Quantity Measured 76 The expected radiat*on levels in the process and effluent streams are such that concentrations in gascous effluents at the Exclusion Area Boundary and liquid effluents at the discharge point are a small fraction of 10-CFR Part 20 limits. The calculation of radioactive concentrations and the levels to be monitored or sampled are described in Section 11.1 and Table 11.5-4. _

18 Each channel, except the iodine monitors, measures gross radioactivity.

27 11.5.2.4 Detector Tvoe. Sensitivity. and Rangg The range of each detector, along with other pertinent information Draft Version 11.5-8

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, i Enclosure to.TXX-89636.

August 31, 1989. CPSES/FSAR Page 6 of 58-such as detector type and reference nuclide are summarized in Table DRAFT 11.5-1.

Detector location and sample line routes from sampling point to 27 i detector are chosen to minimize sample line length, and the number of direction changes are chosen to minimize transport losses. Sample

. lines are appropriately sized; where applicable, stainless steel tubing is made with long radii elbows in conformance with ANSI N13.1-1969.

Process and effluent stream activity detectors are scintillation 66 crystals or Cd Te (C1) which detect beta or gamma radiation over an energy range appropriate for the process stream. Design sensitivities and ranges have b'een selected so that the instrument 27 either reads on scale or stays within system limits during normal operation, taking into consideration the limitations of such equipment.

11.5.2.5 Dioital System Description 27 11.5.2.5.1 General 27 The RMS is a dedicated distributed microprocessor based digital 76 monitoring system. System communication connections require only two twisted-shielded pairs of low-voltage cable. Details are provided in 27 the following text and Figure 11.5-1. Certain channels are seismically qualified to remain operable during and after the SSE.

The Control Room consoles provide digital cathode ray tube (CRT) displays and digital recording on printers. The monitor detector

s locations have control, data processing, data storage, and multilevel

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alarming features. See Table 11.5-3.

The microprocessor-based RMS is comprised of the following components:

1. Two (each) redundant minicomputer consoles, color CRTs, printers, 76 and keyboards 11.5-9 Draft Version

l cEnclosure to TXX-89636-

'Au'gus t 31, 1989 Page 7 of 58 CPSES/FSAR 66 2. One'(each) report processor, disk drives, black and white CRT, and printer (local) l l

3. Four (each) report processor terminals DRAFT. 4. Dedicated microprocessors for each monitor 46 5. Remote displays and controls on process system operator panels 46 6. Monitors with associated equipment 76 7. Control Room equipment racks (two) furnished with display / control modules for selected monitors The system concept is a distributed data base with each individual 76 monitor processor maintaining its own data base and stored data. A stand-alone configuration includes redundant minicomputers in two CRT .

consoles that handle five loops of up to 31 monitors per loop. Alarm messages are sent to the Control Room from the detector microprocessor when polled by the RM-11 console. The requested information is then returned to the RM-11 consoles, where they are displayed, printed, and announced. Alarma are displayed in various display formats.

Operator-initiated display requests cause console requests for data 76 from the monitor processors. The console minicomputers contain the communications links to the monitor processor loops and the necessary memory and programming to provide overall system status, monitor group profiles, and individual monitor trend displays. These minicomputers are interconnected'd to provide alternate communications paths, thus tolerating a single communications cable fault or monitor malfunction without loss of function in the system. In addition to the display requests from the keyboard, other control functions such as check-source readings, pump motor control, and purge control are provided.

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Enclosura to TXX-89636

' August 31, 1989' CPSES/FSAR L Page 8 of 58 l Certain radiation monitor channels are seismically qualified 27 throughout, because of their importance to the safe operation of the plant. .These-channels are capable of withstanding a Safe Shutdown Earthquake (SSE). Dedicated control / display modules on seismically 76 qualified cabinets for the containment air monitors, plant vent stack monitors (WRGMs and PIGS), and the class 1E Control Room ventilation intake monitors are provided in the control room. The individual control /dispicy modules in the cabinets utilize the same 76 microprocessor chip as the monitor processor but on a simpler board.

These modulr.s perform basically the same control and display functions as the CRT consoles, but communicate directly with the monitor processors. The control / display module has lighted alarm indicators, pushbuttons for the check-source test, purge or filter step, and pump

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motor control. Since the seismic channels are also connected to the CRT. consoles, the normal use of these modules is as a backup to the CRT consoles which are not seismically qualified.

Communication is the basis for component interface for the multiprocessor system. Communications ch cuits tie the monitor processors, the Control Room consoles, and the report processor into a single system. Tne communications cabling uses two twisted-shielded pairs in a daisy-chain configuration. Each daisy chain is made into a loop from the first console through a group of monitors to the second console to provide two directions for communications into the central units in case of a failure in any-loop section. The monitor processors on the first console side of such a failure communicate with that console, and those on the other side communicate with the second console. The consoles update each other and lose no information after any. single failure except from a failed monitor D

itself. Communication consists of messages between the units of the DRAFT system and the protocol for handling them.

11.5-11 Draft Version i

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, CPSES/FSAR Page 9 of 58 52 Each monitor processor has a data base which includes count rate, conversion factors, high alarm limit, alert alarm limit, check-source limit, and where monitored, sample and process parameters.

l- - 76. Calculations are performed using these parameters and the raw data from the dete'ctor. The raw data from the detector are accumulated into two separate computational sections. One section performs averaging calculations and history filing; the other computes the current rate and tests for alarm conditions.

DRAFT Processed data are averaged and stored in memory for a history trend.

l The history file of detector data consists of 24 10-min averages, 24 1-hr' averages, and 28-1 day averages.

Alarm determinations are based on having a significant number of counts-available to calculate, with a 95 percent confidence level that count' alarm rates are being reached, Counts are incremented into an accumulator and tested for significance at time intervals consistent with system alarm response requirements. If the count is significant and the rate is beyond an alarm limit, alarming occurs. The rate computed in this alarm section is displayed as the current rate.

11.5.2.5.2 Monitoring Assemblies Each monitoring assembly is the equivalent of a digits 1 ratemeter.

66 Each console with its color CRT display, keyboard, and printer is a remote digital display and recorder for the monitoring assemblies.

76 All field wiring for communication circuits consists of twisted-shielded pairs that are daisy- chained from monitor to monitor and to the display cabinets. Each monitor processor and the display .

consoles are furnished with safety related or reliable non-safety related power (backed by diesel /non-safety related station batteries) as applicable.

Draft Version 31.5-12 i

Enclosure to TXX-89636

'Au*gus t 31, 1989 CPSES/FSAR Page 10 of 58 At each monitor, control, data processing, data storage, and 76 multilevel alarming are all performed by the local microprocessor independently from the rest of the system. If Control Room displays DRAFT and computers are down, the data stored locally at each individual monitor are a"vailable for later communication when the Control Room displays and computers are back on line. The hourly and daily averages are stored, and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months may pass without loss of those averages. Twenty-eight days may pass without loss of daily averages. 66 No data need be lost as a consequence of multiple . failures in the equipment common to all monitor channels.

The microprocessor at each radiation monitor assembly is an Intel 8085A with semiconductor memory to control the monitor, to process and store data, and to communicate messages through intervening monitors to either of the Control Room consoles.

The initial parameters (such as setpoints, conversion factors and 76 channel identification) that specify how to control each channel and how to process its data are provided in the microprocessor da'tabase.

76 Data processing at each nonitor microprocessor is briefly listed as follows:

1. Monitor Microprocessor Control (on command from the Control Room console)

a. Operates the check source upon manual command from the Control Room console o

b. Steps the filter (where applicable) upon manual command from the Control Room console 11.5-13 Draft Version

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'Au'gu s t 31, 1989 CPSES/FSAR

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1. Maint ins a rotating file of past values of radiation data: DRAFT 24.10-ain averages, 24 1-hr averages, and 28 1-day averages.

J. Uses a specification table (conversion factor, etc.) to control the processing. All entries for a monitor's specifications are sent as messages to that monitor's microprocessor, where they are stored in the specification table. See Subsection 11.5.2.5.2 76 11.5.2.5.3 Control Room Consoles The microprocessor-based system with two operator consoles and report computer is a complete, stand-alone system, as shown on Figure 11.5-1.

The consoles are dedicated to radiation monitoring and function independently of the plant computer.

The consoles (see Figure 11.5-1) each have a 19-in color CRT display, 52 a keyboard, a printer, and a DEC PDP-11/34 computer. The computer 76 is the basic control center of the console.

The consoles give the operators consolidated and fully processed information on the RMS throughout the plant and each console stores the complete alarm status for all connected monitors. The basic display on the CRT console is the status grid display. Selection of the proper function key on the console keyboard displays the complete alarm status via a grid wherein each monitor is represented by a colored rectangle with six superimposed characters. The characters 52 identify the monitor and the background color indicates monitor status, alarm conditions, check source testing, off scan, no response, and normal operation.

11.5-15 Draft Version

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Enclosuri to TXX-89636 -

fAu' gust'31,1989 Page 12 of 58 CPSES/FSAR The next level of console display information conveys a greater amount of detail. .There are two types of displays on this level of greater detail: the monitor trend display and the group profile display.

76 The monitor trend display is used to access the trend histories of 24

' DRAFT 10-min. averages 24 1-hour averages, or 28 1-day averages. These trends are displayed in bar chart format scaled to the high alarm limits. The monitor trend display also provides-information such as 76 the current activity in engineering units, the data base background value, the high alarm setpoints, and process and sample flow rates, if applicable.

76 The group profile display shows a horizontal bar of current radiation for each monitor in a selected group. Each horizontally displayed bar is normalized to place its a"ert-alarm at a percentage of scale and is colored to show its status. The group's radiation profile is ,

therefore shown relative to the alert condition. The detailed information consists of the absolute value of current radiation for each monitor, the engineering units of each value, each monitor number, and a description of up to 16 characters for each monitor.

The two console microcomputers communicate with each other, with the remote monitor assemblies, and with the report computer. The serial bit communication lines operate synchronously at the standard rate of 4800 baud (transmission rate of computer messages, bits /sec). The communication and error recovery procedures are subsets of IBM's BSC/BTAM.

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Draft Version 11.5-16

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August 31, 1989 CPSES/FSAR Page 13 of 58 !

A1.5.2.5.4 Report Computer 1

l The report computer collects data from meteorological instrumentation. DRAFT '

This data may be used to generate periodic reports in accordance with NRC Regulatory Guide 1.21. Section 2.3.3.2 discusses the process for accumulation of data by the report ::omputer. 76 76 11.5.2.5.5 Control Room Equipment Racks A seismically qualified control / display module for each Containment 66 Air, plant vent stack (WRGMs and PIGS) and Control Room Ventilation intake monitor is located withi,n seismic equipment racks in the Control Room. Digital displays are provided for each channel, in !

addition to switches for pump control, filter step, check source 27 operation, and alarm acknowledge. The channel status indicators 52 (operate, alert, high) are indicated by means of green, yellow, and ,

red lamps, respectively, provided on each module.

Each seismic channel has a separate radiation detector and internal 27 power supply. A local microprocessor is provided for each monitor.

Each microprocessor has three communication ports which provide for connection to each of the central microcomputer CRT consoles and the 76 control / display modules in the Control Room.

76 I

Should communications between local microprocessors and the Control DRAFT Room fail, the microprocessor at the local detector would continue to monitor radiation levels, and to store daily averages for up to 28 days. Thus, a high degree of reliability and independence is j

assured. The microprocessor is also equipped with a connector where a 76 l

portable digital readout device con be connected to display data.

The monitoring system has independent power supply electronics for each monitor.

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l 11.5-17 Draft Version l

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11.5.2.5.7 Annunciators and Alarms A11' process and effluent radiation monitors are annunciated on'the RMS.

consoles in'the-Control Room. The individual' detector microprocessors 76 respond to pollingslfrom the RM-11 console by-initiating alarm a,

r I

. messages'in the control. room when set points are exceeded, although' all automatic' control functions and local alarms are initiated.

"* -directly.from-the microprocessor. The routine and automatic polling DRAFT l of monitors is for the purpose of accumulating data-for. trend history, radiation'alarus and monitor failures. The~ functions of alarming via

.a CRT, sounding a horn, and printing alarm events on a printer 'are

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_ performed by'the-system. A reflash logic is provided for alarms'on the CRT.

! _Each' console stores complete alarm status for all monitors attached to it. Pushing one button displays the complete _ alarm status via s grid, as-discussed in Subsection 11;5.2.5.3.

Eac'h new alarm condition is logged- at a console printer for.a 52' permanent record. The alarm message, as typed, contains the date, time, alarm' code, channel or monitor identification, and message.

When channels in alarm return to normal, this condition is logged in the same manner. The return to the normal value for each alarm limit is lower by the programmed hysteresis provided to avoid repeated alarms from count rate statistical fluctuation near the set point.-

11.5.2.6 Airborne Radioactivity Monitorina Systems Fixed monitors are provided for continuous detection and measurement p.

of airborne radioactivity for gaseous process streams and for plant gaseous effluents. These monitors, part of the plant PRMS, are summarized in Table 11.5-1. General design.and performance objectives

'for all elements of the PRMS are covered in Subsections 11.5.1 and

-11.5.2. In addition, the following criteria for air sampling are met:

i 11.5-19 Draft Version

' Enclosure'to TXX-89636

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Page 15 of 58 CPSES/FSAR

1. Detectors are located as close to sampler intakes as feasible.

76 2. In the design of : ample nozzles and lines, the guidelines of ANSI l

N13.1-1969 are considered to obtain representative sampling and reduce settling and plateout losses of particulate in transport to the detector.

3. The. Containment atmosphere particulate and gaseous radioactivity monitors are part of the reactor coolant pressure boundary (RCPB)

DRAFT leak detection system. Accordingly, all elements of these channels required for radiation indication are designed and qualified to remain functional following an SSE, in compliance with NRC Regulatory Guide 1.45.

11.5.2.6.1 Sampling Devices 76 For each off-line gaseous monitor, a sample is drawn from a system through a sample line to the monitor skid. The sample is routed 31 through the monitor skid as discussed in detail in the subsequent 76 sections for each monitor type. The air is then returned to the system from which it was extracted. Samples from the plant vent stacks are drawn using isokinetic nozzles.

76 Sample pumps are utilized to draw an appropriate sample through the monitor. Each monitor has a low sample flow alarm. A local flow indicator is provided for vent stack monitors which have particulate and iodine filters, so that the total volume that has passed through 54 the filters can be determined. The filter papers used to collect p particulate have a collection efficiency of at least 99 percent for 76 0.3-micrometer particulate. The cartridges used to collect iodine have been shown to have a minimum efficiency of 95 percent for elemental and organic iodine.

Each off-line gas monitor has manually operated sample valves. This allows room air to be routed through the gas monitor to check the Draft Version 11.5-20

Enclosure to TXX-89636

' August 31, 1989 Page 16 of 58 CPSES/FSAR 76 viewed by a shielded gamma-sensitive scintillation detector. The particulate filter tape and iodine filter are replaced as required to support operation of the monitor. When the sample air leaves the 76 iodine cartridge it is directed thrcugh a closed system to a shielded stainless steel gas sampling chamber viewed by a beta sensitive scintillation detector. The sampled air is finally returned to the Containment atmosphere. Indication and annunciation are provided in DRAFT the Control Room. The detection of high radiation levels by the particulate or noble gas channels causes the high-level set point to trip and initiates Containment Ventilation Isolation. The Containment air particulate, iodine, and noble gas monitor is installed in a single housing mounted on a skid with equipment that is described as follows: ..

1. A flow-control assembly, that includes a pump unit, comprised of the following:

a. A pump to obtain the air sample

b. A flowmeter to indicate the flow rate

c. A flow-control valve to provide flow adjustment

d. A flow switch

e. A flow controller

f. A vacuum gauge 76 2. System sensing units with indications provided on the RMS console and control / display module on a seismic cabinet for the following:

a. Filter stepping

b. A low-flow alarm on the RMS console

c. A high pressure alarm The particulate and gas monitor are also used as part of the RCPB leakage detection system. The sensitivity and response time of this part of the leakage detection system, which is used for monitoring Draft Version 11.5-22

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' ' J:nclosure to TXX-89636 Au' gust 31; 1989 Paga 17 of 58 CPSES/FSAR-E unidentified leakage to the Containment, is sufficiently sensitive to detect an' increase in leakage rate,'or the equivalent of one gpm in less than one hour. Indicators and alarms are provided in the Control Room. A complete description of the leakage detection system is presented in Section 5.2.5.

l 11.5.2.6.3 Plant Vent Stack Monitoring System 27 Each plant vent stack is equipped with a particulate, iodine, and gas. 76 (PIG) monitor. They are off-line monitors that sample the plant vent effluent prior to discharge and are similar to the Containment monitors.

~

The plant vent stack PIG monitors draw representative air samples from 76 the plant' vent stack via isokinetic nozzles in the stack, and directs them through moving filter paper viewed by shielded beta-sensitive scintillation detectors. The sample streams then pass through an iodine adsorber cartridge, where collected iodine is viewed by shielded gamma-sensitive scintillation detectors. This channel is DRAFT.

intended p'rimarily for I-131 monitoring. A single channel differential discriminator is used with the window centered on the I- 27 131,.0.364-MeV photopeak. Lead shielding is provided to reduce DRAFT background to levels that allow the detection of the specified instrument ranges given in Table 11.5-1.

)-

A collector type-monitor is selected for this application in view of 27 the very low iodine-emission rates permissible. Because the monitor is of the collector type, it does not have a definite sensitivity threshold determined solely by background, as with the other plant D

radiation monitors. The quantity of interest is the rate of increase 54 of the count rate of the built-in scintillator, which is a function of sample-stream I-131 concentration.

11.5-23 Draft Version

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, .., CPSES/FSAR Paga 18 cf 58 52 channel range, the channel maintains its operation and returns to 76 normal functioning when the transients have subsided. Since gamma detectors are used. it is possbile to compare the monitor readout with the results of grab samples analyzed in the plant multichannel analyzer as of check of proper monitor operation.

Solenoid-operated check sources are provided to check detector response. Monitor characteristics are listed in Tables 11.5-1 52 and 11.5-3. Monitors with local process control panels have local radiation alarms and/or indication of channel radioactivity levels.

27 11.5.2.7.1 Steam Generator Blowdown Sample Monitor 76 This channel monitors the liquid phase of the secondary side of the steam generators for radioactivity to provide an indication of a

. primary-to-secondary system leak. This provides backup information to the condenser off-gas monitor. The radiation detector is able to monitor radioactivity from blowdown for each steam generator. Blowdown sample lines from each of the steam generators are combined in a common header, and the common sample is continuously monitored by a shielded gamma-sensitive detector located downstream of the sampler assembly. After sampling and monitoring, the blowdown sample is routed to the atmospheric drain tank for return to the Condensate DRAFT System. Control Room alarm and indication are provided to alert operating personnel. Additionally, an alert alarm is also provided on the local process panel. In the event of high activity, the i- monitors high-level set point trips and initiates an alarm and the automatic closure of the isolation valves in the blowdown and sample lines. Prior to this event, the alert alarm set point gives an alarm 4

and indication of increasing activity. The isolation valves for blowdown sampling can be opened by overriding the monitor, as needed, for operation and analysis. Identification of which steam generator

/

is leaking is made by overriding each of the sample line isolation valves and drawing samples from each steam generator blowdown line separately for analysis.

Draft Version 11.5-28

.. . I L '* Enclosure to TXX-89636 Au'gus t ' 31, 1989 Paga 19 cf 58- CPSES/FSAR-

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. Control Room RMS consoles. Containment Air, plant vent stack (PIGS DRAFT ,

and WRGMs),.and control room ventilation intake monitors also have control / display modules in the Control Room. Two distinct, visible alarms are provided for all channels for alert and high alarm. A 27 common audible alarm is provided for alert and high set point trip and for loss-of- instrument signal or background. Certain monitors have local indicators associated with their channels. Some channels have their-indication and annunciation on process system control panels, as listed in Table 11.5-3.

11.5.2.9 Accuracy The overall accuracy of a radiation monitor system is governed by four 66 major areas: (a) factory calibration and alignment (b) detector characteristics and environment, (c) microprocessor environment, and (d) field alignment. Factory calibration is performed with standards traceable to the National Bureau of Standards (NBS). Detector energy response and linearity are demonstrated by factory calibration and site calibration procedures subsequent to operations. Detector and microprocessor environmental variations are determined from qualification tests. Overall monitor error is the root-mean-square I sum of all system errors and for accident conditions is within a l factor of 2 over the entire range. 76 11.5.2.10 Sensitivity Threshold sensitivity is defined as twice the background standard 27 L deviation. 76 0

11.5.2.11 Calibration The initial calibration of each complete monitoring system was 76 performed by the manufacturer at the factory. These calibrations were primary calibrations performed in accordance with ANSI N13.10 on 11.5-33 Draft Version

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I Enclosura to TXX-89636

(- 'Adgust 31, 1989'

[

Page 26 of 58 L CPSES/FSAR The off-line Containment PIG monitors are seismically designed 76 monitors. They have digital indication on the control / display module installed on the seismic equipment rack, located in the Control Room.

All airborne monitors have remote indication, alarm, and printout via the peripherals of the microcomputer consoles located in the Control Room.

l 12.3.4.2 Area Radiation Monitorina System The objectives of the ARMS are as follows:

1. To provfde plant operators and personnel with a system which 76 informs them of radiologic'al conditions is selected plant areas and provide an indication of changing radiological conditions.

2. To indicate, alarm, and record for up to 28 days abnormal 76 radiation levels in areas where radioactive material is present, stored, handled, or inadvertently introduced.

The primary functions of the ARMS are as follows:

1. To provide continuous surveillance of radiation dose rates of representative accessible and restricted areas of the plant

2. To alert personnel of dose rates above a predetermined set point. 76

3. To provide a direct reading indication and on demand record of DRAFT U daily radiation dose rate averages for up to 28 days for each monitor location.

12.3-49 Draft Version

., Enclosure to TXX-89636 CPSES/FSAR' l'

Au* gust'31, 1989 Pags 27 of 58such that less of check sourcs actuatien po er will cause ths 76 source to return to a shielded position. ~ Higher. range area

-monitor ionization detectors have ranges that are too high to check with radiation sources. These are provided with check currents that test the electronic circuitry of the monitor.

These monitor checking capabilities are remotely operable from DRAFT the-control room. These checks provide convenient operational

~

checks of these monitors. Additionally, the radiation check 76 source provides a gross. response check of the detector.

F System operability may be verified by observation of channel behavior or by use of the check source or currene. Any detector whose response cannot be verified by these methods may have its response checked with a portable check source.

6. Test Calibration Circuitry Each monitor microprocessor contains self-checking diagnostics in its ROM, a rotary switch on a printed circuit (PC) card to select each diagnostic program, and a red and green light (also on each PC card) to show the result of each diagnostic test. These allow the microprocessor board to be functionally checked while installed in its enclosure. Typical tests include the following:

a. Communication loop (continuity)

b. ROM DRAFT

c. Local indicator DRAFT

d. Local alarms DRAFT

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12.3-57 Draft Version

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Enclosure to TXX-89636 CPSES FSAR AMENDMENT L h" August 31. 1989 DETAILED. DESCRIPTION' Page 1 LPage 33 of 58

FSAR Page (as amended) Group Description 9.3-98 4' Modifies the text describing the location of the alert radiation level alarm for the recycle evaporator condensate.

Clarification:

This change identifies the specific location of this alert alarm.

FSAR Change Request Number: 89-465.24 Related SER Section: 11.2.1.1 SER/SSER Impact: No 11.5-3 3 Modifies the nomenclature for several of the Process and Effluent Monitors.

Correction:

These changes are made for the purpose of achieving consistency with other references to these monitors FSAR Change Request Number: 89-465.01 Related SER Section: 11.3 SER/SSER Impact: No 11.5-5, 20 3 Modifies the description of the extent and scope of the type of indication and recording that is provided for the detected radiation levels derived from the process and effluent monitoring systems.

Correction:

This change reflects the capability of the control room RMS' consoles, and is consistent with the design cri-teria specified in paragraph 4 of Section 12.3.4.2.1.

FSAR Change Request Number: 89-465.02 Related SER Section: 11.3 SER/SSER Impact: No 11.5-8, 23 2 See Page No(s): Table 11.5-1, sh I to 5 :

Deletes reference to the term "MDA" on pg. 11.5-8 and, in Table 11.5-1 (where it is identified as "MDC")

adds the applicable Nominal Instrument Ranges; also, on pg. 11.5-23, indicates which range is being discussed.

o Correction:

These changes are made to avoid misinterpretations of the MDA/MDC values that had been specified and to achieve consistency with Table 12.3-8. (Note that the values for the Nominal Instrument Range always envelop the design basis values of the Specified Instrument Range.)

FSAR Change Request Number: 89-465.03 .

1 Related SER Section: 11.3 SER/SSER Impact: No

FSAR AMENDMENT

, .' Enclosure to TXX-89636 DETAILED DESCRIPTION Page 2 August 31, 1989 Page 34 of 58 LFSAR Page (as amended) Group Description 11.5-10, 18 2 Modifies the description of the microprocessor-based RMS.

Correction:

These changes are made to indicate that local alarms and displays are not provided for all monitors.

FSAR Change Request Number: 89-465.04 Related SER Section: 11.3 SER/SSER Impact: No 11.5-11 4 Deletes the description of the types-of actions in-volving the messages used by the control room consoles.

in communicating with each other and the protocol for handling them.

Clarification:

This deletion is made since no specific on-site testing is pertformed to provide additional assurance that the units function as described: the verification stems from the manufacturer.

FSAR Change Request Number: 89-465.05 Related SER Section: 11.3 SER/SSER Impact: No 11.5-12, 15 3 Deletes the discussion of data validity testing and the associated reference to Reg. Guide 1.21.

Revision:

This deletion is made since the processor being dis-cussed is no longer used to generate the Reg. Guide 1.21 effluent reports.

FSAR Change Request Number: 89-465.06 Related SER Section: 11.3 SER/SSER Impact: No 11.5-13 2 Modifies the text describing data storage by the local microprocessors when the control room displays and computers are down.

Correction:

This change more accurately reflects the current design since local data indication is not provided for all monitors.

FSAR Change Request Number: 89-465.07 Related SER Section: 11.3 SER/SSER Impact: No 11.5-16 2 Deletes that portion of the text indicating that the monitor trends are displayed at the alert limit.

Correction:

This change reflects the current design of this equip-ment.

CPSES FSAR AMEND W

..%. .Enr.losure.to TXX-89636 DETAILED DESCRIPTION Page 3 r- . August 31,~1980 l Page:35 of 58 FSAR Page (as amended) Group Description FSAR Change Request Number: 89-465.08 Related SER Section: 11.3 SER/SSER Impact: No 11.5-17 3 Deletes that portion of the text in Section 11.5.2.5.4' which indicated that the report computer collects effluent monitor data for usa in generating the Reg.

Guide 1.21 effluent reports.

Revision:

This change is made since the report computer is no longer.used to generate radiological effluent data (for the Reg. Guide 1.21 effluent release report): however, it is still used to collect meteorological data required for.that report.

FSAR Change Request Number: 89-465.09 Related SER Section: 11.3 SER/SSER Impact: No 11.5-19 3 Modifies the text describing the specific data that are accumulated for polling of monitors.

Correction:

This change is made to reflect the capability of the as-purchased equipment.

FSAR Change Request Number: 89-465.10 Related SER Section: 11.3 1- SER/SSER Impact: No 11.5-20 4 Modifies the text by indicating that only those channel elements required for radiation indication are designed and qualified to remain functional following a SSE.

l- Clarification:

This change clarifies which monitor channels are quali-fied (since only the Containment high radiation ~indi-cation is required to remain functional following a SSE).

FSAR Change Request Number: 89-465.11 Related SER Section: 11.3 SER/SSER Impact: No 11.5-22 2 Modifies the de:;cription of the Containment Monitoring System by indicating that Containment ventilation iso-1ation is in!tiated by the particulate and noble gas ,

channels.

Correction:

This change is made to be consistent with an earlier change (identified in Figure 7.2-1. sh 8) that removed the iodine channel from providing this trip signal.

FSAR Change Request Number: 89-465.12

n CPSES'FSAR AMENDMENT f

. Enclosura to TXX-89636 . DETAILED DESCRIPTION Page 4 l ,.

' August 31,71989-L Page 36'of 58-

,FSAR Page . .

(as amended) Group Description Related SER Section: 11.3-

-SER/SSER Impact: Yes Table 11.6 of the SER should be revised by correcting the footnote for the Containment monitoring system to reflect deletion of the iodine channel from initiating Containment ventilation isolation. ESFAS function (12) listed in Section 7.3.1 should be revised similarly, 11.5-28 3 ' Modifies the text to describe the location of the alert alarm for the steam generator' blowdown sample monitor.

Correction:

This change reflects the fact that the alert alarm is

. located on the local process panel.

FSAR Change Request Number: 89-465.13 Related SER Section: 11.3 SER/SSER Impact: No 11.5-33 3 Changes a portion of the text in Section 11.5.2.8, "Honitor Indication and Alarm", to correctly identify the modules that are provided in the Control Room.

Correction:

This change provides the correct nomenclature for these modules.

FSAR Change Request Number: 89-465.14 Related SER Section: 11.3 SER/SSER Impact: No Table 11.5-1 3 See Sheet-No(s):sh I to 5 Modifies a number of the entries in the column titled, "Specified Instrument Range", by lowering the value of the upper range for those detectors.

. Correction:

These changes are made to be consistent with the specification for these monitors.

FSAR Change Request Number: 89-465.15 Related SER Section: 11.3 SER/SSER Impact: No

' Table 11.5-1 3 See Sheet No(s):sh 3 to 5 Adds footnote 8 and identifies the specific detectors for which it is applicable.

Addition:

This change is made to identify the fact that, for the detectors so identified, when they operate in the range SE-03 to IE-01,'their confidence level is outside of that identified in ANSI 13.10. (Note that this range is beyond the design basis values listed in the "Specified Instrument Range".)

FSAR Change Request Number: 89-465.16

i CPSES FSAR AMENDMENT' Enclosure to TXX-89636 Pago 5 August.310.1989- DETAILED DESCRIPTION Page 37 of 58 i'= l FSAR Page j (as amended) Group Description 1 i

Related SER Section: 11.3 l SER/SSER Impact: No

' Table 11.5-3.'sh 1 2 Deletes the automatic control action (i.e., Containment ventilation isolation) associated with the Containment iodine monitor.

i. Correction:

This change is made to be consistent with an earlier l change (identified on Figure 7.2-1, sh 8) that removed the iodine channel from providing this trip signal.

FSAR Change Request Number: 89-465.17 Related SER Section: 11.3 SER/SSER Impact: Yes SER Sections 7.3.1 (see ESFAS function 12) and 11.3 (see table 11.6) should both be revised to reflect the fact that a Containment isolation signal is no longer derived from the iodine channel of the Containment monitoring system.

12.3 3 Modifies one of the primary functions of the Area Radiation Monitoring System (ARMS) dealing with pro-

j. viding direct reading indication and an on demand record of radiation dore rates.

Correction:

This change is made to be consistent with other FSAR sections describing this feature (see, e.g., Sections 11.5.2.1 and 12.3.4.2.1, on pages 11.5-5 and 12.3-52, respectively).

FSAR Change Request Number: 89-465.18 Related SER Section: 12.3.4 SER/SSER Impact: No 12.3-57 2 Deletes the automatic monitoring checking capability for those high range area monitor ionization detectors that are provided with check currents for testing the electronic circuitry of the monitor (in lieu of using a radiation source).

Correction:

This change is made to reflect the capability of the as-purchased equipment and is consistent with the pro-cedures for checking radiation monitors using radio- I active sources.

FSAR Change Request Number: 89-465.19 Related SER Section: 12.3.4 ;

SER/SSER Impact: No )

l J

12.3-57 2 Deletes two of the typical tests used to functionally check the ARMS microprocessor circuitry.

Correction:

I 1

____-_b

~

. CPSES FSAR AMENDNENT

.. .Enclosura to TXX-89636 DETAILED DESCRIPTION Page 6

.j August 31, 1989

.Page 38 of 58:

FSAR Page

'(as amended) GrouD Description This change is m'ade to reflect the capability of the as-purchased equipment.

FSAR Change Request Number: 89-465.20 Related SER Section: 12.3.4 SER/SSER Impact: No Table 12.3-8 3 See Sheet No(s):sh I to 5 Changes the title of one column to read "Specified

-Instrument. Range", and adds a new column titled,

" Nominal Instrument Range".

Correction:

These changes are made to properly differentiate between these two sets of instrument ranges. (Note that the values for the Nominal instrument Range always envelop the design basis values of the Specified Instrument Range.)

FSAR Change Request Number: 89-465.21 Related SER Section: 12.3.4 SER/SSER Impact: No Table 12.3-8 3 See Sheet No(s):sh 1 to 5 Adds footnote 8 which is applicable to the GM Tube detectors.

Addition:

This change is made to identify the fact that, for the i detectors so identified, when they operate in the range I SE-03 to 1E-01, their confidence level is outside of f that designated in ANSI 13.10. (Note that this range ,

j is beyond the design basis values listed in the l "Specified Instrument Range".)

l FSAR Change Request Number: 89-465.2?.

L Related SER Section: 12.3.4 l SER/SSER 1mpact: No Table 12.3-8 4 See Sheet No(s):sh 1 to 5 Adds footnote 9 and indicates that it is only applic-

, able to Channels 1RE 6290A & B.

Clarification:

This change is made to indicate that these particular instruments read out in R/hr rather than in mR/hr.

FSAR Change Request Number: 89-465.23

, Related SER Section: 12.3.4 l SER/SSER Impact: No l

I

4

, . Enclosure to TXX-89636- 1 Au' gust-31o 1989- .

Page 39 of 58 l 1

Table 11.4 Comparison of calculated doses to a maximum individual .'

fromtheoperationofCgmanchePeakUnits1or2with Appendix I to 10 CFR 50 Maximum-Individual Doses Calcul t*.ac Source Design Objective Oose Annual Dose per Reactor Unit Liquid effluents Dose to total body from all pathways 3 mrom 1. 9 mrem Dose to any organ from all pathways 10 arem 2.3 mrem (liver)

Noble gas effluents (at site, boundary)

Gamma dose in air 10 mrad 0.12 mrad Beta dose in air 20 mrad 0.28 mrad Dose to total body of an individual 5 ares 0.08 mrem Dose to skin of an individual 15 mrom 0.19 mren b

Radiciodine and particulate Dose to any organ from all pathways 15 aren 1. 8 mr (bone, .I aAppendix I design objectives from Sections II.A, II.8, II.C, and II.D (By Anne-RM50-2) of Appendix I,10 CFR Part-50; considers doses to maximum individual.

" Carbon-14 and tritium have been added to this category.

system to control boron concentration and reactor water purity. In its evalu; tion model, the staff assumed that a portion of the CVCS flow will be release:

through the LWPS for tritium control.~ In addition, for baron control, the boron recycle system (BRS) will process a portion of the letdown flow (shim bleed) from the primary coolant purification system, along with wastes collecte o' in the reactor coolant drain tanks. Steam generator blowdown will be cooled ar:

sent directly to the condensate cleanup system for processing and reuse in the ,

plant. Laundry, hot shower, and decontamination wastes are normally treated t.. '

a reverse osmosis unit before they are released.

11.2.1.1 Chemical and Volume Control System A letdown stream of approximately 75 gpm of primary coolant is removed from the primary reactor coolant system for processing through the chemical and volume control system (CVCS). The letdown stream is cooled through the letdcwr' s

11-6 /

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11-7

. 3Enclosure to TXX-89636

.Aubust 31. 1989 Page:41"of 58

~

heat exchangers, reduced in pressure, filtered and processed through one of-two mixed-bed domineralizers in the Li 3 B03 form. For cation control,;a cati ' 1) 1 bed domineralizer is valved into the process strqam approximately 10'; of th(

time. The-processed 1stdown stream is collected in the volume control tank and reused in the' primary coolant system. . ' The CVCS is used to control the primary coolant boron concentration by diverting a portion of.the treated letdown stream to the boron recycle subsystem of the CVCS as shim bleed. The f

staff estimated the baron recycle systam input from the CVCS letdown stream to i be approxicataly 1070 gpd/ reactor.

Primary coolant grade water-from equipment drains, from equipment leakage, and F

from relief valves inside containment is collected in the reactor drain tank and equipment drain tank. .The staff estimated the baron recycle system inout from the reactor and equipment drain tanks to be approximately 475 gpd/ reactor.

The 1870 gpd shim bleed and 475 gpd input from the. reactor and equipment drain-tanks is collected in two 56,000 ga_1 holdup tanks. The shim bleed feed is processed through one of two boron recycle system mixed-bed domineralizers before it enters the holdup tanks. Liquid collected in the holdup tank is processed in batches through a 15 gpa boron recycle system evaporator, a condenser, and a baron recycle system' evaporator condensate domineralizar. A stripper column removes dissolved gases from the vapor body zone of the evaporat:

The processed ifquid is either returned to the primary coolant system; stored in a holdup tank, or released to the Squaw' Creek Reservoir through the LWPS discharge header. In its evaluation, the staff assumed that approximately 10%

-of the treated process stream from the boron recycle system is released to the-Squaw Creek Reservoir through the UIPS discharge header.

11.2.1.2 Liquid Waste Processing Subsystems l

l The LWPS consists of three subsysteess: the tritiated waste subsystem, the nontritiated waste subsystem, and the laundry and hot shower drain subsystem.

Each reactor unit also has a steam generator blowdown system and a condensate cleanup system.

Tritiated Waste Subsystem Tritiated wastes are processed through the tritiated waste subsystem and recyc' to the CVCS for reuse through a 5000 gal wasta evaporator condensate (recycle monitor) tank. The' tritiated waste subsystes consists of a 10,000 gal waste holdup tank, a 15 gpa wasta evaporator, and a mixed-b2d polishing domineralizer.

Tritiated wastes from valve and pump leakoffs, equipment drains, and plant samples are collected in the wasta holdup tank at an input flow rate of approxi-mately 300 pd per reactor. This waste is processed through an evaporator and a polishing desintralizer, and after sampling and analysis, the liquid collected in the wasta evaporator condensate tank will-normally be recycled to the primary coolant system for reuse.

The decontamination factors listed in Table 11.3 were applied for radionuclides removal in the tritiated waste subsystem. In its evaluation, the staff assumed that 10% of the tritiated waste condensate is discharged to the Squaw Creek Reservoir through the LWPS discharge header.

V.

1 J

11-8 / - - - - _ _ _ _ _

.', Enclosure.to TXX-89636

Mgust 31,1989 '

"~ Pago 42 'of: 58

'The staff has' evaluated the solid radwaste treatment for normal operation, including anticipated operational occurrences.

The staff estimates that th-

volume 3 and radioactivity level of solid waste shipped offsite will-be 17,0t 2 ft 3/ r/ reactor of solidified wet waste, containing 22 ft / r/ reactor of dry solid waste, containing no more,000 than Ci,5and 4100cr.

Ci/reac 11.2.3.1 Conformance With Federal Regulations and Branch Technical Positions The solid radwaste system is housed in the fuel building, which is designed to meet Regulatoryseismic Catagory Guide 1.143. I Storage criteria, and, therefore, meets the guidarce givsn in facilities for solid waste include an area in the fuel building for approximately 35 50-ft3 containers.and 50 55 gal drums.

Based on the staff's estimate of'the expected solid waste volumes and the recommendation in SRP 11.4 that at least 30 days' storage capacity be providea for packaged solid radweste from each unit, the staff finds that storage capacityoperation.

normal adequate for meeting the demands of Comanche Peak Unit 1 during In Amendment 22, the applicant committed to providing additional storage space prior to the licensing of Unit 2. On the basis of its evaluation of the solid radwaste system, the staff concludes that the system design cannot accommodate the radwastes expected during normal operations including anticipated operational occurrences. The packaging and shipping of all wastes are in ac'cordance with the applicable requirements of 10 CFR Parts 20 and 71 and 49 CFR Parts 170-178.. From these findings the staff concludas that the solid radwaste system is acceptable; however, the staff will review the adequacy of the additional' storage space for meeting the station's demands before the license for Unit 2 is issued. The results of the review will be

. reported on a supplement to this SER. l 11.3 Process and Effluent Radiological Monitoring Systems l

l l The process and effluent radiological . monitoring systems are designed to (1) provide information concerning radioactivity levels in systems throughout the plant, (2) indicate radioactive leakage between systems, (3) monitor equipment performance, and (4) sontter and control radioactivity levels in plant dischargos to the environment. -

Table 11.6 provides the proposed locations of continuous monitors. Monitors oncertaineffluent-releaselines..wil]automatfcalp'erskata,dischargesif radiation ' levels exceed a predetermined value.

0.

-r Systems which are not amenable to continuous monitoring, or for which detailed isotopic analyses are required, are periodically sampled and analyzed in the plant laboratory.

The staff has reviewed the locations and types of effluent and process monitoring provided. Based on the plant design and on continuous-monitoring and intermittent-sampling locations the staff har concluded that all normal and potential release pathways are m,onitored. The staff has also determined that the sampling and monitoring provisions are adeqate for detecting the leakage of radioactive material to normally uncontaminated systems and for monitoring plant processes which could affect radioactivity releases. On thie l- J

, 11-16 y

3 lEnclosure to TXX-89636 Au' gust 31, 1989-Page 43-of 58:

n Table 11.6 Process and effluent monitors *

' Stream Honitored Type Detector Nuncar Monitor Sensitivity Liquids:

Component cooling water -

y Scintillation 3/ reactor 1x10 5 uCi/cm3 (Co-5' Service water effluent y Scintillation 2/ reactor 1x10.s uCi/cm 3 Co-5i Laundry and hot shower recycle y Scintillation 1 shared 1x10.s uCi/cm 3 ((Co-Liquid wasta effluent ** . y Scintillation 1 shared 1x10 8 uCi/cm3 (Co-st.

Bort,n recovery system distillate y Scintillation 1 shared 1x10 3 uCf/cm 3 Letdown system GM Ureactor 1 uCi/cm 3 ((Co-Co-6(

Condensate domineralizer input y Scintillation 1/ reactor 1x10.s uCi/cm3 (co-5' Condansate domineralizer cutput y Scintillation 1/ reactor 1x10.s uCi/cm3 Auxiliary steam condensate y Scintillation 1 shared 1x10.s uCi/cm3 (C Co-5J Turbine b1dg drain input ** y Scintil.lation 1/ reactor 1x10.s uCi/cm3 ((Co-Waste monitor tank input recycle y Scintillation 1 shared 1x10.s uCi/cm3 (Co-6 Gases:

g Plant vent stack monitoring system - Auxiliary Building ***

3

]

p Scintillation 1 shared 1x10.s 5x10 11 uCi/cm3 (Xe-1 3r Gas Particulate p Scintillation 1 snared uCi/cm -(Cs-1 Iodine y Scintillation 1 shared 4x104 cpm /uCi (I-131 Containment monitoring system . Safeguards Building ** .

Gas p Scintillation 1/ reactor 1x10.s uti/cm3 (Xe ~.)

Particulate p Scintillation 1/ reactor 5x10 11 uCi/cm3 (Cs i Iodine y Scintillation 1/ reactor 4x104 cpm /uci'(I- !

Plantventductmonitor(gas)*** $ Scintillation 1 shared 1x10 ' uC1/cm3 (Xe 3

J Auxiliaryb1dgventilationduct(gas) p Scintillation 1 shared 1x10 4 uCi/cm'(Xe Condenser vacuum pump went (gas) p Scintillation 1/ reactor 1x10.s uCi/cm3 (Xe !

GWPS monitor (gas) inlet p Scintillation 1 shared 1x10 1 uCi/cm3 (Xe i HVACroomventdat(gas) e Scintillation 1 shared 1x10 4 uCf/cm3 (Xe 3

Fuel b1dg vent duct (gas) p Scintillation 1 shared 1x10 4 uCi/cm3 (Xe-;

Safeguards b1dg vent duct (gas) p Scintillation 1/ reactor 1x10 4 uCi/cm (Xe-:

"All 11guta anc gaseous effluent streams will De monitored in accorcance witn the guice- 1 lines of Regulatory Guide 1.21.

- Terminates discharge by closing isolation valve when the radioactivity level exceeds a predetermined value.

- - Terminates discharges from GWP5 control room ventilation exhaust, and containment purge:

ventilationwhentheradioactivItylevelexceedsapredeterminedvalue. l 9

o _ _ _ _ _ _ __ __ ___ _ __

11-1

n=---__ _ _ _ _ _

9 Enclosuro to.TX'X 89636 l Au' gust 31, 1989 !

- Paga 44-of 58< '

l i

basis, the staff considers that the monitoring and sampling provisions meet- y the requirements of GDC 60, 63, and 64 and the guidelines of Regulatory Guide 1.21. V l 11.4 Evaluation Findings '

In its evaluation, the staff calculated releases of radioactive materials in liquid and gaseous effluents for normal operation (including anticipated {

operational the plant.

Occurrences), based on axpected radwasta incuts ever the lifa of 1 The staff determined that the applicant's proposed design of the liquid and gaseous waste treatment systams satisfies the design objectives of Appendix I to 10 CFR Part 50. The staff has cencluded that the liquid and gaseous radweste treatment systems will reduce radioactive materials in effluents to ALARA levels in accordance with 10 CFR Part 50.34a and, there-fore, are acceptable.

The staff has cohsidered the potential consequences of reactor operation with a 1% operating power fission product source term and has determined that, under these conditions, the' concentrations of radioactive material ~ in liquid and gaseous affluents in unrestricted areas will be a small fractivr. of the limits specified in 10 CFR Part 20.

The staff has considered the capabilities of the radwaste systems to meet" demands that result frem anticipated operational occurrences and has concluded that the liquid and gaseous waste system capacities and design flexibilities are adequate to meet the anticipated needs of the plant.

The staff has reviewed the applicant's quality assurance provisions for the radwaste systems, the quality group classifications used for system components, the seismic design applied to the gaseous waste processing system, and the seismic classification applied to the design of structures housing'the radwaste-systems. The design of the radweste iystems and structures housing these systems meets the guidelines set forth in Regulatory Guide 1.143.

~

The staff has reviewed the provisions incorporated in the applicant's design to control the releases of radioactive materials in liquids as a result of inadvertent tank overflows and has concluded that the measures proposed by the applicant are consistent with the acceptance criteria set forth in Regulatory Guide 1.143.

o-The staff review 6f the radiological process and effluent monitoring system

- included the provisions for sampling and monitoring all normal and potential effluent discharge paths in conformance with GDC 64, for providing automatic i termination of effluent releases and ensuring control of releases of radio- I active materials in effluents in conformance with GDC 60 and Regulatory Guide 1.21, for sampling and monitoring plant waste process streams for process control in conformance with GDC 63, for conducting sampling and analytical programs in conformance with the guidelines in Regulatory Guide 1.21, and for monitoring process and effluent streams during postulated accidents. The ;

review-included piping and instrument diagrams and process flow diagrams for i the liquid, gaseous, and solid radweste systems and ventilation systems, and the location of monitoring points relative to effluent release points. The staff concluded that the applicant's radiological process and effluent monitoring systems are acceptable. s.

11-18. / _ - -

, .. Enclosure to TXX-89636 Au* gust 31. 1989 Page 45 of 58 areas wi'th progressively greater potential contamination; (2) maintaining, where applicable, areas at slight negative pressure to avoid the release and/or spread of airborne radioactive material to other areas; and (3) providing an enviren-mentally suitaple and radiologically safe environment for control reem oc::carcy under normal and postaccident conditions in accordance with 10 CFR Part 50.

The design criteria agree with those given in Regulatory Guide 8.8, and atmos-pheric cleanup units conforn to Regulatory Guida 1.52 with resoec to oc'cupational exposure. Therefore, the Comanche Peak ventilation system is acceptable, 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation The applicant's area radiation monitoring system is designed to (1) monitor the radiation levels in areas where personnel may be rquired to work; (2) alarm locally and in the control room ~when the radiation levels dxceed4 reset levels to warn of abnormal radiation levels in areas where radioactive material may be present; (3) provide a continuous record of radiation levels at key locations throughout the plant; (4) use geiger counters for monitoring lower level radia-tion and ionization chambers for the higher levels. Each of the area radiation monitoring systems, consisting of 28 monitors in Unit 1 and 25 in Unit 2, is equipped with a remotely operable check source at each detector and will alarm whenever circuit failures occur.

The design objectives of the airborne radioactivity monitoring system include the fo11cwing: (1) to assist in maintaining occupational radiation exposure I to airborne contamination At. ARA; (2) to check on the integrity of increasing radioactivity levels; and (3) to warn of potential . overexposure to airborne radioactivity. The staff finds these design objectives acceptable.

Twelve airborne radioactivity monitoring systems are installed in buf1 dings where potentially radioactive sources exist. .The sensitivity of the continuous air monitors will allow detection of less than one maximum permissible concentra-tion in air within the cubicles monitored. When a building vent monitor alarms, the source location within the building is identified by means of collecting local air samples in specific areas. The applicant also plans to conduct routine surveys for airborne radioactivity in all normally occupied plant areas I with portable continuous air sonitors. All installed instruments have indepen-dont emergency battery power supplies that are activated whenever a power failure occurs. Emergency power is also provided for all accident monitoring I

systems.

i The staff finds that the applicant's area radiation and airborne radioactivity h' monitoring systems satisfy the design objectives of Regulatory Guide 8.8 and are acceptable.

12.4 Dose Assessment The applicant has based his estimate of annual man-res exposure on experience from currently operating reactors and the way Comanche Peak has been designed and will be operated. He has performed an assessment of the doses in accor-dance with Regulatory Guide 8.19. The assessment considers doses that will be received by plant and contractor personnel based on occupancy factors in zones to be occupied, the dose rates in these zones, estimates of occupancy times, d and the personnel necessary to perform the various tasks involveo in plant 4 /12-5

.- .Ensicsure to TXX-89636 Adgust 31', 1989 is '

Paga 46 of 58 Index Page for Bullets SECTION 11 - RADI0 ACTIVE WASTE MANAGEMENT 11.3 Process and Effluent Radiological Monitoring Systems PRPB 4. The FSAR has revised the description of monitor-microprocessors to reflect as-built design.

PRPB' 7. The FSAR has been revised to avoid misinterpretation of MDA/MDC values.

PRPB 8. The FSAR has been revised to indicate that containment ventilation isolation is initiated by the particulate or noble gas channels.

SECTION 12 - RADIATION PROTECTION 12.3 Radiation Protection Design Features PRPB. 1. The FSAR has revised and updated the R.P. program to adopt / incorporate current standards or guidelines and to reflect current organizational structure and as-built design.

e-

, Enclosure to TXX-89636 August 31.L1989 PagG 47 of 58 .

SECTION 11 - RADI0 ACTIVE WASTE MANAGEMENT 11.3-Process and Effluent Radiological Monitoring Systems PRPB 4 The FSAR has revised the description of monitor microprocessors to reflect as-built design.

11.5-10. 18 2 Modifies RMS. the description of the microprocessor-based Correction:

These changes are made to reflect the capability of the as-purchased equipment in that local alarms and dis-plays are not provided for all monitors.

FSAR Change Request Number: 89'-465.04 Related SER Section: 11.3 SER/SSER Impact: No 11.5-15' 2 Modifies the text describing data storage by~the local microprocessors when the control room displays and computers are down.

Correction:

This change more accurately reflects the current design since local data indicaticn is not provided for all monitors.

FSAR Change Request Number: 89-465.07 '

Related SER Section: 11.3-SER/SSER Impact: No 11.5-16 2 Deletes that portion of the text indicating that the monitor trends are displayed at the alert limit.

Correction:

This change reflects the current design ment. of this equip-a FSAR Change Request Number: 89-465.08 Related SER Section: 11.3 SER/SSER Impact: No PRPB 7. The FSAR has been revised to avoid misinterpretation of MDA/MDC values.

D 11.5-8, 23 2 See Page No(s): Table 11.5-1. sh 1 to 5 Deletes reference to the term "MDA" on pg. 11.5-8 and, in Table 11.5-1 (where it is identified as "MDC")

adds the applicable Nominal Instrument Ranges; also, on pg. 11.5-23. indicates which range is being discussed.

Correction:

These changes are made to avoid misinterpretations of the MDA/MDC values that had been specified and to achieve consistency with Table 12.3-8.

(Note that the values for the Nominal Instrument Range always envelop the design basis values of the Specified Instrument Range.)

FSAR Change Request Number: 89-465.03 Related SER Section: 11.3

- SER/SSER Impact: No

. Enclosure to.TXX-89636 Adgust 31. 1989

-Pagi 48 of 58 SECTION 11 - RADIOACTIVE WASTE MANAGEMENT 11.3 Process and Effluent Radiological Monitoring Systems PRPB 8.

The FSAR has been revised to indicate that containment ventilation isolation is initiated by the particulate or noble gas channels.

11.5-22 2 Modifies the description of the Containment Monitoring System by indicating that Containment ventilation iso '

lation is initiated by the particulate ond-noble gas channels.

Correction:

This change is made to be consistent with an' earlier change (identified in Figure 7.2-1, sh 8) that removed the iodine channel from providing this trip signal.

FSAR Change Request Number:- 89-465.12 Related SER Section: 11.3 SER/SSER Impact: Yes Table 11.6 of the SER should be revised by correcting the footnote for the Containment monitoring system to reflect deletion of the iodine channel from initiating Containment ventilation isolation. ESFAS function (12) listed in Section 7.3.1 should be revised similarly.

Table 11.5-3. sh 1 2 Deletes the automatic control action (i.e., Containment i ventilation isolation) associated with the Containment iodine monitor.

Correction:

This change is made to be consistent with an earlier change identified on Figure 7.2-1, sh 8.

FSAR Change Request Number: 89-465.17 Related SER Section: 11.3 SER/SSER Impact: Yes SER Sections 7.3.1 (see ESFAS function 12) and 11.3

_ (see table 11.6) should both be revised to r,eflect the fact that a Containment icol . . ion signal is no longer 0- derived from the iodine enam el of the Containment monitoring system.

I

. Enclosure to TXX-89636 Au* gust 31. 1989

~Page 49 of 58 SECTION 12 - RADIATION PROTECTION 12.3 RadiRtion Protection Design Features PRPB 1. The FSAR has revised and updatsd the R.P. program to

- adopt / incorporate current standards or guidelines and to reflect current organizational structure and as-built design.

12.3 2 Deletes the automatic *onitoring checking capability for those high rangs area monitor ionization detectors that are provided with check currents for testing the electronic circuitry of the monitor (in lieu of using a radiation sourca).

Correction:

This change is'made to reflect the capability of the as-purchased equipment and is consistent with the pro-cedures for radiation monitor checking using radio-active sources.

FSAR Change Request Number: 89-465.29 Related SER Section: 12.3.4 SER/SSER Impact: No 12.3-57 2 See Page No(s): check Deletes two of the typical tests used to functionally check the ARMS microprocessor circuitry.

Correction:

This change is made to refleet the capability of the

., as-purchased equipment.

FSAR Change Request Number: 89-465.20 Related SER Section: 12.3.4 SER/SSER Impact: No 0-l 1

l

3 .Enclos'ure to TXX-89636 August' 31, 1989 CPSES/FSAR Page 50 of 58

4. Dedicated microprocessors dddifft p/dtdisd/d difH Id/d7 dispidf J 76 ddd tdditd7d for each monitor ddfdttdt-

5. Remote displays and controls on process system operator panels 46

6. Monitors with associated equipment 46

7. Control Room equipment racks (two) furnished with display / control 76 modules for selected monitors The system concept is a distributed data base with each individual monitor processor maintaining its own data base and stored data. A 76 stand-alone configuration includes redundant minicomputers in two CRT

~

consoles that handle five loops of up to 31 monitors per loop. Alarm messages are sent to the Control Room from the detector microprocessor when polled by the RM-11 console. The requested information is then returned to the RM-11 consoles, where they are displayed, printed, and announced. Alarms are displayed in various display formats.

Operator-initiated display requests cause console requests for data

-from the monitor processors. The console minicomputers contain the 76 communications links to the monitor processor loops and the necessary memory and programming to provide overall system status, monitor group profiles, and individual monitor trend displays. These minicomputers are interconnected to p' ovide alternate communications paths, thus l

tolerating a single communications cable fault or t.onitor malfunction I

without loss of function in the system. In addition to the display requests from the keyboard, other control-functions such as check-source readings, pump motor control, and purge control are provided.

Certain radiation monitor channels are seismically qualified 27 throughout, because of their importance to the safe operation of the plant. These channels are capable of withstanding a Safe Shutdown Earthquake (SSE). Dedicated control / display modules on seismically 76 qualified cabinets for the containment air monitors, plant vent l

Bold /0verstrike 11.5-10 Version

~ ^

[ ;)

~

.f..... .. Enclosure to TXX-89636 Adgust 31 1989 CPSES/FSAR i Paga 51 of 58 l l 76 The group profile display shows a horizontal bar of current radiation for'each monitor in a selected group. Each horizontally displayed bar is normalized to place its alert-alarm at a percentage of scale and is colored to show its status. The group's radiation 7rofile is therefore shown relative to the alert condition. The detailed information consists of the absolute value of current radiation for each monitor, the engineering units of each value, each monitor number, and a description of up to 16 characters for each monitor.

The two console microcomputers communicate with each other, with the remote monitor assemblies, and with the report computer. The serial bit communication lines operate synchronously at the standard rate of 4800 baud (transmission rate of computer messages, bits /sec). The communication and error ~ recovery procedures are subsets of IBM's BSC/BTAM, 11.5.2.5.4 Report Computer The report computer collects dffidddf dddffd/ did/dddi didt Wdtiddd J 76 fidd pdtidds ftdd fMd tddddId tddpdtd/ ddd data from meteorological iitstrumentati on. This data may be used to generate periodic .

/ddidddtlfdd dffldddf (didddd repcrts in accordance with NRC Regulatory Guide 1.21. Section 2.3.3.2 discusses the process for accumulation of data by the report computer.

1 D:

l l

Bold /0verstrike 11.5-18 i

Version 1

_________________-__-____m

-s , inclosuro to TXX-89636-Adpust 31, 1989 CPSES/FSAR Page 52 of 58 11.5.2.5.2 Monitoring Assemblies Each monitoring assembly is the equivalent of a digital ratemeter.

Each console with its color CRT display, keyboard, and printer is a 66 remote digital display and recorder for the monitoring assemblies.

All field wiring for communication circuits consists of twisted- 76 shielded pairs that are daisy- chained from monitor to monitor.and to the display cabinets. Each monitor processor and the display consoles are furnished with safety related or reliable non-safety related power (backed by diesel /non-safety related station batteries) as applicable.

At each monitor, control, data processing, data storage, and 76 multilevel alarming are all performed by the local microprocessor independently from the rest of the system. If Control Room displays and computers are down, fMd ddtd if didH iddifdt tddffdddi fd Ed f tstitiddl ifdtidl didtiidl ddd fr\dilitdd 1did11fl the data stored ,

l g. ally at each individual monitor are available for later communication f6 fMd fddttd1 Rddd dddddidd when the Control Room displays and computers tddddidd are back on line. The hourly and daily averages are stored, and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months may pass without loss of those averages. . Twenty-eight days may pass without loss of daily averages. 66 No data need be lost as a consequence of multiple failures in the equipment common to all monitor channels.

The microprocessor at each radiation monitor assembly is an Intel 8085A with semiconductor memory to control the monitor, to process and store data, and to communicate messages through intervening monitors to either of the Control Room consoles. 76 76 f.

l 1

j. 11.5-13 Bold /0verstrike Version

+

,A Enclosura to TXX-89636 August 31, 1989 CPSES/FSAR

- Paga 53 of 58 and control relays. Resets the local horn. Issues a status message to the Control Room consoles when the'alara status changes.

g. At the appropriate stage of processing, tests for the other alare conditions listed previously L

h. Checks for data validity (see Subsection 11.5.2.5.1) and

. marks each stored ~value questionable if the majority of its counts are not valid

i. Maintains a rotating file of past values of radiation data: 52 24 10-min averages, 24 1-hr averages, and 28 1-day averages J ditddds tHd (dditidd'deld itdtdf if ddtd tMid Mdif df tHd ,

didtiddd ididdi d/d (dddfidddWidt if dddd ididdd did .

.diditi6dd61dl intRi t>d did/d11 did/did ditiddtid INRt Ridd1didtf 6didd 112111 11 Idit tMid 10 $dttidt 4/4 ditiddtidi intRt 154 didtd11 did/ddd 166ddl1.

j. Uses a specification table (conversion factor, etc.) to control the processing. All entries for a monitor's specifications are sent as messages to that monitor's microprocessor, where they are stored in the specification table. See Subsection 11.5.2.5.2 l 76 11.5.2.5.3 Control Room Consoles The microprocessor-based system with two operator consoles and report computer is a complete, stand-alone system, as shown on Figure 11.5-1.

The consoles are dedicated to radiation monitoring and function independently of the plant computer.

Bold /0verstrike 11.5-16 Version

.y

,, . Incicsero to TXX-89636

, .. . .Au' gust 31, 1989 CPSES/FSAR Page 54 of 58 monitoring points are indicated schematically on diagrams referenced in Table 11.5-1. Monitors are provided for the following:

1. Process streams that normally discharge low level activity directly to the environment.

2. Continuous process streams that discharge directly to the 76 environment but do not normally carry radioactive material.

Such mon (toring indicates if any radioactive leaks into these process lines have occurred.

3. Process lines which contain radioactivity but do not normally discharge to the environment. Such monitoring indicates if j process malfunctions have occurred.

l52 11.5.2.3 Exoected Radioactivity Concentrations and Quantity Measured The expected radiation levels in the process and effluent streams are 76 such that concentrations in gaseous effluents at the Exclusion Area Boundary and liquid effluents at the discharge point are a small fraction of 10 CFR Part 20 limits. The calculation of radioactive concentrations and the levels to be monitored or sampled are described in Section 11.1 and Table 11.5-4.

Each channel, except the iodine monitors, measures gross radioactivity.

11.5.2.4 Detector Tvoe. Sensitivity. and Ranoe 27 The range of each detector, along with other pertinent information 27 such as detector type and reference nuclide dM MBAl are summarized in Table 11.5-1.

Detector location and sample line routes from sampling point to 27 1

detector are chosen to minimize sample line length, and the number of Bold /0verstrike 11.5-8 Version

t' I

. , . - Epclosure to'TXX-89636 s August 31, 1989 CP3ES/FSAR L Page 55 of 58 unidentified leakage to the Containment, is sufficiently sensitive to detect an increase in leakage rate, or the equivalent of one gpm in less than one hour. Indicators and alarms are provided in the Control )

Room. A complete description of the leakage detection system is l presented in'Section 5.2.5.

11.5.2.6.3 Plant Vent Stack Monitoring Syscem 27 Each plant vent stack is equipped with a particulate, iodine.- and gas 76 v (PIG) monitor. They are off-line monitors that sample the plant vent effluent prior to discharge and are similar to the Containment monitors.

TheplantventstackPIGmonitohsdrawrepresentativeairsamplesfrom 76 the plant vent stack via isokinetic nozzles in the stack, and directs them through moving filter paper viewed by shielded beta-sensitive scintillation detectors. The sample streams then pass through an iodine adsorber cartridge, where collected iodine is viewed by shielded gamma-sensitive scintillation detectors. This channel is

-intended primarily for I-131 monitoring. A single channel 27 differential discriminator is used with the window centered on the I-131, 0.364-MeV photopeak. Lead shielding is provided to reduce 76 background to levels that allow the detection of the specified instrument ranges given in Table 11.5-1.

A collector type-monitor is selected for this application in view of 27 the very low iodine-emission rates permissible. Because the monitor is of the collector type, it does not have a definite sensitivity threshold determined solely by background, as with the other plant radiation monitors. The quantity of interest is the rate of increase 54 of the count rate of the built-in scintillator, which is a function of sample-stream I-131 concentration, 11.5-23

p . 4 Enclosure to TXX-89636' i ,;.t ugust A 31. 1989 CPSES/FSAR Pags 56 of 58

.76- viewed by a shielded gamma-sensitive scintillation detector. The particulate filter tape and iodine filter are replaced as required to support operation of the monitor. When the sample air leaves the 76 iodine cartridge it is directed through a closed system to a shielded stainless steel gas sampling chamber viewed by a beta-sensitive scintillation detector. The sampled air is finally returned to the Containment atmosphere. Indication and annunciation are provided in 31 the Control Room. The detection of high radiation levels by the particulate or noble gas channels causes the high-level set point to trip and initiates Containment Ventilation Isolation. The Containment air particulate, iodine, and noble gas monitor is installed in a single housing mounted on a skid with equipment that is described as follows: ,

1. A flow-control assembly, that includes a pump unit, comprised of

- the following:

a. A pump to obtain the air sample

b. A flowmeter to indicate the flow rate

c. A flow-control valve to provide flow adjustment

d. A flow switch

e. A flow controller

f. A vacuum gauge 76 2. System sensing units with indications provided on the RMS console and control / display module on a seismic cabinet for the following:

g- a. Filter stepping

b. A low-flow alarm on the RMS console

c. A high pressure alarm The particulate and gas monitor are also used as part of the RCPB leakage detection system. The sensitivity and response time of this part of the leakage detection system, which is used for monitoring

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' g ' August 31, 1989J Page 58 of-58 CPSES/FSAR

[76' such' that_ loss of check source actuation power will cause-the-source to return to a shielded position. Highte range area monitor ionization detectors have ranges that are too high to-check with radiation sources. These are provided'with check currents that test the electronic circuitry of the monitor.

These monitor, checking capabilities are remotely operable from t.he control room Add d/d (dtiddiddiff difdddffdd77f idiffdtdd.

g TNdf ddf didd-5d ddddd77f idiffdfddl These checks provide L 9nvenient operational checks'of these monitors. Additionally, he radiation check source provides a~ gross response check of the detector.

System operability may be verified by observation of channel

.. behavior or by use of the check source or current. Any detector whose response- cannot' be verified by these methods ma'y have its response checked with a portable check source.

6. - Test Calibration Circuitry Each monitor microprocessor contains self-checking diagnostics in its ROM, a rotary switch on a printed circuit (PC) card to select each diagnostic program, and a red and green light (also on each PC card) to show the result of each diagnostic test. These allow the microprocessor board to be functionally checked while installed in its enclosure. Typical tests include the following:

, a. Communication loop (continuity)

Wl RAM b d. ROM di PdTid ddddffdd (TidNt MIfdKdJ c d. Local indicator d f. Local alarms Bold /0verstrike 12.3- 57 Version _ _ . _ _ _ _ _ _ _ _ _ _ _ _

TXX-8963, Forwards Advanced FSAR Change Re Clarification of Radiation Monitor Parameters,Including Related Ser/Sser Pages & Index Page for Bullets

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SUBJECT:

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TXX-8963, Forwards Advanced FSAR Change Re Clarification of Radiation Monitor Parameters,Including Related Ser/Sser Pages & Index Page for Bullets

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