ML20086A715
| ML20086A715 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/08/1983 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RBG-16313, NUDOCS 8311160085 | |
| Download: ML20086A715 (31) | |
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GULF STATES UTILITIES COMPANY POST OFFact nOx 2952 . O t' A U M O N T . TEXAG 77?OJ AR EA CODE 4016 9 ) e c- 8 31 November 8, 1983 RBG-16313 File Code No. G9.5 G9.8.6.2 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Schwencer:
River BendLStation Units 1 and 2 Docket No. 50-458/459 Enclosed are Gulf States Utilities Company responses to-the open items
. identified in the Draft _ Safety Evaluation Report by the Meteorological and Effluent Treatment Branch (METB) and to those items identified-in the Staff's April 6, 1983 letter. Enclosure 1 of this letter summarizes the open items and indicates changes to be made in the River Bend Station FSAR. Enclosure 2 includes a brief discussion of' each open item, the action used to resolve it, and a summary of the response. Finally, Enclosure 3 thru 5 contain'the actual written chat.ges to the FSAR as well as'all-accompaning inserts, tables, and figures. These changes will be incorporated into'the next amendment of the FSAR.
Sincerely, O!kok!g [.
'J. E. Booker-Manager-Engineering,
' Nuclear Fuels & Licensing River Bend; Nuclear Group JEB/JWL/kt- -
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ENCLOSURE 1 ITEM DSER SUBJECT FSAR NUMBER SECTION DESCRIPTION CHANGE 1 11.1 Pg 11-1,3 Solid Waste Processing 11.4 Pg 11-20,21 System and Instrumentation See Enclosure 2 11.5.4 Pg 11-25 Description 11.2 -
2 Apri:1. 6, 1983 Liquid Radwaste Tank or Amendment 5 letter Component Failure Minimum Residence Times 3a 6.5 & 9.4 For All Ventilation System See Enclosures 2 & 3 April 6 letter Charcoal Adsorbers 3b 11.3.1 Hydrogen Explosion and April 6, letter Relief Protection Features See Enclosures 2 & 4 For The Main Condenser, Air Ejectors & Inner Coolers 4 15.7.1 Pg 15-40 Noble Cas Effluent See Enclosure 2 & 5 Monitor 5 15.7.2 Pg 15-40 Sampling and Analysis See Enclosure 2 & 5 of Plant Effluents L
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ENCLOSURE 2 Item No. 1 Solid Waste Processing System In addition to being identified as a DSER open item, this issue was also transmitted as Question #460.001 and #460.006. The River Bend Station (RBS) Radioactive Waste Solidification System will utilize the Chem-Nuclear Mobile Cement Solidification System described in CNSI Topical Report CNSI-2 Revision 2, dated Janaury 1983. The NRC has found this report acceptable for referencing in License Applicatf or.s as documented in Mr. Cecil 0. Thomas' (NRC) letter to Mr. James P.
Stachr (CNSI) dated April 11, 1983. RBS FSAR Section 11.4 will be revised to reflect the CNSI System including the information in the enclosure to Mr. Thomas' letter, and will be transmitted to the NRC Staff in January 1984.
Item No. 2 Liquid Radwaste Tank / Component Failure This DSER open item was previously ret uested in Question #460.005 and i
answered in Amendment 5 to the FSAR (see Section 15.7.3).
Item No. 3a Minimum Residence Times All RBS ventilation system charcoal adsorbers have a minimum bed depth of 4 inches and a minimum residence time of 0.5 seconds. This information is already provided in the referenced FSAR Sections for the following systems:
- 1. Standby Cas Treatment System Section 6.5.1.2.1 Table 6.5-2
- 2. Control Room Charcoal Filtration Section 6.4.2.2 System Table 9.4-2 In addition, the following systems / sections will be updated to reflect these minimum residence times:
- 3. Fuel Building Charcoal Filtration Section 9.4.2.2.4, Pg. 9.4-18 System Table 9.4-3, Pg. 5/5
- 4. Radwaste Building Tank Exhaust Table 9.4-6, Pg. 2/3 Filtration System Note 3
- 5. Containment Purge Filtration Table 9.4-6, Pg. 2/3 System Note 3
- 6. Air Removal llogging Pump Table 9.4-6, Pg. 2/3 System Note 3 Refer to Enclosure 3 for details of the changes to systems 3 thru 6 above.
Item No. 3b Ilydrogen Explosion & Relief Protection The METB reviewers requested additional information regarding hydrogen explosion and relief protection features for the main condenser, air ejectors and inner coolers. In response, the RBS condenser air removal system does not have hydrogen analyzers; however, hydrogen
analyzers are provided downstream of the offgas system catalytic recombiners. During plant shutdown, a significant hydrogen build-up to explosive 1cvels is not possible because the main condenser will be isolated from the reactor.
Revised FSAR Sections 10.4.1.3 (Pg. 10.4-3) and 10.4.2.3 (Pg. 10.4-6) as well as Figure 10.4-1 (see Enclosure 4 ) delineate those provisions of the Condenser Air Removal System and Off Gas System available to monitor system operation.
Item No. 4 Noble Gas Effluent Monitor Item No. 5 Sampling and Analysis of Plant Effluents These DSER open items (Nos. 4 & 5) were transmitted to GSU via Question #460.007 and #460.002 and are in regard to TMI items II.F.1.1 and II.F.1.2 of NUREG-0737. The NRC Staff requested additional details to show a commitment for meeting the requirements of these TMI items. FSAR Table IA-1 and Section 11.5, " Process and Effluent Radiological Monitoring and Sampling System" were revised to incorporate clarifications and are provided as Enclosure 5.
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- 2. High pressure in the drywell
- 3. Reactor vessel low low water level.
The plant operator can stop one of the units from the rain control room after the startup is complete.
The charcoal filtration system, an engineered safety feature (ESF) , is designed to function following a LOCA or fuel handling accident and is designed to meet Safety class 3 and Seismic category I requirements. The detailed component system description and materials for various components is similar to the standby gas treatments units discussed in Sections 6.5.1.2 and 6.5.1.5, respectively.
Charcoal filter component sizing is governed by the following flow parameters:
- 1. Noisture separator is designed to remove at least 99 percent by weight of the entrained moisture in an airstream containing 0.005 lb of entrained moisture per cu ft and at least 99 percent by count of the 1 to 10 micron diameter droplets without visible carryover when operating at rated (10,000 cfm) capacity to twice rated capacity.
- 2. Prefilters are designed so that airflow through any standard 24 x 24 x 11 1/2 in cell does not exceed approximately 1,000 cfm.
- 3. High Efficiency Particulate Air Filters - both HEPA filter banks are designed so that air flow through any standard 24 x 24 x 11 1/2 in cell does not exceed app,roximately 1,000 cfm.
- 4. Charcoal Filter Bank - the effective face area of charcoal filter is designed so that the average air velocity through the charcoal bed does not exceed 40 ft/ min when the charcoal filter unit is operating at 10,000 cfm. Gas residence time in the l charcoal bed is a' minimum of 0.25 sec 7 Activated carbon material (4,250 lbs) similar in type to i Earnaby cheney 727 is provided for each charcoal l filter train to meet' the gas- flow and minimum residence time established herein.
per 2 inches of bed depth.
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+ e. Charcoal filters Type Rechargeable Filter efficiency for removal of elemental iodine (at 90% RH) 95%
Methyl iodide (at 90% RH) 95%
Filter pressure drop, in W.G.
(clean / dirty) 1.0/2.0
- f. Exhaust fan Equipment Mark No. 1HVF*FN 3A & 3E Type Centrifugal Airflow capacity, cfm 10,000 Static pressure, in W.G. 16 Speed, rpm 1,720 Motor, hp 40
- g. Decay heat removal exhaust fan Equipment Mark No. 1HVF*FN 7A 6 7B Type Centrifugal Airflow capacity, cfm 100 Drive Direct Static pressure, in W.G. 2.5 Motor, hp 0.5
% e. Charcoal Filters Type Deep bed, rechargeable Capacity 10,000 CFM Media Impregnated Coconut shell charcoal Radioiodine Removal 99% elemental iodine and 99% methyl iodine, test at 70%
relative humidity Depth of each bed 4 inches Face Velocity 40 FPM Pressure Drop, Clean 1.0 in. W.G.
Ignition Temperature 340 C Density 30 lbs/ft3 m '
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Radwaste Building Air Removal tank Exhaust Containment Purge Hogging Pump Paragraph No. Filtration System Filtration System System C-6 " Laboratory Testing Criteria for Activated Carbon" 6.a In compliance In compliance In compliance 6.b In compliance In compliance In compliance (1) Housing leak tests are performed in accordance with the guide, but ductwork leak tests are performed using the methods of the Associated Air Balance Council instead of ANSI N510-1975.
(2)For HEPA filters and adsorber mountings, requirements of ANSI N509-1976 Section 5.6.3 are complied with except for the tolerance requirements. Tolerances for HEPA filters and adsorber mounting frames are sufficient to pass the bank leak tests of paragraohs 5.c and 5.d of the guide.
(3) Bed depths of charcoal adsorber units at RBS are 4 in, with a minimum "Ostdence time of 0.5 g sec. verification of filter efficiency is the objective; thus HE'JA filters are tested in the shop and in the field for efficiency. Upon installation, and pe'iodically thereafter, the filters are DOP tested in accordance with ANSI N510-1975.
(4)Ixception is taken to Section 5.2.2.4 of ANSI N509-1976 which calls for a reans of compaction to unif orm density. Where uniform compaction can be demonstrated, compacting means are not required.
(5)1. System resistances are determined in accordance with Section 5.7.1 of ANSI N509-1976 except that fan inlet and outlet losses are not calculated in accordance with AMCA 201.
- 2. Exception is taken to Section 5.7.2 of ANSI N509-1976. Copies of fan ratings or test reports are not necessary when certified fan performarce curves are furnished.
- 3. Exception is taken to Section 5.7.3 of ANSI N509-1S'5. Balancing techniques specified need not be followed. Maximum permissible vibration velocity level method need not be complied with.
- 4. Exception is taken to Section 5.7.5 of ANSI N509-1976. Wht -4 AMCA certification ratings are submitted, documentation is not furnished.
(6) Airflow distribution is within 220 percent of the average airflow as tested in accordance with ANSI N510-1975. Turning vanes are provided only where a uniform air distribution cannot be achieved.
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ENCLOSURE 4 4
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RBS ESAR
'; gases, such as hydrogen, is precluded since the air removal
'7V system is in continuous operation.
INSERT =
The treatment of radioactive gases removed from the condenser by the air removal system is discussed in Sections 11.3.2 and 9.4.4.2.5. Since the condenser operates at a partial vacuum the possibility of gaseous outleakage is
- not considered during operation.
1 Some low level radioactive impurities are normally present in the liquida entering the condenser. The condensate s
demineralizers (Section 10.4.6) are designed to remove these impurities. Abnormal radioactive inleakage is detected by conductivity elements located both in the condenser hotwell and upstream of the condensate demineralizers. The source of the abnormal radioactive inleakage is then determined by a review of the systems discharging to the condenser. The system found to be causing the abnormal radioactive inleakage is either diverted to the liquid radwaste system s for processing or isolated from the condenser.
The retention pit located under the condenser collects liquid leakage out of the condenser and drains it to two sumps until the leakage can be stopped. Any liquid collected in these sumps is pumped directly to the liquid
- - g ., radwaste system for processing. The sumps are provided with
' y: level alarms and controls for automatic level control.
The turbine building ventilation. system is designed to control and monitor airborne radioactive contaminants (refer to Section 9.4.4 for further discussion). ,
Conductivity cells are provided in drip trays under the tube bundles to detect condenser tube leakage in any of the eight condenser bundles. The leaking tubes are identified 3 and repaired, plugged, or replaced during a unit maintenance outage. A motor-operated butterfly valve at each of four waterbox inlets and four waterbox outlets provides individual waterbox isolation while maintaining the station
! online at reduced capacity.. lIhe condenser hotwell contains
. two partitions parallel to the tubes to provide a minimum I 5-min effective detention of the condensate for the decay of radioactivity in the condensed steam.
Condenser materials were chosen to maximize performance and minimize corrosion / erosion. The majority of condensor tubes-are Admiralty metal, which is very corrosion-resistant. The air cooling sections and impingement sections of the tube bundles have 70-30 Cu-Ni tubes, chosen for hardness. The tube sheets are Muntz metal, chosen for both strength' and g Amendment 5 10.4-3 August 1982 l
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material. The steam jet air ejector inlet valves close on a low steam flow signal of 7,800 lb/hr to the second stage.
The shellside drains from the intercondenser are returned to the condenser.
Cooling water for the intercondensers is condensate from the discharge of the condensate pumps. Steam for the primary and secondary steam jets is taken from the main steam system cnd reduced to about 250 psig by prescure control valves.
10.4.2.3 Safety Evaluation During startup, 8 to 5 in Hg absolute pressure is obtained in the condenser by operation of both motor-driven air removal pumps. The discharge of the air removal pumps is passed through charcoal filters, described in Section 9.4.4, to limit its radioactivity before being released to the a tmosphere. Should the radiation monitor located in the discharge of the charcoal filters detect high radiation, the air removal pumps are manually shut off and the pump suction valve closed, thereby terminating the release to the atmosphere. Also, the air removal pumps are automatically shut off if high radiation is detected in the main steam s lines. ;
Each full-capacity air ejector is designed to remove air and noncondensable gases from the condenser during normal operation and exhaust them to the radwaste off-gas treatment system. An inventory of radioactive contaminants in the condenser air removal system is presented in Table 12.2-9.
The gaseous radwaste system, which treats the off gas prior to its discharge to the atmosphere, is discussed in Section 11.3. Provisions for the sampling and monitoring of radioactive materials in gaseous effluent from the air removal system are described in Sections 9.3.2 and 11.5.3.
The capacity of the ejectors is determined by taking into consideration potential air inleakage, the oxygen and hydrogen formed by disassociation of water in the reactor, and the water vapor contained in the air-gas mixture.
- INSERT r Loss of condenser vacuum due to the malfunction of an air ejector is extremely remote. Loss of condenser vacuum prevents the operation of the turbine bypass system. When condenser pressure reaches 7 in Hg abs, the turbine bypass valves close. Additionally, when the condenser pressure reaches 10 in Hg abs, the main steam isolation valves are closed, resulting in the opening of the main steam safety relief valves.
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INSERT Pg 10.4-3 During plant shutdown a significant hydrogen build-up to explosive 1cvels is not possible because the main ccndenser is isolated from the reactor. On lost of condenser vacuum, the condenser and main turbine exhaust hood are protected from excessive steam pressure by I
atmospheric relief diaphragms on the full throttle steam flow at a safe pressurelow pressure turbine (see Section 15, which passes Miscellaneous Devices, of the Turbine Manual).
INSERT Pg. 10.4-6 The valves steam are not jet air ejectors, intercondensers, associated piping and hydrogen detonation. specifically designed to withstand the effects of a The normal operation of the steam jet air ejectors flammable limits. Although aflow prevents the process to the offgas system from reaching significant reduction or loss of steam flow to the air ejectors could result flammable in the piocess flow reaching limits, the condenser air removal system has the following design features and instrumentation available to monitor system operation:
1.
The motive steam flow to the second stage jet is monitored in the
- main control room (see Section 10.4.2.5).
- 2. A significant reduction or loss of motive steam flow to the second stage jet automatically closes the ejector suction valves (see Section 10.4.2.5).
3.
Low motive steam pressure downstream of the regulating valve is indicated and alarmed in the main control room.
4.
Increased main condenser pressure due to the build-up of air and noncondensible gases is room (see Section 10.4.1.5). indicated and alarmed in the main control 5.
In addition to this instrumentation provided in the condenser air removal system, two (2) hydrogen analyzers are provided in the off gas system, downstream of the recombiners. These analyzers allow monitoring of hydrogen concentrations as an additional safeguard against the occurence of hydrogen detonation.
Tbc steam jet air ejectors intercondensers, associated piping and valves are provided with pressure relief protection (see Figure 10.4-1).
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RBS FSAR 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.1 Design Bases The process and offluent radiological monitoring and sampling systems are provided to allow datormination of the content of radioactivo material in various gaseous and liquid process and offluent streams. The design objective and criteria are primarily dotormined by the system designation of eithor:
- 1. Instrumentation systems required for safety, or
- 2. Instrumentation systems required for plant operation.
11.5.1.1 Design Objectives 11.5.1.1.1 Systems Required for Safety The main objectivo of radiat.fon monitoring systems required for safety is to initiato approprinto manual or automatic protective action to limit the potential rolcase of radioactive materials from the reactor vessel, primary and secondary containment, and fuol handling areas if prodotermined radiation levels are exceeded in major process /offluent-streams, and to protect main control room personnel throughout the course of an accident. Additional objectivos are to have these systems availablo under all oporating conditions including accidents, except as noted in the text, and to provido main control room personnel with an indication of the radiation levols in thn major process /offluent streams including alarm annunciation if high radiation levels are dotected. The radiation monitoring systems (RMS) provided to mont thoso objectivos are: l
- 1. . Main steam lino i
- 2. Reactor building. annulus. ventilation
- 3. Fuel building ventilation exhaust
- 4. Main control room air intakes
- 5. Main plant exhaust duct (extended range gas monitor)-
- 6. Containment and drywell atmosphere monitoring 11.5-1
RBS FSAR
- 7. Containment purge isolation 8 .' RHR heat exchanger service water effluent 11.5.1.1.2 Systems Required for Plant Operation The main objective of RMS required for plant operation is to provide i operating personnel with measurement of the content of radioactive '
material in all potentially radioactive effluents and significantly contributing process streams. This allows demonstration of compliance with plant normal operational technical specifications by providing gross radiation level monitoring and collection of halogens and particulates on filters (gaseous effluents) as required by Regulatory Guide 1.21. Additional objectives are to initiate discharge valve isolation on the off gas or liquid radwaste systems if predetermined release rates are exceeded and to provide for sampling at certain radiation-monitor locations to allow determination of. specific radionuclide content. The RMS provided to meet these objectives are:
- 1. For gaseous effluent streams
- a. Radwaste building ventilation exhaust
- b. Main plant exhaust duct (normal range monitor)
- 2. For liquid effluent streams
- a. Liquid radwaste effluent
- b. Cooling tower blowdown line
- 3. For gaseous process streams
- a. Off. gas pretreatment
- b. .Off gas post-treatment
- c. Auxiliary building. ventilation
- d. Containment purge-t i e. Mechanical vacuum pump discharge
- f. LTurbine building ventilation l
l- g. . Radwaste reboiler clean steam outlet i= l h. Seal steam evaporator _ clean steam outlet l [ 11.5-2
RBS FSAR-
- 1. Condensate demineralizer and off gas building ventilation
- j. Turbine gland seal discharge
- k. Standby gas treatment system effluent
- 4. For liquid process streams
- a. Fuel pool cooling and cleanup
- b. Turbine plant component cooling water
- c. Reactor plant component cooling' water 11.5.1.2 _ Design Criteria 11.5.1.2.1 Systems Required for Safety The design criteria for the safety-related radioactivity monitoring systems are that the systems:
- 1. Are designed to. Seismic- Category I criteria to withstand the effects of natural phenomena (e.g.', earthquakes) without loss of capability to perform their functions.
- 2. Perform their intended safety function in the environment resulting from normal, abnormal,_and postulated accident conditions.
- 3. ' Meet the reliability, testability, independence, and failure mode requirements of, engineered safety features (ESF).
- 4. Provide continuous outputs on main control room panels.
5.
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Permit checking of the operational availability of each channel during reactor operation with provision'for calibration function and instrument checks.
- 6. Assure-an extremely high' probability of' accomplishing their safety functions in the event of' anticipated oper2tional occurrences.
- 7. Initiate prompt-. protective action prior.to exceeding plant.
technical specification limits.
'8. Provide warning of ' increasing. radiation levels indicative 'of-
! abnormal conditions by alarm annunciation. ,
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RBS FSAR
- 9. Insofar as practical, provido annunciation to indicato power failure or component malfunction.
- 10. Register full-scale output if radiation detection exceeds full scale.
- 11. llave sensitivities and ranges compatible with anticipated radiation levels.
The safety-related radioactivity monitoring systems satisfy the applicablo General Design Critoria (GDC) of 10CFR50 Appendix A which are 60, 63, and 64. The systems meet the design requirements for Safety class 2, Seismic Category I systems, along with the quality assuranco requirements of 10CFRSO, Appendix B. 11.5.1.2.2 Systems Required for Plant Operation The design criteria for operational RMS are that the systems:
- 1. Provide indication of radiation levels in the main control room.
- 2. Provide warning of increasing radiation levels indicative of abnormal conditions by alarm annunciation.
- 3. Insofar as practical, provido annunciation to indicato power failure or component malfunction.
- 4. Monitor a samplo representative of the bulk stream or volume.
- 5. llavo provisions for calibration, function, and instrumentation checks.
- 6. llave sensitivities and rangos compatibio with anticipated radiation levels and technical specification limits.
- 7. Register full scalo output if radiation detection exceeds full scalo.
11.5-4
RBS FSAR The monitors installed on the containment purge system, the off gas system, and the radwaste treatment systems have provisions to alarm and to intitiate automatic closure of the discharge valves on the affected treatment system prior to exceeding the limits specified in technical specifications, as required by Regulatory Guide 1.21. The design base's conforms to applicable GDC of 10CFR50, Appendix A which are 60, 63 and 64. 11.5.2 System Description The process and effluent radiation monitoring system consists of a computer based digital radiation monitoring system (DRMS) and nondigital monitors supplied as part of the reactor protection system (RPS) ?nd off gas treatment system. 11.5.2.1 Digital Radiation Monitoring System The function of the DRMS is to measure, evaluate, and report radioactivity in process streams, in liquid and gaseous effluents, and in selected plant areas, and to annunciate abnormal system conditions. The process and effluent monitors, except as noted in Table 11.5-1, and area monitors in Table 12.3-1 make up the DRMS. Each monitoring channel has a microprocessor associated with the detector or sample station. The DRMS computer system continuously polls the microprocessors collecting and storing radiation levels, alarms and status information for these monitoring channels. This information is available on demand for analysis of plant conditions, trending of radiation 1cvels, and maintenance purposes. Associated with the DRMS computers is a dose assessment and report processor which collects meteorological tower data. For a more detailed description of the dose assessment system see FSAR Section 13.3. This information is combined with information from the gaseous effluent monitors to generate the gaseous release calculations for Regulatory Guide 1.21 report generation. l l Monitors are provided for the following gaseous release points: ! 1. Main plant exhaust
- 2. Fuel building ventilation exhaust
- 3. Radwaste building ventilation exhaust Isotopic composition for the-o effluent streams is determined by laboratory analysis and input to the DRMS/ DOSE-ASSESSMENT computer as required by the technical specifications.
11.5-5
I 4 RBS FSAR Liquid radwaste effluent data is determined by batch sampling before release in accordance with Regulatory Guide 1.21. The isotopic analysis is input to the DRMS computer. The liquid radwaste effluent monitor terminates the release if the technical specification limits are exceeded. All monitoring channels have three alarm states: alert radiation, high radiation, and monitor failure. Alarm's for all digital based process monitors monitor microprocessors and are annunciated at each DMS CRT console. Consoles are located in the main control room,-technical support center and emergency operations facility. System panels are provided in the main control room for safety-related monitors and post-accident monitors. -In the unlikely event of failure of the redundant central processors, current radiation levels, alarms, and controls for these monitors are provided on -these panels. For nonsafety-related monitors, communication interface is at the system CRT's in the main control room, technical support center, and
- emergency operations facility. All monitors can be communicated with at the local level by using a portable control unit.
i 11.5.2.1.1 DRMS Monitor. Descriptions Four basic types of_ monitoring or sampling systems _are provided as
'; indicated in Table 11.5-1 for the DRMS process and effluent monitoring systems; offline gas and particulate, offline gas, online steam, and l offline liquid. -Offline Gas and Particulate Monitor The typical offline gas and particulate monitor consists of an isokinetic sampling system, moving particulate filter with detector, iodine - filter cartridge, gas sample chamber with detector, and associated pump and valving'. Connections are available - for taking grab samples of the process stream, and taking tritium samples downstream of the filter units (effluentimonitors only). Check sources that are remotely operated are provided with each detector to check the function of each channel regularly. Remote purging capability is provided for the gas sample chamber.
Detectors are designed to obtain the sensitivities and ranges indicated in Table 11.5-1. w 11.5 . ,-
RBS FSAR The isokinetic sampling systems for these monitors are designed in accordance with ANSI N13.1-1969. Flow straighteners are provided in process streams that do not meet the minimum straight-run duct lengths specified by the standard. Sample lines from process streams in which plateout due to condensation could be a problem have been heat traced so that particulate sampling is representative of the process stream. Platcout is also minimized by using stainless steel for sample lines and for all surfaces of the sampler which are in contact with the sample stream. Offline Gas Monitor The typical offline gas monitor consists of an isokinetic sampling system, fixed particulate and charcoal filters, a gas sample chamber with detector and associated pump with valving. Connections are available for taking grab samples of the process strcams. All filters are removable for laboratory analysis. Check sources and purging capabilities are provided as described for the offline gas and particulate monitor. Detector type, ranges, and alarm set points are given in Table 11.5-1. Isokinetic sampling systems are designed as described for the offline gas and particulate monitor, with the exception of the main control room primary air intakes. For post-accident monitors, multiple detectors are provided with a minimum overlap of a decade in range to cover the extended ranges indicated on gaseous channels. Sampling and' collection capability only is provided to cover the extended particulate range to 100, uCi/cc. These monitors are also designed to perform their required function under the appropriate environmental conditions as defined in Section 3.11. Online Steam Monitor The online steam meritor consists of a detector shielding, and a-remotely operated acck source. The monitor is_ mounted to view a steam line and shielded to obtain the sensitivities-indicated in Table 11.5-1. Offline Liquid Monitor The typical offline liquid monitor consists of a sample chamber with detector and associated pump, piping, and-valving. 11.5-7.
RBS FSAR The detector is provided with a remotely operated check source and shielded to obtain the sensitivities indicated in Table 11.5-1. Connections for taking a grab sample from the process stream and purging the liquid sample chamber and sample tubing are provided. Heat exchangers are provided on sampling systems for which the process stream would cause detector failure. 11.5.2.1.2 DRMS Monitoring Systems Required for Safety 11.5.2.1.2.1 Fuel Building Ventilation Exhaust One offline gas and one offline gas and particulate monitor as described in Section 11.5.2.1.1 are provided for monitoring the fuel building ventilation exhaust before discharge to the environment. These monitors function to collect data for Regulatory Guide 1.21 report generation during normal operation, and indicate airborne levels of radiation in the fuel building (Section'12.3.4). The fuel building monitors are required for safety in the event that high airborne levels of radiation are present in the fuel building. They divert the ventilation exhaust through the fuel building ventilation system safety-related filter trains on a high alarm signal. The fuel building offline gas monitors have an extended range as indicated in Table 11.5-1 to cover releases throughout a design basis accident (DBA). These monitors are designed to perform their required function under all environmental conditions as defined in-Section 3.11. Reliable Class-1E safety-related 120-V ac electrical power is provided to these monitors as described in Section 8.3. 11.5.2.1.2.2 Main Plant Exhaust Duct Effluent from the main plant exhaust duct is monitored by an extended range offline gas monitor. The primary function of these monitors is to assure that technical specification limits for releases are not exceeded, to collect data for Regulatory Guide 1.21 report generation, l' and provide extended range post-accident monitoring. Major process streams exhausted through the main plant exhaust duct' include, reactor j building ventilation, auxiliary building ventilation, turbine building i ventilation,. piping tunnel ventilation, standby gas treatment system-
~
l exhaust and off gas building ventilation exhausta. This monitor is-designed'to perform its required function under all environmental conditions as defined in Section 3.11. Reliable safety-related Class IE 120-V ac electrical power is provided to-this monitor as described l in Section 8.3. i ( 11.5-8
l l l RBS FSAR 11.5.2.1.2.3 Containment and Drywell Atmosphere Offline gas and particulate monitors are provided to monitor the containment and drywell airborne levels of activity. The drywell monitor pull a sample from the drywell through the monitoring system located in the containment and returns the sample exhaust to the drywell. The containment monitor is located near the reactor building ventilation unit coolers at 162 ft 0 in of the reactor building. The unit coolers provide mixed air that is representative of the containment atmosphere. The containment and drywell atmosphere monitors are provided to aid in detecting reactor coolant pressure boundary (RCPB) leakage in accordance with Regulatory Guide 1.45. They are designed to remain functional during and after the seismic loading conditions as defined in Sectica 3.7. The containment atmosphere monitor also functions to indicate airborne radiation levels in containment (Section 12.3.4) for maintaining workers' exposure ALARA. Reliable safety-related Class 1E 120-V/480-V ac electrical power is provided to these monitors as described in Section 8.3. 11.5.2.1.2.4 Containment Purge Isolation Monitors Redundant area monitors are provided on the containment purge system. These monitors are intended to meet the requirements of NUREG-0737 Task II.E.4.2 (Containment Isolation Dependability). On receipt of a high radiation signal, the containment purge is isolated. Reliable, safety-related, Class 1E, 120-V ac electrical power is provided to these monitors as described in Section 8.3 11.5.2.1.2.5 Reactor Building Annulus Ventilation Redundant offline gas monitor are provided on the reactor building annulus ventilation exhaust. The annulus monitors function to indicate airborne levels of activity in the annulus area (Section 12.3-4). On a high radiation alarm signal the containment,. auxiliary, and annulus ventilation exhaust is diverted through the SGTS. These monitors are also designed to perform their required function under all environmental conditions as defined in Section 3.11. Reliable safety-related Class 1E 120-V ac electrical power is provided to these monitors as described in Section 8.3. i i i 11.5-9
RBS FSAR 11.5.2.1.2.6 Main Control Room Air Intakes Redundant offline gas monitors are provided at all main control room air intakes (local and remoto). The main control room ventilation local intako monitors divert the intake air through safety grado filter systems on a high radiation alarm. The main control room ventilation intake monitors enable the operator to chooso the least contaminated air intake throughout the course of an accident (Section 6.4) and provide an indication of airborno radiation levels present in the main control room (Section 12.3.4). These monitors are also designed to perform their required function under all environmental conditions as defined in Section 3.11. Reliable safety-related Class IE 120-V ac electrical power is provided to these monitors as described in Section 8.3. 11.5.2.1.2.7 RIIR llent Exchanger Service Water Ef fluent An offlino liquid monitor is provided to monitor the service water affluent on each of the two RilR heat exchanger trains. These monitors function to detect and alarm contamination of the service water of fluent due to leaks in the heat exchangers following a DBA or under normal operating conditions. These monitors are also designed to perform their required function under all environmental conditions as defined in Section 3.11. Reliable safety-related Class IE 120-V ac electrical power is provided to the monitors as described in Section 8.3. 11.5.2.1.3 DRMS Monitoring Systems Required for Plant Operations 11.5.2.1.3.1 Liquid Effluent Monitors Two monitors are provided to prohibit unidentified radioactive liquid releases from the plant:
- 1. Cooling tower blowdown line monitor
- 2. Liquid radwasto offluent monitor.
The cooling tower blowdown monitor detects and alarms high levels of radioactivity in the normal plant service water affluent. The liquid radwasto effluent monitor termintes a liquid radwaste system release if radiation levels exceed the technical specification limits. Nonsafety-related electrical power is provided to these monitors as described in Section 8.3. 11.5-10
RBS FFAR Gaseous Effluent Monitors 11.5.2.1.3.2 11.5.2.1.3.2.1 Main Plant Exhaust Duct One normal range offline gas and particulate monitor is provided to monitor the main plant ventilation exhaust. This monitor function primarily to assure that technical specification limits for releases are not exceeded and to collect data for Regulatory Guide l.21 report generation. Nonsafety related electrical power is provided to these monitors as described in Section 8.3. 11.5.2.1.3.2.2 Fuel Building Ventilation E::haust One normal range offline gas and particulate monitor is provided to monitor the fuel building exhaust. The monitor functions are described in Section 11.5.2.1.2.1. 11.5.2.1.3.3 Radwaste Building Ventilation Exhaust One offline gas monitor and one~offline gas and particulate monitor are provided to monitor the radwaste building ventilation exhaust. These monitors primarily function to assure that technical' specification limits for releases are not exceeded, monitor airborne levels of radiation in the:radwaste building (Section 12.3.4), and to collect data for Regulatory Guide 1.21 report generation. Gases from the radwaste tanks are filtered and discharged through the radwaste building ventilation exhaust duct. The radwaste building offline. gas monitor hasLan extended range to cover post-accident monitoring requirements for radwaste building effluents. Nonsafety-related electrical power is provided to these monitors as described in-Section- ! 8.3. i 11.5.2.1.3.3 Process' Ventilation Monitors ! Offline gas and particulate monitors are provided on the following- ! process ventilation streams:
- 1. Auxiliary building ventilation exhaust
- 2. Containment purge exhaust l
l 3. . Turbine building ventilation exhaust l l 4. Condensate demineralizer and off gas building ventilation l exhaust.
- 5. _ Standby gas treatment effluent' i
I Th'e function of the preceding-monitors-is to 1dentify sources of 1 radiation in main plant-exhaust' duct effluent in accor' dance with r 211.5-11'
,,- - + e - 4
RBS FSAR I Regulatory Guide 1.21 for monitoring separate streams into a common release point for better resolution. These monitors also function to indicate airborne levels of radiation in the corresponding plant buildings (Seetion.12,3.4). 1 The containment purge exhaust monitor isolates the normal containment { purge on a high radiation alarm. The standby gas treatment system effluent is monitored to ensure the adequate performance of the system and to alarm if release limits are exceeded. Nonsafety-related electrical power is provided to these monitors as described in Section 8.3. I l s
~ ^
11.5- 11a - LQY
RBS FSAR 11.5.2.1.3.4 Process Liquid Monitors The following process streams are monitored by offline liquid monitors for detection of radiation levels:
- 1. Fuel pool cooling pumps discharge (one monitor per discharge line)
- 2. Turbine plant component cooling water
- 3. Fuel pool cooling demineralizer outlet
- 4. Reactor plant component cooling water.
l l The fuel pool cooling pumps discharge monitors monitor cooling water for contamination from fuel failure on each recirculation loop. The fuel pool cooling demineralizer outlet monitor measures the performance of the spent fuel pool cleanup system. The turbine and reactor plant component cooling water monitors detect and alarm contamination of the circulating water in these systems. No1 safety-related electrical power is provided to these monitors as described in Section 8.3. 1 11.5.2.1.3.5 Process Gaseous Monitors { )l The following process gaseous streams are monitored for radiation level and alarm if abnormal levels are detected:
- 1. Mechanical vacuum pump exhaust
- 2. Radwaste reboiler clean steam outlet 1
- 3. Seal steam evaporator clean steam outlet i
- 4. Turbine gland seal discharge.
The mechanical vacuum pump exhaust is monitored to alarm if ef fluents from this system approach or exceed the limits determined by the technical specifications. The radwaste reboiler clean steam outlet and seal steam evaporator clean steam outlet are monitored to detect contamination of clean steam in the evaporator or reboiler. The turbine gland seal discharge is monitored to detect any degradation in the sealing system that would cause radioactive releases to the environment. Nonsafety-related electrical power is provided to these monitors as described in Section 8.3. 11.S-12 ;)
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