TXX-8955, Forwards Advance Submittal of FSAR Changes Re Deletion & Relocation of Certain Process Radiation Monitors
| ML20246L871 | |
| 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-89559, NUDOCS 8909070054 | |
| Download: ML20246L871 (26) | |
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P M Log # TXX-89559 ll"."." File # 10110
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911.2 nlELECTRIC August 31, 1989 William J. Cahill, Jr.
Ltecutive nce President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
C0HANCHE PEAK STEAM ELECTRIC STATION (CPSES)-
DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR CHANGE SUBMITTAL-PROCESS RADIATION MONITORING SYSTEM INSTRUMENTATION Gentlemen:
The' attachment to this letter provides an advance submittal of FSAR changes related to the deletion and relocation of certain process radiation monitors.
In order to facilitate NRC staff review of this submittal, supporting information related to these FSAR changes is organized as follows:
- 1. Draft revised FSAR pages, with changed portions identified by a revisicn 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 the related SER/SSER sections.
- 4. An index page containing the title of " bullets" which consolidate and categorfzii similar individual FSAR changes by subject and related SER section.
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-TXX-89559J August 31~, 1989' Page 2?of.2.
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S '. 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 ftem.that impacts the existing SER/SSERs'..
(The discussion of these groupc'is.-contained in TU; Electric letter TXX-88467 dated June'1, 1988).
The bold / overstrike version of the revised FSAR pages referenced by the description / justification for'ench' item identified-above.
The bold / overstrike versiori facilitates-review of the revisions by highlighting each addition ofLnew text in'beld type. font and-overstriking with a slash (/)- the portion of the text. that is-deleted.
TU. Electric : requests that the NRC perform an expedited review of this FSAR -
change package and inform us as to its acceptability.
Sincerely. .
~
ryt h' )fr William J. Cahill, Jr.
By: M .
Roge M . Walker Manager, Nuclear Licensing I
RLA/vid
. Attachment c - Mr. R. D. Martin Region IV Resident Inspectors. CPSES (3)
V Attachment to TXX-89559 August 31, 1989 Advance FSAR Change Related to Process Radiaiton Monitoring System Instrumentation, Sub.iect Puce Item I' Draft revised FSAR pages 2 Item 2 Descriptions / Justifications for all FSAR changes 8.
Item 3 Related SER/SSER pages 10 Item 4 Index Page for Bullets 21 i
Item 5 Dorcription/ Justification for Bullets and 22 l Associated Bold /0verstrike Pages i
i
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . . _ . . __ _ ._ _ _ _ _. J
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'. Attach mnt'to'TXX-89559 Augost' 31. 1989 CPSES/FSAR
. Page 3 of.24. -
Safeguard Building vent duct monitors (1 per unit) 27
- h. Plant vent stack monitors (2/ stack. common)'
.. l 76
- 2. Process and Effluent Monitors l27
- c. Auxiliary steam condensate monitor. (1. common) 27-J- b. Boron ~ recycle monitor (1. common)- 27 -
- c. Component cooling water monitors (3 per unit) l27
- d. Service water monitors (2 per unit) 27
- e. Spent. fuel pool cooling water monitors (2. common) DRAFT
- f. Steam generator blowdown sample monitors (1 par unit) 27
- g. Steam generator blowdown monitors (1 per unit) 27
- h. Turbine Building drain effluent monitors (1 per unit) l27
- 1. Liquid waste effluent moniter (1. common) DRAFT l j. Waste gas monitor (1. common) 27
- k. Condenser off-gas monitors (1 per unit) 27 l" 1. Spent fuel pool demineralized monitor (2. common) DRAFT
- m. Failed-fuel monitors (1 per unit) 27
- n. Main Steam ifne monitors (4 per unit) 27 11.5-3 Draft Version i
_ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ . - - _- - _ - - - - - - -- ---- - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - -
. Attachneet t3 TXX-09559 August 31 1989 CPSES/FSAR 11.5.2.7.2 Steam Generator Slowdown Minitor 27
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This channel monitors blowdown which is exiting the Steam Generator 27 Blowdown Cleanup System. A shielded gamma-sensitive scintillation detector is' located in an off-line sampler assembly, downstream of the cleanup system's desineralizers. Automatic closure of both the blowdown isolation valves to the cleanup system and the blowdown j effluent control valve are initiated after a hith radiation level 1; detected. Alarm and indication are provided by the Control Room's RMS console and there is a ratemeter on the process cleanup system panel.
11.5.2.7.3 Liquid Weste Monitef l27 Discharges from the LWPS (see Section 11.2) are continuously monitored DRAFT by a shitilded gamma-sensitive (NaI) scintillation detector. A radiation monitor and a control valve discharges processed waste to the circulating water discharge tunnel. The discharge control valve is administratively centro 11ed; if activity concentrations exceed the discharge monitor high radiation alarm set point, automatic closure of the discharge control valve is initiated. Indication and annunciation are provided on the WPS control panel and in the Control Ream.
11.5.2.7.4 Auxiliary Steam Condensate Monitor 27 This channel continuously monitors auxiliary steam condensate from the outlet of a sample line header. Sample fluid is drawn from the WPS 3 waste evaporator, floor drain waste evaporators and the BRS recycle i
11.5-29 Draft Version
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s? ; . Attachment tc TXX-89559 'I
.Augdtt 31r 1989 ' .
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h .. S ' ' .. , CPSES FSAR' AMENDMENT 5' '
' DETAILED DESCRIPTION
" (Attachi:nt to TXX-895b9 Pag 2 1
- Aug0stJ31, 1989
.:Page 8 of 24-lFSAR Page m.myp_(gtu Stg.yg Dfscriotion Figure 11.2 4, sh 1 2 See Sheet No(s):F13.2-5(sh 0)
Deletes process radiation monitors XRE 5251 and XRE 5252 located on the. laundry holdup and monitor tank recycle line and on the return line to the condensate storage tank, respectively. Revision:
.This change reflects the current desigh of the Liquid l Waste Processing System.
[ FSAR Change Aequest Number: 89-506.4 . Related SEM Section: 11.3 SER/SSER Impact: Yes Table 11.6 in the SER should be revised to reflect the deletion of the process (radiation) monitors on the laundry and hot shower recycla streau end on the waste monitor tank input recycle stream.
- 11.5-5 2 Removes 2 of the 3 process monitors identified in item-
*1' of the subsection " Process and Effluent Monitors".
Revision: These monitors tre no longer requirta since the recycle capability for the two streams being konttored has been eliminated in the current Liq 91d Waste Processing .$ System design. f FSAR Change Request Number: 89-306.1 Related SER Section: 11.3 SER/SSER Impact: Yes Table 11.6 of the SER should be revised to re.flect the deletion of the process (radiation) monitcrs on the l 1kundry and hot shower. recycle stream and on the waste Arir.mmm,e e n monitor tank -input Pecycle stream. 11.5 - 29 2 See Page No(s):T11.5-1(sh 2), T11.5-2. T11.5-3(sh 2 Removes process radiation monitors XRE 5251 & XRE 5252 from service (XRE 5251 monitored processed liquid waste from the laundry holdup and monitoring tanks: XRE 5252 monitored processed tiquid waste from the waste monitoring tanks). Revision: This change reflects the current design of the Liquid Waste Processing System wherein processed liquid rad-waste will no longer be recycled to the condensate storage and laundry tanks, thus eliminating the need for these two process radiation monitors. FSAR Change Request Number: 89-506.2
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Related SER Section: 11.2.1.2 SER/SSER Impact: Yes Table 11.6 of the SER should be revised to reflect the deletion of the monitors on the laundry and hot shower recycle stream and on the waste monitor tank input recycle stream.
CPSES FSAR AMENDMENT
'.Atta$11m::nttoTXX-89559 DETAILED DESCRNTION' ~ Page 2
, .Aughst 31.-1989.-
, -. Page 9 of 24
'FSAR Pete (as amended). Group Description
-i
' Table 11.5-1, sh 2 3' See Sheet No(s):F11.2-5(sh 0)
C.hanges process radiation monitor XRE 5253, located on the' liquid waste discharge line, from in-line to off-- line service. Addition: Relocation of'this monitor reflects.-the current design of the Liquid Waste Processing System. FSAR Change Request Number: 89-5f10.3 Related SER Section: 11.3 SER/SSER Impact: No e
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. Attachment to TXX-89559 AugQst 31, 1989 '
. Page 10 of 24 i
6 11 RADI0 ACTIVE WASTE MANAGEMENT 0.. . 11.1 Summary Description f The radioactive waste management systems are designed to provide for cetro11ed handling and treatment of liquid, gaseous, and solid wastes. The liquid radioactive waste system processes wastes from equipment and floor drains, sample wastes, decontamination and laboratory wastes, and laundry and shower i wastes. ..
- The gaseous radioactive waste system provides holdup capacity to allow decay of short-lived noble gases stripped from the primary coolant and t
i treatment of ventilation exhausts throu0h high efficiency particulate air 1 i filtert, and charcoal adsorbers as necessary, to reduce releases of radioactive i materials to "as icw as is reas,onably achievable" (ALARA) levels in accordance with 10 CFR Part 20 and 10 CFR Part 50.34a. The solid radioactive waste i-system provides for solidifying, packaging, and storing radioactive. wastes generated during station operation before they are shipped offsite to a ifcensed facility for burial. i t In its evaluation of the liquid and gaseous radioactive waste systers, the staff has considered: (1) the capability of the systems for keeping the levels of radioactivity in effluents ALARA based upon expected radwaste inpets over the life of the plant; (2) the capability of the systens to maintain raleases below the limits of 10 CFR Part 20 during periods of fission product leakage from the fuel at design levels; (3) the cap bility of the systems to meet tie processing demands of the station during anticipated operational occurrences; (4) the quality groep and seismic design classification applieri to the systee; equipment and components and to the structures housing these systems; (5) the design features that will be incorporated to control the releases of radioactive materials in accordance with General Design Criterion 60; and (6) the potential for gaseous releases as a result of hydrogen explosions in the gaseous rzdwaste system. In its evaluation of the sulid radioactive waste treatment system, the staff has consid8r3d: (1) tystem design objectives in terms of expected types, volumes, and activities of waste processed for shipment offsite; (2) the applicant's process control program; (3) waste packaging and conformanca to app 1kable federal packzging regulations,'as well as provisions for controlling , potatial radioactive airborne dusts during bailing operation; and (4) provisions for onsite atorage of waste before shipment offsite. j In its evaluation of the process and effluent ' radiological monitoring and sampling system 4 l the staff has considered the system's capability: (1) to monitor all norm,al and potential pathways for release of radioactive materials I to the environment; (2) to control the releases of radioactive materials to the environment; and (3) to monitor performance of process equipment and tc detect radioactive materials leakage between systems. During its evaltation, the staff determined the quantities of radioactive materials that will be released in liquid and gaseous effluents and the amount 11-1
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' L Attachment to Td-89559 - l Aug0st 31, 1989
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. Page 11 4 of N radioactive waste that will be shipped offsite e to a licen{
In making these determinations, the staff considered waste flows uri levels, and equipment performance, Consistent, activny operation With RXpec including anticipated
- 30. years o,f nonaal plant operation. operational occurrences, for an assum; j
were calculated using the PWR-GALEThe . Code liquid ents de k i The principal parameters used in these calcul . and assumptions used by the staff cre consisted with valu ., I decordance with the mathematical models and Guide 1.109 (Revision 1). n were determined using the guidance in Regulatory G} The calculated individual doses are given in Table 11.4. . 1 Based on the evaluation below the staff has concluded that the liquid and gaseous radioactive waste proc,essing systems for Comanche Pea are capable of maintaining releases of radioactive materials in liquid Daseou:: with Sections effluents II. A, ILB,toII.C, ALARA levels and II.D in accordance of Appendix I to 10 CFR with Part1 Based on the evaluation described below the staff finds the designed liquid and logicalgaseous monitoringradioactive and samplingwaste systemssystems acceptable. an,d associated proces supplement to the SER prior to the licensing of Unit ) 11.2 _ System Description and Evaluation z 1 11.2.1 Liquid Waste Processing System shared between Units 1 and 2The liquid waste processing syste{ . and instrumentation necessary. The system consists of the process equipment i dispose o_f radioactive liquid wastes.to collect, process, ,aonitor, an:t recycle or their expected levels of radioactivity.to con ect and pro1 i batch basis to permit optimen control of releases.All liquid waste is processed on{ Before processed liquid wastes amounts of are released,present. radioactivity they are sampled and analyzed to determine theI i
, (
the waste is either recycled for p entual reuse in the plant, retain { j further praessie, or released to the environment under controlled A radiation dischar monitor in the discharge line will automatically terminate t . l 1evel. ge of liquid waste if radiation measurements exceed a predeter.nined ;
. The liquid radioactive waste processing system consists of the tritia r.ontritiated waste subsystems and a laundry and shower subsystem. f diagram of the liquid waste processing system is given Ainschematic Figure The 11 1 j chemical and volume control system (CVCS) processes letdownj 11-2
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.Attachzent to TXX-89559 L Augost-31, 1989 I
. Page 13 of 24 .
I- ' heat' exchangers, reduced in pressure, filtered and processed through one of' two mixed-bed demineralizers in the Li3B03 form. For cation control, a :r.ica , L i bed time.demineralized is valved into the process stream a) proximately 10% of the l - l , The. processed letdown stream is collected in tie volume control tank and reused-4n-the-primary coolant system, . The CVCS is used to control the - l' 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 be approximately 1870 gpd/ reactor. staff estimated the boron recycle s j' Primary coolant grade water from equipment drains, from equipment leakage,_
' from and relief valves equipment inside containment is collected in the reactor drain tank. drain The staff estimated the boron recycle system input 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 gal holdup tanks. The shim bleed feed is processed through one of two boron recycle system mixed-bed demineralizers before it enters the holdup tanks. Liquid collected in the holdup tank is processed in batches through a 15 gpm boron recycle system evaporator, a
.I condenser,- and a boron recycle system evaporator condensate demineralized. A I
The processed liquid is either returned to the primary co in a h,oldup discharge tank, or released to the Squaw Creek Reservoir through the LWPS header. of the treated process stream from the boron recycle system is Squaw Creek Reservoir through the LWPS discharge header. 11.2.1.2 Liquid Waste Processing Subsystems The LWPS consists of three subsystems: the tritiated waste suuystem, the nontritiated waste subsystem, and the laundry and hot shower drain subsystem. Each reactor cleanup system. unit also has a steam generator blowdown' system and a condensate Tritiated Waste Subsystem Tritiated wastes are processed through the tritiated waste subsystem and recy to the CVCS monitor) tank. for reuse through a 5000 gal waste evaporator condensate (recycle The tritiated waste subsystem consists of a 10 000 gal waste holdup tank, a 15 gpm waste evaporator, and a mixed-bed polishing demineralized. Tritiated wastes from valve and pump leakoffs, equipment drains, and plant samples mately 300aregpd collected in the waste holdup tank at an input flow rate of approxi-per reactor. and a polishing demineralizerThis waste is processed through an evaporator and after sampling and analysis, the liquid collected in the waste evapora, the primary coolant system for reuse. tor condensate tank will normally be recycled to 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 Rerervoir through the LWPS discharge heeder. 11-8 L__--_----
.AttachbenttoTXX-89559 August 31, 1989
. PagHoWTtined Waste Subsystem Aerated wastes and nontritiated wastes are processed through the nontritiatea
~
waste s'ubsystem for discharge to the environment. Nontritiated wastes consisting of floor drains, nontritiated equipment drains, and other waste sources containing less than 10% of the tritium concentration in the reactor's coolant will be collected in one of two 10,000 gal floor drain tanks (Nos. I or II) or a 30,000 900 gpd/gal floor drain tank (No. III) at an input flow rate of approximately reactor. This waste will be processed through a 15 gpm floor drain evaporator, and the distillate will be collected in one of two 5,000 gal waste monitor tanks where samples will be taken and analyzed to determine if the processed waste is suitable for release to the environment. Laundry, Hot Shower, Lgboratory, and Decontamination Drains laundry and hot shower drains are collected in a 10,000 gal tank and processed in batches, through a 10 gpm reverse osmosis unit. Treated liquid may be reused or collected in one of two 5,000 gal laundry holdup and monitor tanks for sampling and analysis before it is released to the environment. Decontamina- 4 tion liquid wastes and laboratory chemical liquid wastes norrnally will drain
; to a 600 gal chemical drain tank.
These wastes and the concentr'ates from the
'i reverse osmosis unit are then transferred to the solid radwaste system for solidification. Other laboratory wastes are transferred to a floor drain tank for processing through the nontritiated *.aste subsystem. 1 Steam Genarater Clowdcwn Svstem A steak generator blowdown system (SGBS) is provided for each reactor unit. I l
The SGBS consists of a heat exchanger, filters, two 640 gpm cation demineralizers, and two 640 gpm mixed-bed demineralizers. all or some of the components are placed in service.Dep iding Spent on from resin the mode the of operation, SGBS is transferred to a 3740 gal SGBS spent resin storage tank (shared by Units 1 and 2) to be processed by the solid waste system. There are no liquid effluent releases from the SGBS. Condensate Cleanuo System Each reactor unit has a system of five condensate filter /demineralizers for cleanup of turbine condensate. In the full flow polishing mode, each system has a maximum capacity of 21,000 gpm. In its evaluation, the staff assumed that 70% of the condensate is processed by the filter /demineralizers. Spent > powdered resins are flushed to a phase separator where the backwash and flush water the solidis decanted for reuse and the resins are drained for batch treatment by waste system. i Because the filter /demineralizers are automatically backwashed, the Technical Specifications will require resin sampling and analysis for radioactivity. There are no liquid effluent releases from the i condensate cleanup system. 11.2.1.3 Conformance With Federal Regulations and Branch Technical Positions The liquid waste processing system is located in the auxiliary building, which j is designed to meet seismic Category I criteria. The proposed seismic design 11-9
- ---- - - \
.AttacMent to TXX-89559 Augtsst 31. 1989
.. Page 15 f and'Ne qua'lity-group classification and capacities of prin that the staff considered in evaluating the 1.WPS are listed in Table 11
-The staff finos the appifcant's proposed liquid radioactive waste treatm ..
system design to be acceptable in accordance with Regulatory1.143. Guir' active storage tanks.materials as a result of potential overflows fr , room, and high level alarms are activated if preset levels Overflow provisions such as sumps, drains, and overflow lines permit the collection and subsequent processing of tank overflow. The staff believes materials to the environment.that these provisions are capable of con operational occurrences, the liquid radioactive wa capable to of reducing approximately the release 0.16 Ci/yr/ reactor of radioactive materials in liquid effluents excluding tritium and dissolved gases, and 340 Ci/yr/ reactor for tritium. ,The calculated annual releases of radio-nuclides in liquid effluents from each unit are given in Table 11.1. dose to any individual in an unrestricted area to b the combined liquid effluents from Units 1 and 2. processing system for Comanche Peak Steam Ele capable of maintaining releases of radioactive materials in liquid eff during normal operation (including anticipated operational occurrences)luen so that the calculated doses are less than the numerical design objectives Section II. A of Appendix I to 10 CFR Part 50. of The staff evaluation also shows and 2 satisfies the design objectives set forth in RM the of 10option CFR Partprovided
- 50. by the Commission's September 4, 1975 amendmen of Appendix I of 10 CFR Part 50.Therefore, the design meets the requirements of The staff concludes that the liquid waste processing system is capable of reducing the releases of radioactive materials in effluents to ALARA levels in accordance with 10 CFR Part 50.34a and Appendix I to 10 CFR Part 50.
the staff has determined that the liquid waste processing system is capable o reducing the release of radioactive materials in liquid effluents to concentra-tions below the limits specified in 10 CFR Part 20, during periods of fission product leakage from the fuel at design levels. 11.2.2 Gaseous Waste Processing System : are designed to collect, storeThe gaseous radioactive waste processing potentially operation radioactive of the plant. gaseous, wastes which are generated during nor The systems consist of equipment and instrumentation necessary to reduce releases of radioactive gases and particulate to the environment. The principal sources of caseous waste are the effluents from the gaseous waste processing system, concenser vacuum pumps, and ventilation exhausts from the auxiliary building, reactor containment, and turbine buildin , l { 11-10 I
> ~
,Attadhnnt to TXX-89559 Augtsst 31, 1989
;. Page 16 of 24 l.
}; Table.11.5 Design parameters of principal components considered in the evaluat
,[. -systems {onofliquidandgaseousradioactivewastetreatment i
i Component Number Capacity, each
, Liquid Systems:
n Chemical and volume control system
' Volume control tank e Mixed bed demineralizers 1/ reactor 400 fta Cation demineralized 2/ reactor 120 gpm Thermal regeneration demineralized 1/ reactor 120 gpm 5/ reactor 250 gpm Boron recycle system (BRS)
BRS feed demineralizers 2 shared BRS holdup tanks 120 gpm 2 shared 56,000 gal Reactor coolant drain tank 1/ reactor BRS evaporator package 350 gal BRS evaporator condensate demineralized 1 shared 15 gpm 1 shared 120 gpm
. Liquid waste processing system (LWPS)
LWPS vaste holdup tank LWPS waste evaporator condensate tank 1 shared 10,000 gal-1 shared 5,000 gal LWPS floor drain tanks (I or II) 2 shared 10,000 gal LWPS floor drain tank (III) 1 shared 30,000 gal LWPS monitor tanks Chemical drain tank 2 shared 5,000 gal Laundry and hot shower drain tank 1 shared 600 gal 1 shared 10,000 gal LWPS evaporator packages (floor drain & waste) 2 shared LWPS demineralizers 15 gpm Laundry reverse osmosis unit 2 shared 35 gpm I shared 10 gpm Gaseous Systems: Gaseous waste processing system (G4PS) GWPS compressors (design pressure 150 psig) 2 shared GWPS recombiners (design pressure, 150 psig) 40 scfm ! 2 shared 50 scfm GWPS decay tanks (design pressure,, 150 psig) 10 shared 600 ft3 a Design Classification and Seismic Design Criteria per Regulatory Guide 1.143. l l 11-11 e OdeM
[ ,-
.Attachmnt to TXX-89559 August 31. 1989
..(Page17o[h[4 5taff'has evaluated the solid radwaste tre including anticipated operational occurrences.atment for normal operation, volume-and radioactivity level of solid waste shipped offsite will b ft3/yr/
3 reactor of solidified wet waste, containing 22 000 Ci and 4100 , ft /yr/ reactor of dry solid waste, containing no more,than 5,Ci/ reactor 11.2.3.1 Conformance With Federal Regulations and_ Branch Technica i meet Regulatory seismic Guide 1.143. Category I criteria, and, therefore the fuel building for approximately-35 50-ftStorage facilities for solid waste 3 containers and 50 55 gal drums. Based on the staff's estimate of the expected solid waste volumes an recommendation in SRP 11.4 that at least 30 days' storage capacity be for packaged solid radwaste from each unit, the staff finds that st capacity normal adequate for meeting the demands of Comanche Peak Uni operation. additional storage In Amendment space 22,licensing prior to the the~ applicant committed to providing of Unit 2. its evaluation of the solid radwaste system, the staff On the basis of that th concludes system design cannot including anticipated accommodate operational occurrences. the radwastes expected during n ,. 20 and 71 and 49 CFR Partsall wastes are in accordance with the ap 170-178. that the solid radwaste system is acceptableFrom these findings the staff concludes however, the staff.will review before the license for Unit 2 is issued.the adequacy of the add reported on a supplement to this SER. The results of the review will be 11.3 Process and Effluent Radiological Monitorino Systems (1) provide information concerning radioactivity levels i equipment performance, andthe plant, (2) indicate(3) radioactive monitor leakage plant discharges to the env(ironment.4) monitor and control radioactivity levels in Table 11.6 provides the proposed locations of continuous monitors. Monitors on certain radiation effluent levels exceed release lines will a predetermined automatically terminate value. discharges-Systems which are not amenable to continuous monitoring, or for wh isotopic plant analyses laboratory. are required, are periodically sampled and analyze The staffprovided. monitoring has reviewed the locations and types of effluent and process and intermittent-sampling locationsBased on the plant design and on continu the staff has concluded that all normal and potential release pathways are m,onitored. The staff has also determined i that the sampling and monitoring provisions are ad ' monitoring plant processes which could affect radioactivity releases. On tnis 11-16 l
'L; AttachmGnt. to TXX-89559 August 31, 1989 j.'Page18of24 ,
l Table 11.6 Process and effluent monitors
- l Stream Monitored Type Detector Number Monitor Sensitivity {
f Liouids: i Component cooling water y Scintillation' 3/ reactor 1x10.s uCf/cd (Co-60)
! Service water effluent y Scintillation 2/ reactor Laundry and hot shower recycle y Scintillation 1x10 5 uCi/cd (Co-60)
! 1 shared 1x10 5 uti/cd (Co-60)
Liquid waste effluent ** y Scintillation 1 shared Boron recovery system distillate 1x10.s uCi/cd (Co-60) y Scintillation 1 shared 1x10 5 uti/cd (Co-60) Letdown system GM 1/ reactor Condensate demineralized input 1 uCi/cv (Co-60) y Scintillation 1/ reactor 1x10.s uCi/cd (Co-60) Condensate demineralized output y Scintillation 1/ reactor 1x10 5 uCi/cd (Co-60)
, Auxiliary steam condensate y Scintillation I shared 1x10 5 uCi/cd Co-60)
Turbine b1dg drain input ** Waste monitor tank input recycle y Scintillation 1/ reactor 1x10 5 uCi/cd ((Co-60) y Scintillation 1 shared 1x10 5 uCf/cd (Co-60) Gases: Plant vent stack monitoring system - Auxiliary Building *** Gas s Scintillation 1 shared 1x10 8 uCi/cd (Xe-133) Particulate E Scintillation 1 shared 5x10 11 uCi/cd (Cs-137) Iodine y Scintillation 1 shared 4x104 cpm /uci (I-131) Containment monitoring system - Safeguards Building ** Gas Particulate s Scintillation 1/ reactor 1x10 6 uCi/cd (Xe-133) p Scintillation 1/ reactor 5x10 12 uCi/cd (Cs-137) Iodine y Scintillation 1/ reactor 4x104 cpm /uci (I-131) Plant vent duct monitor (gas)*** E Scintillation 1 shared 1x10 4 uCi/cd (Xe-133) Auxiliary b1dg ventilation duct (gas) S Scintillation I shared 1x10 4 uCi/c ,a (Xe-133) Condenser vacuum pump vent (gas) p Scintillation 1/ reactor 1x10 5 GWPS monitor (gas) inlet uCi/cd Xe-133) E Scintillation 1 shared 1x10 1 uCi/c9 ((Xe-133) HVAC toom vent duct (gas) S Scintillation 1 shared Fuel b1dg vent duct (gas) 1x10 4 uCi/cd (Xe-133) s Scintillation I shared 1x10 4 uCi/cm3 Safeguards b1dg vent duct (gas) p Scintillation 1/ reactor 1x10 4 uCi/cP(Xe-133) (Xe-133)
^All liquio anc gaseous effluent streams will be monitoreo in accorcance with the guice-lines of Regulatory Guide 1.21.
** Terminates discharge by closing isolation valve when the radioactivity level exceeds a predetermined value.
*** Terminates discharges from GWPS, control room ventilation exhaust, and containment purge 1 ventilation when the radioactivity level exceeds a predetermined value.
11-17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - _ _ _ _ _ _ __ l
r Attachment to TXX-89559 August 31, 1989 ( k
, Pa9eGuide 191.21.Bis $$., the staff considers that the monitoring a the requirements of GDC 60, 63, and 64 andu the a oryguidelines i 11.4 Evaluation Findings In itsand liquid evaluation, gaseous effl the staff calculated releases of radioactive m erialc in operational the plant. occurrences)uents for normal operation -(including anticipated Thestaffdeterminedthattheapplicant'spropose Appendix I to 10 CFR Part 50. liquid and gaseous waste e trea i
gaseous radwaste treatment systems will reduce radioac ! effluents to ALARA 1crels in accordance, with fore, are acceptable. there- 10 CF The staff has considered the potential consequences of react a 1% operating power fission product source term eration andwith has de under these conditions, the concentrations of radioactive , quid mate and gaseous effluents limits specified in 10 CFR Part 20. in unrestricted areas will be a small e frac demands that result from anticipatedconcluded operation meet that the liquid and gastous waste system capacities and design fl are adequate to meet the anticipated needs of the plant. exibilities The staff has reviewed the applicant's quality assurance r the provisi radwaste systems, the quality group classifications used the seismic design applied to the gaseous waste processing for s s, system
, and the seismic classification applied to the design of structures systems. housi The design of the radwaste systems and structures housing t waste systems meets the guidelines set forth in Regulatory Guide 1143 The staff has reviewed the' provisions incorporatedesign in the applic to control the releases of radioactive materials in liquids as a inadvertent tank overflows and has concluded that resultthe of measures oposed by the applicant Guide 1.143. are consistent with the acceptance criteria set forth i ry The staff review of the radiological process and effluent monitorin included the provisions for sampling and monitoring g all normal system n potential ad effluent discharge paths in conformance with GDC a64, termination of effluent releases and ensuring control of release ic for provi s of radio-1.21, for sampling and monitoring plant control in conformance with GDC 63 rocess ue waste pk -
monitoring process and effluent streams during p .
, and for review included piping and instrument diagrams and process w diagrams The for flo the liqcid, gaseous, ana solid raowaste systems and nrelea ventilatio systems, and the location of monitoring points relative to effluent se points.
- taff conciuoed monitoring systems arethat the applicant's acceptable, radiological process Tne and effluen i
11-18 l l 1
.Attachr:nt'to TXX-89559
,' August 31. 19891 l
, Page Ihn (he" basis of the evaluations discussed above, the staff concludes that the .
design-liquid and gaseous radwaste processing systems and monitoring systems are acceptable. The basis for acceptance has been ennformance of the applicant's designs, design criteria, and design bases for these systems to the applicable regulations and guides referenced above, as well as to staff technical positions
.and industry standards.
- Moreover, based on its~ evaluation of the solid radwaste processing system, the
. staff concludes that the designed system for " dry" waste is acceptable. For Unit 1 only, the storage capacity for packaged waste is adequate to meet the recommendation. for an area to acccamodate at least 30 days. of storage. .In addition, the staff finds that the applicant has.not completed his process control program for solidification. Therefore, the staff will complete its evaluation for increased storage capacity of the solid waste processing system
, in a supplament to this SER prior to the licensing of Unit 2.
i 0 11-19
. . _ _ _ _ - ~ _ _ - - - - -
FAugutt; 31,t1989?
,. Pg.:l1 ofc24 -
y;y , .. r,
.y r11 2.1 ' 'Liouid' Waste Processino System v
SPLB. 15. The'FSAR has'been revised to. indicate that' process- -(77)-
-radweste will'not be returned to the consensate-storage.and laundry tanks., therefore .'ar '.oring.+
configuration has been modified. s I (
' Attachte::t to TXX-89559 August 31, 1989 Page 22 of 24 11.2.1 Liouid Waste Processino System
! SPLB- 15. The FSAR has been revised to indicate that process radwaste will not be returned to the consensate storage and laundry tanks. therefore, monitoring configuration has been modified. Figure 11.2r4. sh.1 2 See Sheet No(s):F11.2-5(sh 0) Deletes process radiation monitors XRE 5251 and XRE 5252 located on the laundry holdup and monitor tank recycle line and on the return line to the condensate storage tank, respectively. Revision:
- This change reflects the current design of the Liquid Waste Processing System.
, FSAR Change Request Number: 89-506.4 Related SER Section: 11.3 SER/SSER Impact: Yes Table 11.6 in the SER should be revised to reflect the deletion of the process (radiation) monitors on the laundry and hot shower recycle stream and on the waste monitor tank input recycle stream.
11.5-3 2 I Removes 2 of the 3 process monitors identified in item
*1*
of the subsection " Process and Effluent Monitors". Revision: These monitors are no longer required since the recycle capability for the two streams being monitored has been eliminated in the current Liquid Waste Processing System design. 1 FSAR Change Request Number: 89-506.1 Related SER Section: 11.3 SER/SSER Impact: Yes Table 11.6 of the SER should be revised to reflect the deletion of the process (radiation) monitors on the 1aundry and hot shower recycle stream and on the waste monitor tank inpu.t recycle stream, l 2 11.5 - 29 See Page No(s):T11.5-1(sh 2). T11.5-7.. T11.5-3(sh 2 l Removes process radiation monitors XRE 52511 XRE S252 from service (XRE 5251 monitored processed liquid waste from the laundry holdup and monitoring tanks XRE 5252 monitored processed liquid waste from the waste monitoring tanks). Revistun: This change reflects the current design of the Liquid Waste Processing System wherein processed liquid rac-waste will no longer be recycled to the condensate storage and laundry tanks. thus eliminating the need for these two process radiation monitors. FSAR Change Request Number: 89-506.2 Related SER Section: 11.2.1.2 SER/SSER Impact: Yes Table 11.6 of the SEP. should be revised to reflect the deletion of the monitors on the laundry and hot shower recycle stream and on the waste monitor tank input recycle stream. s O
.. Attach::nt.to TXX-89559
, August. 31,,1989 CPSES/FSAR Page 23 of 24 g.- Safeguard Building vent duct monitors (1 per unit) 27
- h. Plant vent stack munitors (2/rtack, common) 76
- 2. Process and Effluent Monitors 27.
- a. Auxiliary steam condensate monitor (1, common) 27
- b. Boron recycle monitor (1. common) 27
- c. Component cooling water monitors (3 per unit) 27
- d. Service water monitors (2 per unit) l27
- e. Spent fuel pool cooling water monitors (2, common) l27
- f. Steam generator blowdown sample monitors (1 per unit) 27 9 Steam generator blowdown monitors (1 per unit) l27
- h. Turbine Bu'1 ding drain effluent monitors (1 per unit) 27
- 1. Liquid waste If(did effluent Add p/dddds monitori (1 3, 27 common)
- j. Waste gas monitor (1, common) 27
- k. Condenser off-gas monitors (1 per unit) l27
- 1. Spent fuel pool domineralizer tddlidd difd/ dddpfd monitor 46 (2, common) l
- m. Failed-fuel monitors (1 per unit) l27 l
- n. Main Steam line monitars (4 per unit) l27 i l I i 11.5-3
- _- a
Attachment to TXX-89559
*'N' August 31, 1989 CPSES/FSAR
>Pige 24 of 24
'27 11.5.2.7.2 Steam Generator 81owdown Monitor 27 This channel monitors blowdown which is exiting the Steam Generator Blowdown Cleanup System. A shielded gamma-sensitive scintillation ,
detector is ibcated in an off-line sampler assembly, downstream of the cleanup system's demineralizers. Automatic closure of both the blowdown isolation valves to the cleanup system and the blowdown effluent control valve are initiated after a high radiation level is detected. Alarm and indication are provided by the Control Room's RMS console and there is a ratemeter on the process cleanup system panel. 27 11.5.2.7.7 Liquid Waste Monitor Discharges from TNtdd cNinndit Gf the LWPS (see Section 11.2) are continuously monitored by a shielded gamma-sensitive (NaI) scintillation detector.ilidd ddnitdti fd/ (diftidd it/didi ind did fd/ in tN4 dittnitti ittd66 16 tnd fi/it tNinndil $/didiidd ditidi if tNd tid dittd ddnitdtind id6Ki itd $dd$dd fd i iddddn Ndidd/ fNit fi ditddlif fddtdd tN/dddN 6 tidfitidn idiftdt ind ddit/dl idlfd td Et , ditMit di tNd tid tddddititd itdtd64 TinKil if tNd ittiitti l idntinttitidd di tK6 $/didtidi iditit it66 tNii (Ninndi ditidd tNd l ddnitdt MitN tidtitidn 616td idt idinti tNd ddntidt inittitit distite l di tNd dddnitid6d idditd1 tilidt tidildt tNd $/didiidd dittd td fidd J tN/dddN i (ddflld lidd Idtitdd d$df,tddd f/dd tNd ddnfidf/ In tNd istddd tNinndil $tdidiidd 46didi in tNd 16dnd/f Ndidd$ ind dinitdting tinti itd $dd$dd td i Ndidd/ WNitM ndtdillf ditdtit fidd fNtdddN i tidfitidn ddnftdt ind idnt/dl idlid td (Nd 16didtf ditdt Mdid finKl 52 l 11 ittiitti iddidnttiti6dt df tNii tNinndi idttit$diding td tNd NigK Y , 414td idt$ditt i/d diididddl tNd idnitif inittitdi tidtifd di tNd
, d6dnittiiG dditid1 tilidt tidiing tNd li$did ditidi td fidd tNfdd4N i (dt/ tid ifnd d$dt/ddd f/dd tNd dinitdt! WNdn (Nd finitd1 tiliti df tNd /dtfild ind $tdtdit initi lindi iti tididdl idtidlif Editdd/tliidd idntid1 Wilidt tin vi d$didd difdtting fldt tKtintN i tnt /d lNinndt tdntiining A radiation monitor and a control valve dNitM discharges processed waste to the circulating water discharge tunnel. The Witdilif EddKdd/tididd discharge control valved itd is administrative 1y controlled; if activity concentrations exceed the Bold /0verstrike 11.5-30 Version}}