ML20246L424
| ML20246L424 | |
| 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-89629, NUDOCS 8909060325 | |
| Download: ML20246L424 (13) | |
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M"""" N Log # TXX-89629' 1
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C' 911.2.
1EIELECTRIC August 31, 1989 Wulissa J.Cahul,Jr..
Executive Vice Presiden U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
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SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR CHANGE SUBMITTAL-LIQUID RADWASTE EFFLUENT MONITOR Gentlemen:
The enclosure.to:this letter provides an advance submittal of FSAR changes -
related to the design and location of a liquid radweste effluent monitor that is utilized to automatically close the downstream stop valve.
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 cha:'ged 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 the related.SER/S*,ER sections.
4.
An index page containing the title of " bullets" which consolidate and categorize similar individual FSAR changes by subject and related SER section.
8909060325 890831 PDR ADOCK 05000445 A-PDC 08 400 North Olive Street LB 81 Dallas, Texas 75201
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- TXX-89629.
August 31,-'1989 Page.2 of 2 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).
The bold / overstrike version of the revised FSAR pages referenced l
by the description / justification for each item identified above.
The bold / overstrike version facilitates review 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.
TV Electric requests that the NRC perform'an expedited review.of this FSAR change package and inform us as to its acceptability.
Sincerely, T iYo Hif-r
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WilliamJ.Cahill,'Jr.
By:
- -i fo a
r Roger"'D. Walker Manager, Nuclear Licensing RLA/vid Enclosure c
Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
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~Encicsure.to TXX-89629 py * -
August-31,;1989:
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i Enclosure to TXX-89629 August 31. 1989 j
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Advance FSAR Change Related to a Liquid Radweste Effluent Monitor Subiect Eggg
- i Item 1 Draft revised FSAR pages 2
i Item 2 Descriptions / Justifications for all FSAR changes 4
Item 3 Related SER/SSER pages 5
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Item 4 Index Page for Bullets 9
l Item 5 Description / Justification for Bullets and 10 l
Associated Bold /0verstrike Pages I
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. Enclosure to TXX-89629 August 31, 1989
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CPSES/FSAR
.1 The normal path of floor drain waste is through the floor drain tank pump strainer, filter, and evaporator, and then to the waste monitor tank via the waste monitor tank desineralizer and filter.
The evaporator bottoms are disposed of as required. The 46 processed fluid in the waste monitor tank is then sampled and analyzed to determine if the fluid is acceptable as secondary system makeup. If the fluid is found to be acceptable, it is pumped by the waste monitor tank pump to the Condensato Storage Tank.
If the fluid is not found to be acceptable, it is.either discharged or reprocessed in Drain Channel 8.
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Any releases to the environment have radioactivity levels that DRAFT we ALARA (within the Itaits of Appendix ! of 10 CFR Part 50) and are administratively controlled by using a downstreen stop valve interlocked with a radiation monitor. This valve automatically closes if the waste activity reaches the senitse set point. The DRAFT scatter initiates automatic closure of the valve when the setpcint is exceeded. The radiation monitor setpoint is
'stablished at a value below the required limits to provide a margin of assurance that release limits will not be exceeded. A palisanent record of radioactive releases is provided by.an analysis of the known volumes of waste effluent released. The stop valve is also interlocked with the circulating water pump to block flow should sufficient dilution water not be available.
l Details of the Drain Channel 5 subsystes are shown on Figure 11.1-4.
4.
Drain Channel C Subsystem Drain Channel C is provided to collect and process waste effluents from the plant laundry, personnel decontamination showers and hand sinks, and surface decontamination. These liquids are collected in the laundry and het shower tank. Orain Channel C equipment includes a laundry and hot shower tank, strainer and filter, reverse ossosis system, two laundry holdup and monitor tanks, and a laundry water head tank.
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eaevvusu te oraamwusu August 31, 1989
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CPSES FSAR AMENDMENT' DETAILED DESCRIPTION Page 1 b
.FSAR Fage (as amended)
Stamt Descristing I
11.2-11 2
Modifies the text describing the means by which the waste effluent monitor assures that effluent release limits will not be exceeded.
Revision:
This change is made to reflect the as-built functional capability of this equipment.
(The change is consis-tent with the guidance provided in Section 8 of Ap-pendix A to Regulatory Guide 1.11. Rev.1.).
FSAR Change Request Number: 89-577.1 Related SER Section: 11.2.1 SER/SSER Impact: No 11.2-11 3
Modifies the text describing the radiation Monitor that is interlocked with the stop valve in the discharge line by indicating that it is no longer located in-line (i.e.. It now is located off-line).
Correction:
This change is made to reflect the current' design and layout of the Liquid Waste Processing System.
FSAR Change Request Number: 89-577.2 Related SER Section: 11.3 SER/SSER Impact: No Figure 11.2-5, sh 0 2
Deletes Note 6 as applicable to R:diation Monitor XRE-5253.
L Revision:
This change is made to reflect the current design and layout of the Liquid Waste Processing System.
FSAR Change Request Number: 89-577.3 Related SER Section: 11.2.1 SER/SSER Impact: No l
wj EnclosuretoTXX-8962d' August.31, 1989
.Pagh 5 of 11-of radioactive waste that will be shipped offsite to a licens In making these determinations, the staff considered waste flows levels, and equipment performance, consistent with expected norma operation including anticipated operational occurrences, for an assumed
- 30 years o,f normal plant operation.
were calculated using the PWR-GALE Code desc The principal parameters used in these calculati N liquid L
F and assumptions used by the staff are consisted with values giv accordance with the mathematical models a Guide 1.109 (Revision 1).
Meteorological factors in the dose calculations were determined usin The calculated indivl1 the guidance in Regulatory Guide 1.nl (Revision 1).
dual' dose,s are given in Table H.4.
Based on the evaluation below the staff has concluded that the liquid and gaseous radioactive weste proc,essing systems for Comanche Peak are capable of maintaining releases of radioactive materials in ifquid and gaseous effluents to ALARA levels in accordance with 10 CFR Part 50.34a with Sections II.A, II.8, II.C, and II.D of Appendix I to 10 CFR Part 50.
Based on the evaluation descriLed below the staff finds the' desig and gaseous radioactive waste systems an,d associated procetss a logical monitoring and sampling systems acceptable.
supplement to the SER, prior to the licensing of Unit 2 u.2 System Description and Evaluttion I
H.2.1 Liquid Waste Processing System i The ifquid weste processing system (LWS) for the Comenche Peak Sta Ishared between-Units 1 and 2 The system consists of the process equipment
'and instrumentation necessary.
dispose of radioactive liquid westas.to collect, process, monitor, and recycle or i their expected levels of radioactivity.to collect and pr
! batch beefs to permit optimum control of releases.All liquid westa is processed o Before processed liquid wastes are released amountsofradioactIvitypresent.they are sampled and analyzed to determine t the weste is either recycled for eventual reuse in the plant, retain further processing, or releaswd to the environment under controlled con A radiation monitor in the dia, charge line will automatically teminate the discharge of liquid wasto if radiation measurements exceed a predeterm level.
nor, tritiated waste subsystems and a laundry and s diagram of the liquid waste processing systas is ginn in Figure 11.1.
A schematic chemical and volume control system (CVCS) processes letdown fro The
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. Enclosure to TXX 89629 August 31. 1989
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Pag'e'6 of 11 The staff has evaluated the solid radwaste treatment for nonnal opera including anticipated operational occurrences.
The staff estimates that the volume and radioactivity level of solid waste shipped offsite will be ft8/yr/ reactor of solidified wet waste, containing 22 ft3/yr/ reactor of dry solid waste, containing no more,000 Cf. and 4100 than 5 Ci/ reactor.
11.2.3.1 Conformance With Federal Regulations and Branch Tec seet seismic Category I criteria, andThe solid radwaste syste therefore meets the guidance given in Regulatory Guide 1.143.
Storage facilities for s,olid waste include an area in the fuel building for approximately 35 50-fts containers and 50 55 gal drums.
Based on the staf" 3 estimate of the expected solid waste volumes a recommendation ie. SF.P 11.4 that at least 30 days' storage capacity b for packaged scly t edwaste from each unit, the staff f' nds that storage capacity adequatt k r meeting the demands of Comanche Peak Un normal operation.
In Amendment 22, the applicant committed to providing additional storage space prior to the licensing of Unit 2, its evaluation of the solid radweste system, tw staff concludes that th On the basis of I'
system design cannot accommodate the radwestes exsected durin including anticipated operational occurrences.
20 and 71 and 49 CFR Partsall wastes are in accordance with the 170-178.
From these findin the adequacy of the additional storage sthat the solid radwe the staff will review before the license for Unit 2 is issued. pace for meeting the station's demands reported on a supplement to this SER..
The results of t,4 review will be 11.3 Process and Effluent Radioloofcal Monitorina Systems The process and effluent radiological monitoring systems are design (1) provide information concerning radioactivity levels in systems the plant, (2) indicate radioactive leakage between systems plant discharges'to the environment.equipmentperformance,and (3) monitor Table 11.6 provides the proposed locations of continuous monitors.
on certain effluent release lines will automatically terminate discharges Monitors radiation levels exceed a predetermined value.
Systems which are not amenable to continuous monitoring, or for w isotopic analyses are required, are periodically sampled and analyz plant laboratory.
The staff has reviewed the locations and types of effluent and process monitoring provided.
and intermittent-sampling locationsBased on the plant design and on contin the staff has concluded that all normal and potential release pathways are m,onitored.
that the sampling and monitoring provisions are adeqate for detecti leakage of radioactive material to normally uncontaminated systems a monitoring plant processes which could affect radioactivity releases.
On this 11-16
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. Enclosure to TXX-89629
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August 31, 1989 Pape 7 of 11 Table 11.6 Process and effluent monitors
- l Stream Monitored Type Detector Number Monitor Sensitivity Liquids:
Component cooling water y Scintillation' 3/ reactor 1x10.s uct/cm8 (Co-60)
Service water effluent y Scintillation 2/ reactor 1x10.s uCf/cma Co-60) 3 ((Co-60)
Laundry and hot shower recycle y Scintillation 1 shared 1x10 8 uC1/cm i
Liquid waste effluent **
y Scintillation 1 shared 1x10 8 uC1/cm8 (Co-60)
Boron recovery system distillate y Scintillation 1 shared 1x10 8. uC1/cs8 (Co-60)
Letdown system 94 1/ reactor 1
uC1/as8 Co-60)
Condensate domineralizer input y Scintillation Vreactor 1x10.s uC1/cs8 Co-60 Condensate domineralizer output y Scintillation 1/ reactor 1x10.s uCf/cas Co-60 Auxiliary steam condensate y Scintillation 1 shared 1x10.s uC1/ css Co-60 3
Turbine b1dg drain input **
y Scintillation Vreactor 1x10.s uggfesa (Co-60)
Wasta monitor tank input recycle y Scintillation 1 shared 1x10.s uC1/cas (Co-60)
Gases:
Plant vent stack monitoring system - Auxiliary Building ***
Gas p Scintillation 1 shamd 1x10.s uC1/ca3 (Xe-133) s Particulate p Scintillation 1 shared 5x10 11 uC1/cm (Cs-137)
Iodine y Scintillation 1 shared 4x104 cps /uci (I-131)
Containment monitoring system - Safeguards Building **
~uC1/cm8(Xe-133)
Gas p Scintillation 1/ reactor 1x10.s Particulate p Scintillation Vreactor 5x10 11 uC1/cm3 (Cs-137)
Iodine y Scintillation Vreactor 4x104 cps /uct (I-131)
Plantventductmonitor(gas)***
p Scintillation 1 shared 1x10 4 uCf/cm3 (Xe-133)
Auxiliary b1dg ventilation duct (gas) p Scintillation 1 shared 1x10 ' uC1/cas (Xe-133)
Condenser vacuum pup vent (gas) p Scintillation 1/ reactor 1x10.s uCf/cm8 uCf/cm8 (Xe-133)
GWP5 monitor (gas) inlet p Scintillation 1 shared 1x10 1 s ((Xe-113)
HVAC room vent duct p Scintillation 1 shared 1x10 4 uCf/ca Fuel b1dg vent dust-
%b p Scintillation 1 shared 1x10 4 uct/cma (Xe-133)
Safeguards bids vest
.. Gas) p Scintillation 1/ reactor 1x10 4 uCi/cm3 (Xe-133)
"All 11gu18 aAE
.of71EBnt streams will De monitored in accordance with the guide-lines of Regula Guide L21.
- Teminates discharerty closing isolation valve when the radioactivity level exceeds a predetermined value.
- Terminates discharges from OfPS, control room ventilation exhaust, and containment purge ventilation when the radioactivity level exceeds a predetermined value.
11-17
.' Enclosure to TX'X-89629.
August 31,.1989 I
Pag'e'8 of 11 I
basis, the' staff considers that the monitoring and sampling p the requirements of GDC 60, 63, and 64 and the guidelines Guide 1.21.
11.4 Evaluation Findings In its evaluation, the staff calculated releases of radioactive ma liquid and gaseous efflu operational occurrences)ents for normal operation (including anticipated s in The staff determined that the applicant's prop the plant.
liquid and gaseous waste treatment systems satisfies the des Appendix I to 10 CFR Part 50.
gaseous radwaste treatment systems will reduce radioact as of offluents to ALARA levels in accordance with 10 CFR Part 50 fore, are acceptable.
i a 1% operating power fission product soutLe t under these conditions and gaseous effluents In unrestricted areas will be a limits specified in 10 CFR Part 20.
The staff has considered the capabilities of the redweste syst that the liquid and gaseous waste system cap ne are adequate to meet the anticipated needs of the plant.
es The staff has reviewed 'Ae applicant's qualit the seismic design applied to the gaseous waste processing system seismic classification apslied to the design of structures hou
, and the systems.
The design of tie radweste systems and structures housin systems meets the guidelines set forth in Regulatory Guide 1.143. g the The staff has reviewed the^ provisions incorporated in the to control the releases of radioactive materials in liquids as a result applicant are consistent with the acceptanc i
of Guide 1.143.
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The staff review of the radiological process and effluent mon included the provisions for sampling and monitoring all normal and 6
effluent discharge paths 1 conformance with GDC 64, for prov es potential termination of effluent releases and ensuring control of releases active mate 9fals in affluents in conformance with GDC 60 and a o-1.21, for stapling and monitoring plant waste process streams f control in conformance with GDC 63 monitoring process and effluent streams during s
, and for the liquid, gaseous, and solid raowaste system The the location of monitoring points relative to effluent release poi t or ems, and
- taff concluded that the applicant's radiological process and effluen n s.
The monitoring systems are acceptable.
11-18 l
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..' Enclosurd to TXX-89629 -
August'31, 1989 Page-9 of'11
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a SECTION 11 - RADI0 ACTIVE WASTE MANAGEMENT t
y; 11.2 System Description and Evaluation i
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11.2.1' Liqui,d Radwaste Processing System
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SPLB 17.- The FSAR has been revised to modify the automatic isolation of liquid effluents when the radiation signal setpoint is exceeded to assure that any discharge'is within acceptable limits.
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, Enclosure to TXX-89629
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- - ~ August 31. 1989 Page.10 of 11 SECTION 11 - RADI0 ACTIVE WASTE MANAGEMENT 11.2 System Description and Evaluation 11.2.1 Liquid Redweste Processing System SPLB
- 17. The FSAR has been revised to address the design and location of the liquid redweste effluent monitor that is utilized to automatically close the downstrees stop valve, 11.2-11 2
Modifies the text describing the means by which the waste effluent monitor assures that effluent release limits will not be exceeded.
Revision:
This change is sede to reflect the as-built functional capability of this equipment.
(The change is consis-tent with t,he guidance provided in Section B of Ap-pendix A to Regulatory Guide 1.11. Rev. 1.)
FSAR Change Request Number: 89-577.1 Related SER Section: 11.2.1 SER/55ER !apact No
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Figure 11.1-5. sh 0 2
Deletes Note 6 as applicable to Radiation Monitor XRE-5253.
Revision:
This champs is onde to reflect the current design and layout of the Liguid Weste processing System.
FSAR Change Roguest number: 89-577.3 i
Related SER Secties: 11.2.1 SER/SSER !apact: No
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.. Enclosure to TXX-89629 CPSES/FSAR
, August 31, 1989 Page.11 of 11 The normal path of floor drain waste is through the floor drain tank pump strainer, filter, and evaporator, and then to the waste monitor tank via the waste monitor tank desineralizer and filter.
46 The evaporator bottoms are disposed of as required. The processed fluid in the waste monitor tank is then sampled and analyzed to determine if the fluid is acceptable as secondary system makeup.
If the fluid is found to be acceptable, it is pumped by the waste monitor tank pump to the Condensate Storage Tank.
If the fluid is not found to be acceptable, it is either discharged or reprocessed in Drain Channel 8.
Any releases to the environment have radioactivity levels that are ALARA (within the limits of Appendix ! of 10 CFR Part 50) and are administrative 1y controlled by using a downstream stop valve interlocked with ad id/Jidd radiation monitor. This valve automatically closes if the waste activity reaches the monitor set point. The sentter initiates automatic closure of the valve.
when the setpoint is exceeded. The radiation monitor setpoint is established at a value below the required limits to provide a margin of assurance that release limits will not be exceeded. Tnd fddiffind diddddf if Idddfdd spiffddd df fMd distMd/dd idifdd it i dittidtd istfilidnt fd didtd (tidt td $ditidd t%d 11did indt diffidfdd fMd ddfdtidt stip didddll A permanent record of radioactive releases is provided by an analysis of the known volumes of waste effluent released. The stop valve is also interlocked with the circulating water pump to block flow should sufficient dilution water not be available.
Details of the Drain Channel 8 subsystem are shown on Figure 11.2-4.
4.
Drain Channel C Subsystem Drain Channel C is provided to collect and process waste effluents from the plant laundry, personnel deconte.mination showers and hand sinks, and surface decontamination. These liquids are collected in the laundry and hot shower tank. Drain Channel C equipment includes a laundry and hot shower tank, 11.2-11 Bold /0verstrike Version
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