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Docket File 50-400 i-Docket File 50-401 (w/o, enc 1)
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I:ETB Reading File.
Oce'< c t "n t. 50 t 0''/.* 01 dAMd 6' $3 ADRP Reading File IIETB Docket File C V..*C # FOR:
Thonas ". !'ovah, /.ssistant Director for Licensing, DL FPH:
_R.1.'cync !!ouston,' A:sista.t Dire: tor for P.cdiation Protection, DSI S'JCJt0T:
!!ETB It' L'T FO?. 02/FT S.*.:. ETY E*'AL'JATICt! F.EDO~ti FOP. S!! EAT.0"
!!A?.P.IS, Ut!IT l'OS.1 W.'D 2 Enclosed for ycur n:e is the I;cteorol:7y and Effluent Trettaent tiranch (!'.ETB),
Effluent Trect-.ent Systens Section (ETSS) input to the draft Safety Ev 1uation Rct rt (SER) for'the Shecron !!arris I.iuclear Pcuer Plant (Sit!PP).
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Ti 1 r inout-is;c revised version of the draft v.hich we r.revided June 25, 1902.
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Thc nu-!r;r of onen itens ero too nicerous to detail in this nmorandtn.
It sbruld to noted that !'c draft has asstmed that t'10 plant ' sets the detien cNc:tivas of f.ppandix I to 10 CFR Part 50. This esstnption will be vorified once Cerolina Pouer and Light Connany orovides the additiomi infor.tation to allo: 'EE to calculcto the effluente resulting fre. or.: ration of t"e fluidi:c bc:.'r; or.
Car input to iter. III.D.1.1 of EUREG-0737 is not included. The applicant i
re:ent1.v prcvider' this infornation in k1s'enent 3 to the FSAP..
I:ET?'s revist is not ccepleted. The results of this review &,ill be fonverded to you upon ccrpl etion.
If there are questions concerning the ETSS revieu, ple se contabt J. Hc.yes r
(x27~n9) Wo is the reviwer for SI'."PP.
The "Warolory Section inout to the drrf t SEP. ucs tran'itti6 to DL en 10/27/2?.
I ann c'!9rle: ented on 10/2f./'.2. Tuo cPon isse2: rc : in in this area.
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.-.=..c cn D..TalMC~~iBDit:en, Assistant Dirc:ter fer Eadie.tien Pratsetion g
gg Divi Sion of S,este~.s Intecration U
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_6. 5.,1 Eligineered Safety Feature (ESF) Atmospheric Cleanup System 6.5.1.1 Summary Description The engineered safety feature (ESF) atmospheric cleanup systems at the Shearon Harris Muclear Power Plant (SHHPP) consist of process equipment and instrumentation necessary to control the release of radioactive iodine and particulate material following a design basis accident (DBA). At the SHNPP, there are three filtration systems designed for this purpose. These systems are:
(1)
Reactor Auxiliary Building (RAB) Emergency Exhaust System; s
12R' Fu'el Handling Building (FHB) Emergency Exhaust System; and (3) control Roon Energency Filtration ' System.
The RAB energency air exhaust systtm consists of, in order, a demister, electrical heating coil, pre-filter, HEPA filter, charcoal adsorber, I
liEPA filter, and decay heat cooling air connection. The purpose of this system is to limit the potential for post-accident radio-logical releases to contaminated portions of the RAB. Those areas which are filtered include the rooms containing the charging pump, the RHR heat exchanger, containment spray and RHR pumps, and the mechanical, electrical and heating and ventilation penetration areas and rooms.. Upon receipt of a Safety Injection Actuation Signal (SIAS)., air operated valves on the nomal ventilation penetration into areas containing equipment essential for safe shutdown close and both RAD emergency exhausts are automatically energized. Either filter unit may then be manually de-energized from'the control room and placed en standby.
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6.5.1.1 By continually exhausting air a negative pressure of 1/8 inth water gauge (ifGlis established. Pressure is then controlled by the airflow control system which' adjusts the variable inlet vanes of the exhaust fans.
The'FHB emergency air exhaust system consists of components which are identical to the RAB emergency exhaust with the exception that j
the charcoal adsorber section is two inches deep whila that of the RAB system is 4 inches deep. The purpose of the FHB system is to Saintain the fuel
* storage building at a negative pressure so that
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any radioactive iodine or particulates released to the building will be contained within the building and then filtered prior to release.
The actuation of the FHB system is from a signal initiated'by one l
of the four radiation monitors located around the walls of each of the fuel pools. Both trains will be actu'ated initially.
Either train may be manually de-energized frota the Control Room and placed on standby'. Pressure in the FHB is maintained at 1/8 inch ilG and controlled by the a,irflow control system.
The control room emergency filtration system consists or two-100%
capacity filtration systems. Each filtration system inc1'ud,es, in order, a demister, t:0 electric heating coils arranged in series.
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(one operating and one on standby), a HEPA filter, a charcoal adsorber,'
and another HEPA filter. The purpose of the co,ntrol room emergency filtration systen is to limit the amount of radioactivity introduced into the control room following an accident and filter radioactivity
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3-3 6.5.1.1 already in the cbntrol rocr. such that doses to control roca operators will be within the design criterion of GDC 19 of 10 CFR Part 50, Appendix A.
Upon receipt of a Safety Injection signal (SIS) or a high chlorine concentration signal at the outside air intakes, the outside intake isolation valves will be closed, the control room purge system isolation valves will be closed, one fan'in each emergency filtration train will start and the respective fan valve 2 i
opened. ' All isolation valves in the normal exhaust system will close and the exhaust fans de-energized.
All of these actions will occur automatically. Upon receipt of a high radiation signal from the radiation monitor located within each air intake, the air intake l
on the affected side of the control building will automatically isolate and the emergency filtration system will start. Upon com-pletion of the above automatic functions, the operator will place one _of the emergency filtration trains on standby, select and open one_ emergency outside air intake based upon radiation and chlorine readings, and open exhaust bypass dampers for laboratory and kitchen bypass exhaust.
The control room emergency filtration system will process a mixture of control room. air and a small cuantity of outside air through HEPA filters and charcoal adsorbers and maintain the :ontrol envelope e
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.<.;a 6.5.1.1 under a positive pressure of -rl/8 i :h water gauge. Air is con-tinuously drawn for the supply air ubsys. tem, blended with outside air, precessed through the filtrati n system and supplied to the control room.
Sections 6.5.1 and 9.4.1 of the Har is FSAR contain a detailed description the ESF filtratio,n syst as.
. 3. 5.1.2.
Eval.uation and Findings The staff's review included the cap bility of ESF filter systens to operate after a design basis acc dent; an evaluation of the systems design, design criteria, de ign objectives, components design and qualification testing; and desi n provisions incorporated to.
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facilitate operation and maintenanc and testing of components to ensure continued acceptable perfour :nce. The staff's review was based upon the relevant requirement ; of (1) GDC 19 of of, Appendix A to 10 CFR Part 50 for systems desit ied for the habitability of the control room under accident condit: ms; (2) GDC 61 for the design of systems for radioactivity contrt under postulated accident con-
,ditions;.and (3) GDC 64 for the moi :toring of radioactive releases under postulated accident conditici 2.
l The ESF filter systems were not re' iewed according to SRP 6.5.1 of NUREG-0800 because the acceptants criteria of this document calls.. for the design, testing, and :onstruction of components of
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5.5.1.2 the ESF filter system to AflSI N509-1980. These standards were not in existence at the time the SHNPP ESF filter systems were designed
. nor when the equipment was purchased. Therefore, the review of the ESF filter systems was conducted utilizing SRP 6.5.1, Rev.1, of
!!UREG-75/087, which more adequately reflects the criteria which were in effect at the time the SHNPP ESF filter system was designed.
. ln those. instances where the equipment was purchased prior to Rev.1, conformance with prior document cri,teria, whether Regulatory Guide 1.52, Rev.1, or SRP_6.5.1, Rev. O, was considered acceptable.
As a result of this review, the following evaluations and 51 ridings have been made.
1 The applicant has provided a comparison of the design of the SHNPP ESF filter systems with the regulatory positions of Regulatory Guide 1.52, Rev. 2 March 1978 in a Table of the FSAR. The staff has de-termined that the applicant has proposed few exceptions to Regulatory Guide 1.52 and that these exceptions are trivial in nature and judged to.be acceptabla.
The staff credited the applicant with 95% removal efficiency for' methyl radiciodine for the FHB emergency exhaust system and 99% for methyl radiciodine for all other ESF filter systems".
As a result of the staff's rev.iew of the applicant's designs, design criteria, and design bases for-ESF atmospheric ' cleanup systeas and
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the systems' confomance to applicable regulatio ts', guides and industry 6.5.1.2 standards, the staff has concluded that the ESF atmospheric cleanup systems include the equ'ipment and instrumentation to control the release of radioactive materials in airborne effluents following a design basis accident.
The staff finds the proposed ESF atmosphere cleanup systems acceptable and the filter efficiencies given in Table 2 of Regulatory Guide 1.52 appropriate for use in the l
' accident analyses.
L 10.4.2 Main Condenser Evacuation System l
10.4.2.1 Summary Description The main condenser evacuation system (MCES) of each unit cons'. ts of two 100% capacity mechanical vacuum pumps.which serve the main At startup, one or both pumps may be operated.to evacuate condenser.
the condenser. Once operating pressure is obtained, one pump is placed on standby. On startup, and prior to turbine operation, the p
non-condensible gases will be discharged dir,ectly to the atmosphere r.
P in the turbine building at without filtration. With turbine operation the discharge from the mechanical vacuum pumps is directed L'
to the turbine building vent stack without filtration.
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The.non-condensible gases flow to a moisture separator tjhere most
. of the water vapor is condensed. The condensed water' drains to the i
industrial waste sumps. However,'the discharge from these sumps t,t.
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- will be directed to the secondary waste system for treatment on de-tection of radioactivity by m6nitor REM-3528. The airborne disc.harge from the mechanical vacuum pumps is monitored for radioactivity. Any radioactivity exceeding the monitor set point will initiate an alarm by the radiation monitors. The applicant has indicated that there is no potentially explosive gas mixture present in the MCES during normal operation, or duri6g shutdown or startup conditions. A more detatied discussion of the MCES is presented in Section 10.4.2 of the FSAR.
l-10.4.2.2 Evaluation Findin5s I
. The staff's review included the system's capability to process Fi I
radioactive gases and the design provisions incorporated to monitor and control releases of radioactive materials in gaseous effluents in accordance with GDC 60 and 64 of Appendix A to 10 CFR Part 50.
The quality group classification of equipment and components used to collect gaseous radioactive effluents was reviewed relative to the guidelines of Regulatory Guide 1.26. The staff reviewed the applicant's system descriptions, piping and instrumentation diagrami, and design criteria for components of the MCES with respect to the Acceptance Criteria of SRP 10.4.2 of flVREG-0800.
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10.4.2.2 The staff, in a question to the applicant, stated that the 14CES contains no provisions for sampling and monitoring discharges frca the turbine building vent during startup operations as specified in Table 1 of SRP 11.5.
The applicant, in response to this question, stated that the discharge would be monitored by noble gas monitor RB4-3534 because valve 7AE-B3-1 is ' nomally open butterfly valve which would be open during hogging a
[perations, thus resulting in a dual exhaust during these operations.
The flow passing by monitor RBi-3534 would allow action to be taken to close valves 7AE-33-1 and 7AE-B9-1 on a high radiation signal and the rerouting of the off-gas through the condenser vacuum penp effluent treatment system (CVFi M. The CYPETS consists.of a demister, an electrical heating er HEPA filter, a 4-inch chercoal adsorber, t
another HEPA filter, and two-100% capacity fans in parallel.
It is the staff's position that the release of the off gas during hogging operations must be monitored as noted in Table 1 of SRP 11.5.
As long as flow is maintained through valves 7AE-B3-1 ak 7AE-B9-1
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no additional monitor is required. However, the staff believes that since the purpose of the hogging operation is to establish a vacuum in.the condenser as soon as possible, there will be occasions where the plant staff will desire to discharge the off gas only to the turbine building atmosphere. 'Therefore, the staff will cake it
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10.4.2.2 a enliition of the license that no discharges may occur form the nachanical vacuum pumps without the effluent being nonitored. The NRC staff would allow isuch a release only.if there were a conitor on the exhaust to the turbine building, y
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The applicant has indicated that the main condenser is constructed to the Heat Exchanger Institute's " Standards for Steam Surface Condensers"(pL.n.x } u ik -.,,.
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.p sistent with the guidelines given by the above industrial standard py
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as required by the Acceptance Criteria of SRP 10.4.2.
The oaff requests at the ap icant.provi.b g justificati why. e capacity of t MCES is r o consistent th the guide 'nes o'f the " Standards f
Steam S face Condense k
The applicant has indicated that the quality group classification pFj (IM to which the liCES is designed is non-nuclear safety, Category 1
,,,,g f for the condensate vacuum pump effluent treatment syst:n ud non-nuclear safety, Category 2 for the mechanical vacuum pumps. Mc :n'r, he applicant has not indicated, in Secton 3.2 of the FSAR, W these quality group classifications coerelate with Quality Group D of R'egu' tory Guide 1.26. Sch ; c;.. a dv..
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g of the above items the staf f'will be able to judge the MCES's conformw.e with the acceptance criteria of SRP 10.4.2 t*
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x 10.4.2.2 and whether the liCES has met the requirements of GD; 69 and 64 with respect to the control and monitoring of releases of radica:tive materials to the envirbnment and whether the MCES has met the re-quirements of the industrial standard " Standards for Steam Surface Condensers".
10.4.3 Turbine Gland Sealing System 10.4.3.1 Summary Description The turbine gland sealing system provides sealing steam to the main turbine generator shaft to prevent the leakage of air into the turbine casings and the potentini escape of radioactive steam into the turbine building. A portion of the main steam supply.is passed c.
through' the t.urbine gfand seals and condensed in.the gland steam condenser. The condensate is returned to the main condenser hot tell
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while non-condensible gares are discharged by two 1007, capacity blowers to the environment. A core detailed discussion of the turbine gland sealing systen is presented in Section 10.4.3 of the FSAR.
10.4.3.2 E' valuation and Findings m
The 'staf f has reviewed the turbine gland sealing system with respect to the Acceptance Criteria of.SRP 10.4.3 of flVREG-0800. The scope of this review included the source of sealing steam'and the provisions incorporated to monitor and control releases of gaseous radioactive effluents in accordance with GD0 60 and 6'4 of Appendix A to 10 CFR 7
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10.4.3.2 Part 50. The staff has reviewed the applicant's system description and design criteria for the components of the turbine gland sealing systen.
QN The applicant has indicated that the quality group classification
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to which the turbine gland sealing system has been designed is ncn-g v h nn.
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nuclear safety, Category ?.
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Th; i :igr :h=1 d conforA to the Acceptance Criteria of SRP 10.4.3.
t' The venting of the turbine gland seal condenser's noncondensable gases is not monitored as req'uired by Table 1 of SRP 11.5. The applicant stated in response to a staff qu,th(tions, that they do not consider the turbine gland seal condenser a principal source of radionuclide release and therefore it does not require non'aring because the expected activity is far below guideline values.
1:hile the turbine gland seal condenser is not a principal source, it is, nevertheless, a source and a source which, accorcing to GDC 64 of Appendix A to 10 CFR Part 50, requires monitoring and which as noted e
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1 10.4.3.2 in Table 1 of SRP 11.5 also requires sampling. Therefore, it is the staff's position that monitoring of the turbine gland seal condenser occur and that the associated sampling also occur.
The co initment by the applicant to meet the Acceptance Criteria of
. the above SRP will allow the staff to conclude that the turbine gland sealing system meets the requirements of GDC 60'and 64 with respect to the control and monitoring of releases of radioactive
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11.0 Radioactive Waste Management 11.1 Source Terms l L 11.1.1 Summary Des ~cription The applicant calculated the liquid and gaseous effluents from the Shearon Harris Nuclear Power Plant (SHUPP) utilizing the PWR GALE computer progran. The applicant utilized the source assumptions of
-Regdlatory Guide 1.112. " Calculation of Releases of Radioactive
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Materials in Gaseous and Liquid Efflu*ents from Light-Mater-Cooled Power Reactors", and HUREG-0017, " Calculation of Releases of Radio-active Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs)". Gaseous effluents were calculated from such sources as offgases from the main condenser evacuation' system; leak-
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age _ to containment, the reactor. aux'iliary building, and the turbine building; noble gases stripped fr'om the primary coolant during normal i
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. operation and at shutdown; and cover and vent gases frca tanks and i
equipment containing radioactive material. Liquid effluents were calculated from such sour'ces as shim bleed, leakage collected in 4
equipment and floor drains such as found in as the reactor auxiliary building, fuel handling, waste processing, and turbine buildings, contaminat'ed liquids from anticipated plant operat'fons such as resin sluices, filter backwash, decontamination solutions, sample station drains, and detergent wastes.
The staff has perfomed an independent calculation cf the primary l
and secondary coolant concentrations and of the release rates'of radioactive materials using the information supplied in the appli-(
cant's FSAR, the GALE computer program, and the methodology presented s,
Table 11.1-1 presents the principal parameters which in HUREG-0017.
were used in this independent calculation of the source tems. These source terms were utilized in Sections 11.2 and 11.3 to calculat,e individual doses in accordance with the mathematical models and guidance contained in Regulatory Guide 1.109, " Calculation of Annual.
' Average Doses to Man From Routine Releases of Reactor Effluents for the Pur. pose of Evaluating Compliance with 10 CFR Part 50, Appendix I."
Liquid effiuents occur from the waste monitoring tanks, the treated laundry and the hot shower storage tanks and the secondary waste sample tanks. The sources of wastes to these tanks are discussed in a
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11.1 Section 11.2 of this SER. One source of waste to the waste monitor tanks which is not discussed in Section 11.2 is that originating from the baron recycle system (BRS). Distillate from the BRS evaporators can be pumped to the waste monitor tank for discharge offsite.
The staff's estimate of the liquid effluents was based upon the information presented in Tables 11.1-1 and 11.1-2.
The applicant as'sumid that floor drain wastes would be treated by the reverse
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esmosis (RO) unit of the floor drain treatment subsystem. The stcff calculated liquid effluents assuming that the floor drains would be treated by the RO unit. However, the results indicated that over t.
5 curies per year per unit would be reicased based upon t'.m 7taff I
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projected inputs to the floor drain treatment subsystem.
this would not comply with one of the requirements of the Annex to Appendix I of 10 CFR Part 50 which the applicant chose to use to show compliance with Section II.D of Appendix I, the staff assumed that wastes collected by the floor drain tanks would be treated by the waste evaporator in the equipment drain treatment subsystem. The applicant had indicated in the FSAR that these evaporators would be available to treat the floor drain wastes when they contained high activity. The staff then calculated the effluents from floor drains based upon the the use of this evaporator. With it's use the effluents frcm the SHNPP could satisfy the criterion of Secti,on A.2 of the Annex to Appendix 1.
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11.1 In its evaluation, the staff determined that adequate holdup and processing time were available for the treatment of the floor drain wastes and the equipment d' rain wastes.
The applicant assumed in his analysis that the wastes collected by the secondary waste low conductivity holding tank would be processed by an evaporator in addition to a inixed bed decineralizer. The staff's review of the applicant's description of this system in-dicat'ed that these wastes would usually be treated only by a de-mineralizer. Therefore, in their analysis, the staff assumed the latter made of treatment.
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The holdup time calculated by the staff for the treatment of the i
regenerative solutions from the condensate polishing system (input s
to secondary waste high conductivity holding tank) was calculated to be.less than 2' days. Since the secondary waste evaporator, which was intended for Units 3 and 4, is available for processing the contents of the high conductivity holding tank'if the evaporator for Units 1 and 2 becomes inoperable; no alternative treatment scheme hao to be considered in lieu of the evaporator even though less than 2' days holdup was avt.ilable for treatment of the regenerants.
The staff assumed that chemical drain wastes from the chenical drain tank of Units 1 and 2 and the concentr. ate from the laundry and hot e,
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shower RO unit would be sent to the R0 concentratts tank a 11.1 The applicant by the R0 concentrates evaporator' prior to discharge.
did not include this source in their evaluation of effluent release All detergents wastes were considered by the staff to be collected and treated by the laundry and hot shower RO unit and then disc'harged.
Airborne effluents occur from the building ventilation systems, frol
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; the. continuous and pre-entry containment purges, from the gaseou waste processing system (GUPS), the main condenser evacuation system, All airborne effluents except and the turbine gland steam condenser.
those released from the turbine gland steam condenser, the main con-
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denser mechanical vacuum pump, and the G'JPS are passed through a H The continuous con-filter and charcoal adsorber prior to discharge.
tainment purge is filtered by a HEPA filter and charcoal adscrber in the airborne radioactivity renoval system ( ARRS) inside the containment.
Additional infomation utilized by the staff in its estimate of air-Addi tional borne releases is provided in Tables 11.1-1 and 11.1-2.
details on the liquid and gaseous radwaste syste.ns are contained in Sections 11.2 and 11.3 of this SER.
e to process evap-The applicant is installing a fluidized bed drye
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x 11.1 of reducing the volume of solid radwaste shipped offsite. The opera-tion of this volume reduction (VR) equipment will result in additional liquid and airborne effluants. Airborne effluents will result from
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the VR system's offgas and will be discharged on a continuous basis while the system is operating. There are no ifquid effluents which will be discharged directly off-site from the VR equipment operation.
However, based upon FSAR Figure 11.4.2-2, decantabination solutions,
; condensate from the scrubbers and leakage from pumps, pipes, etc.
will result in additional quantities of wastes being treated by the floor drain treatment system. Ultimately, some of these wastes will be discharged offsite from the waste monitor tanks and scoe will again be treated in the VR system.
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11.1.2 Evaluation and Findings The applicant has'~notliFesented any detail on the VR system.
In particular, the applicant has not addressed (1) the volume of waste to be handled by the VR system; (2) the quantity of aircorne radio-active effluents released from the VR system; (3) the additional voluae of wastes to be treated by the liquid waste processing system as a result of operation of the VR system; and (t.) thi additional radioactive liquid effluents resulking from operation of the VR 7
system.
The staff has estimated the qtiantity of wastes to be treated by the VR system and the radioactivity associated with these wastas. The
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11.1.2 staff has estimated the additional amount of radiaoctivity released as airborne effluents from the VR system and as liquid effluents from the liquid radviaste system. These releases were included with the releases 15 calculated using flVREG-0017 and the total quantity of effluents was W
FCS presented in Section 5 of the SHNPP Environmental Statement (ttt).
Tables 11.1-1 ar.d 11.1.2 of this SER present assumptions.which were,,
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utilized in the calculation of effluents esulting frem YR w.gac.t.
g The ap'pli antias not filed with the Co'm issiot detafis on the VR
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n its interface wi various pla t systems such as prpcess and efflue t montoring, uch infomation w 11 be required i
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Table 11.1-1 Principal parameters and conditions used in releases of radioactive material in liouid and gaseous effluents from Shearon Harris !!uclear Power Plant Reactor power level (MWt) 2900 Plant capacity factor 0.80,
Failed fuel 0.12%
Prinary systen 5
Itass of coolant (1b) 3.42 x 10 Letdown, rate ! gal / min) 60 3
Shim bleed rate (gal / day) 1.44 x 10 Leakage to secondary system (ib/ day) 100 U Leakage to containment building (ib/ day) b Leakage to auxiliary building (1b/ day) 160 Frequency of degassing for cold shutdowns (times /yr) 2 c
Letdown cation demineralizer flow (gal / min) 6.0 Secondary system 7
Steam flow rate (1b/hr) 1.2 x 10 5
liass of liouid/ steam generator (ib) 1.01 x 103 liass of ster.n/ steam generator (ib),
9.00 x 1
/
Secondary coolant mass (1b) 1.53 x 1 Rate of steam leakage to turbige area (1b/hr) 1.7 x 10 6
2.3 x 10 Containnent building volume (f t )
Trecuency of containment purges (times /yr) 4 i
Containment 1cw volume purge rate (ft"/ein) 17g0 Containment atmosphere cleanup rate (ft<nin) 10 Pre-purge claanup time duration thr) 16 locine partition factors (gas /licuid)
Leakage to auxiliary builcing 0.0075 Leakage to turbine area 1.0 liain condenser / air ejector (volatile species) 0.15 Liould radwaste system decontamination factors
-i.2 q
Boron Recycle Equipment Drain Secondary taste System Treatment High Conductivity
,.i Material System Sub-tvstem 10f 10l 6
Iodine 10 3
;i
: Cesina, 2x10 10 10 Rubidium 4
4 5
Other 10 10 10
*This value is constant and corresponds to 0.12% of the operating power product source term a's given in 14UREG-00i7 ( April 1976).
b N)
%/ day of the primary coolant noble gas inventory and 0.001%/ day of the primary coolant iodine inventory.
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Table 11.1-1 (continued)
Secondary Waste Low Laundry and Hot Shower Conductivi ty R.O. Concentrate Subsystem Subsystem Material 10f 2
Iodine 10 Cesium,. rubidium 2
10 2
4 Other 10 10 Liouid Maste Inouts Process Flow Rate Fraction Fraction Collection Time Stream (gal / day) of PCA Discharged time (days) (days)
Shimaleea Rate (5RS) 1440 1.0 0.1 23.3 3.11
, Equipment Drains (EDTS) 250 1.0 0.1 24.4 0.46 R.O. Concentrates Wastes 838 0.002 1.0 2.23 0.17 Bl owdown 119000 0.0 0
0 Floor Drains (FDTS) 935 0.11 1.0 21.4 0.46 Regenerant Solution (SWTS) 6000 1.0 0.50 0.21-Detergent Wastes 450 1.0 6
1 Low Conductivity Holding Tank 19000 8.7x10 1.0 0.47 0.13 Source of Volume Reduction System Wastes Volume / Year / Unit 1.
Evaporator Botton.s.
3 (a) Recycle Evaporator 1,025 ft3 (b) Waste Evt;;rator 960 ft 3 (c)
Secondary Waste Evaporator 4,675 ft3 (d)
RC Concencrate 876 ft 2.
Filter Sludge ft Gaseous Maste Inputs There is continuous low volume purge of volume control tank Holdup. time for xenon (days) 70 Holdup time for Krypton (days) 70 Fill time of decay tanks (days) 35 9
t 1
em fM' t
4
 
, _f--
Table 11.1-2 Individuci Ecuipment Decontamination Factors All nuclides except iodine Iodine 1.
Evaporators 10f Secondary Waste and Waste 103 Recycle 10 10
~
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U
: Cesium, Other Anions Rubidium
?!uclides 2.
03 min N.11zers Secondary Maste, tiixed Bed 10 2
i 10 CYCS Laundry Reverse Osmosis 1
10 10 Package and L'aste lionitor Tank,
/
Catior Bed i
Recycit. Evaporator Feed, tiixed Bed 10 2
10 '
2 Recycle Evapora*ar Condensate, 10 1
1 Anion Bed Decontacination Factors Iodine Others 3.
Volune Reduction Eo,uipment Fluidized Bed Dryer and Gas / Solids 2
100 Separator Scrubber /Preconcentrator 3
100 HEPA Filter 1
100 Charccal Adsorber 100 1
y/.4 Tr uss,m BJidev$ F. \\ 4'<
p.
leo M *dt+ 4 ''
All IJuclides 4.
Reverse Osmosis Units Laundry and Hot Shower 30
/
 
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22 -
11.2 Liquid Radwaste System 11.2.1 Summary Decription The liquid waste processing system (LWPSI at the SH!:PP consists of process equipment and instrumentation necessary to collect, process, monitor, and recycle and/or discharge radioactive liquid wastes.
The LWPS is designed to collect and process wastes based on the origin of the waste in the plant and the expected levels of radioactivity.
- All'1fquid waste is processed on a batch basis to permit optimum f
control of releases. Before liquid waste is released, sanples are analyzed to determine the types and amounts of radioactivity present.
e Based on the results of the analysis and the waste treatment system
(
utilized, the waste may be recycled for eventual reuse in the pla~nt, retained for further processing, or released to the environment under con ' rolled conditions.
A radiation monitor in the discharge line from the various discharge tanks will automatically terminate liquid waste discharges if radiation measurements exceed a predetermined level. An alarm will bc simultaneously actuated in Units 1 and 2's control room, in the WPB control room and the Health Physics control room.
The LMPS at the SHUPP is comprsed of the following subsystems:
(1) the equipment drain trestment; (2) the floor drain treatment; (3) the laundry and het shower treatment; and
(,,
(4) the secondary wasta treatment.
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..I 11.2.1 The SHl:PP's has been designed so that liquid wastes from the reactor coolant and its associated subsystems are separated into three main streams - recyclable reactor grade, nonrecyclable, and secondary waste. The recyclable reactor grade stream consists of tritiated wastes collected in the equipment drains. This strean is treated by the equipment drain treatment subsystem. The nonrecyclable equipment stream consists of nonreactor grade water sources and is collected and pr.ocessed through either the floor drain treatment subsystem or the laundry and hot shower treatment subsystem. The secondary waste l
l stream con,ists of regenerant solutions from ~the condensate polishing I
l system and backflush from the electrcmagnetic filters of the steam
(.-
generator blowdown system and is collected and processed in the secondary waste treatment subsystem.
~
The above systems are shared vwincan as t.n u...it; at the SHl:PP.
There are two floor drain treatment subsystems and two secondary waste treatment subsystens shared between the t<to units. All other shared systens are single subsystems.
All releases are monitored before discharge to the cooling tower blowdown. The discharge valve is interlocked with a process r'adiation monitor and will close automatically if the radioactivity in the liquid should exceed a predetermined limit or if the ' dilution flow afforded by the cooling tower blowdown falls below a preset value.
Additichal details on the liquid radwaste treatment system follow.
)
9 4
 
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. L.
n 11.2.1 The equipment drain treatnent subsystem collects reactor grade water fron eouipment leaks and drains, valve leakoffs, pump seal leakoffs, tritiated water sources and tank overflows. These wastes are collected in the waste holdup tank and then processed via filtratio,n
- and evaporation. After processing, these wastes are either sent to the reactor makeup water storage ttnks or to the waste monitor tank for discharge or to the waste holdup tank for additional treatment.
1
- The floor drain treatment subsystem collects and processes water frcm the floor drains of the reactor auxiliary building (RAB), fuel handling.
building (FHB), waste processing building (WPB), tank areas (reactor makeup, water storage and condensate storage tanks) and portions of
-[
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~
the hot shop. - The waste is collected in the floor drain tank and n~.
p processed by filtration and treatment in the floor drain treatment subsystem reverse osmosis (RO) unit and then collected n the waste monitor tanks. From the waste monitor tanks, the wastes may be dis-charged to the cooling tower blowdown line, pumped to the condensate storage tank, recycled to the waste holdup tank for treatment in the c
equipment drain treatment subsystem, or pumped directly to the waste
' processing system (WPS) waste evaporator for treatment. The latter route will be utilized when radioactivity levels are such that filtration and reverse osmosis are insufficient to reduce the radioactivity to acceptable levels.
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The laundry and hot shower treatment subsystem collects, in the laundry 11.2.1 hot shower tank, detergent waste from the k'PB, the FHB and the hot shop.
The applicant expects this waste to be of a quality such that treatment
: However, for removal of radioactivity will not noma'ily be required.
if analysis indicates that treatment is required it will be routed to the laundry and hot shower RO unit. The permeate from the RO unit will and then routed to the treated laundry be passed through a demineralizer The contents of this tank can be recycled for
-and hot shower tank.
~~
~
~
f urther treatment or discharged via cooling to'wer blowdown or pumped to the condensate storage tank.
The secondary waste treatment subsystem is designed to treat wastes This water will contain radio-(
generated from secondary systems.
activity only if primary to secondary leakage occurs in,the steam The secondary waste treatment subsystem consists of one generators.
subsystem to treat high conductivity wastes and one to treat low conductivity wastes.
Low conductivity wastes such as the backflush from the' electromagnet'c filters of the steam generator blowdown system and the low conductivity wastes from the condensate polishing system are collected in the low conductivity holding tanks. These wastes are filtered and passed through a demineralizer and then collected in the secondary waste From the secondary waste sample tanks the water is sample tanks.
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11 2.1 either recycled to the condensate storaje tank, discharged to the cooling tower blowdown or to the neutralization basin or recycled back to the low conductivity holding tanks.
The main source of high conductivity wastes is the regenerant solutions from the condensate polishing system. This waste is collected in the high conductivity holding tank, processed by an evaporator and the evap' orator distillate discharged to the low
^
~
~ clo'nductivity system upstream of the demineralizer. From the demineralizer, treatment is the same as for the low conductivity subsystem.
Turbine building equipment drains and curbed area oil equ'ipment and
{
floor drains below the operating ceck are collected in the industrial waste sumps of the turbine building. Drains below ground elevation are collected in a condensate pump area sump. This sump and the in-dustrial waste sumps discharge through a radiation monitor. The contents of these sumps will normally go to a yard oil separator and then to the cooling tower blowdown.
If the monitor detects high radiation in the discharge from one of these pumps, the discharge will be directed to the low conductivity holding tank for treatment.
The secondary waste subsystem also collects 1) 'the waster from the chemical drain tank which are not sent to the solid waste processing system for solidification, and 2) the concentrated wastes from the i
s.
 
(
i,
_ 27 waste evaporator, the reversa osmosis units, and the seconcary waste 11.2.1 These wastes are collected in the R0 concentrate tank ard evaporator.
The distillate from are processed in the RO concentrate evaporator.
this evaporator goes to the treated laundry and hot shower storage tank for discharge. The evaporator concentrate goes to the waste evaporatdr concentmte tank for solidification or for treatment in the volume reduction system. The liquid waste system consists of a number of cross-ties which allows alternative treatment schemes to those discussed above. Further detail on the liquid waste system and these treatment schemes is provided in Section 11.2 of the SHUPP FSAR.
~
11.2.2 Evaluation and Findings
('
-ed with respect to the ' Acceptance Criteria
'~
The LWPS system was r:
~
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~
of Standard-Review Plen 11.2, NUREG-0800. The staff's r'evies con-sidered the capability of the proposed LWPS to meet the anticipated demands of the plant due to anticipated operational occurrences.
The potential consequences resulting from reactor operation have also
^
been considered and the staff has detennint4 the concentrations of radioactive materials in liquid effluents in unrestricted areas to be a small fraction of the limits in Table II, Column 2 of Appendix B to 10 CFR Part 20.
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28 -
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11.2.2 The staff has also considered the potential consequences resulting.
from reactor operation wiih 17. of the operating fission product in-ventory in the core being released to the primary coolant and has determined that the concentrations of radioactive materials in liquid 1
effluents in unrestric ced' areas will be a small fract' ion of the limits of Table 2, Column 2 of Appendix B to 10 CFR Part 20. As discussed in Section 11.1 of this SER, the.eteff calculated liquid effluents using thz GALE computer program based upon the treatment systems for liquid effluents described above. These source terms were presented in, Appendix D of the SHNPP DES.
The staff calculated the doses to offsite individuals utilizing the methodology of Regulatory Guide 1.109 and the liquid dispersion parameters calculated in accordance with Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents fr ct Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I".
The staff has deterriined that the proposed liquid radwaste~ treatment systems are capable of maintaining releases of racioactive materials i
in liquid etfluents such that the calculated individual doses in an unrestricted area from all pathways of exposure are less than 3.orem to the ' total body and 10 mrem to any organ.
l The staff has calculated, as noted in Section 11.1, The release of radioactive materials in liquid effluents exclusive of tritium and
~
noble gases and has found it to'be less than 5 Ci/yr per reactor
~
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29 -
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11.2.2 and the annual dose to any organ of an individual in an unrestricted area to be less than 5 millirem per year total from both reactors.
Therefore, in accordance with the option to Section II.D of Appendix I as provided in the Annex to Appendix I of 10 CFR Part 50, the staff finds that the liquid radwaste system is capable of reducing liquid radioactive effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a, Appendix I to 10 CFR Part 50,
- and the Annex to Appendix 1.
The SHMPP DES presents a' comparison of the PJi 30-2 and Appendix I design objective doses with the doses calculated for the liquid e
source tems and a comparison of the R!i 50-2 curie limitation with the projected releases for the SHNPP.
The design of th_e liquid radwaste system presented in the FSAR is different from that which was proposed at the Construction Pemit (CP) stage. At the CP stage the steca generator blowdown liquid was to be discharged. Although no process treatment system was proposed, the applicant made a commitment to install equipment capable cf re-ducing the level of activity in the blowdown stream by a factor of 3000 or greater. The applicant has since decided to install an electromagnetic fiiter to remove magnetite and other spinel type oxides which are magnetic and to remove a portion of the nonmagnetic
~
particulates. The filter is flush'ed and the water is collected in the settling tank. The flush water is then pumped to the secondary
)
i 1
1
 
u 30 -
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I; The steam generator blowdown s_,
waste low conductivity holding tank's.
11.2.2 The con-passes from the electromagnetic filter ^o the condenser.
densate polishing system provides some removal capability fo radionuclides.
t s The staff has assessed the overall capability of the radwast failure by to process waste in the event of a single major equipment and a comparison.of the design flows to the potential process rout i
Based upon this review, the staff has detemined
~
equipment capacities.
ts that the radwaste system will be adequate to process was e.
liquid rad-The staff has considered the capabilities of the proposed, f the plant due waste treatment system to, meet the anticipated demands o p'*
p-l d d that the to antir.ipated operational oc.currences and have cenc u e ti-system capacity and design flexibility are adequate to m cipated needs of the plant.
i i ns The staff has reviewed the applicant's quality assurance prov i
se-
[ '',l, for the li'. id radwaste systems, the quality group classifica for system components, and the seismic design applied to y
The design of the systems and str +.ures housi hotrsing these systems.
Guide 1.14:
lt these systems meet the criteria as set forth in Regu a ory
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ine staff has rev'. sed the provisions incorporated in the applicant's 11.2.2 design to control the release of radioactive materials in liquids due to inadvertent tank overflows and conclude that the measures proposed by the applicant are consistent with the criteria as set forth in s
Regulatory Guide 1.143.
Note A noted i Sections 11.1 and 11.4 of this SER, appi cant has J.ot provided ufficient detail on the VR syst to allow e staff to assess the c tability of the liquid radw te system to ocess the additional li uid waste generated by e VR system or t effluents resulting from this processing Until such'infoma iea 7
is presented, the SHN cannot be judg as to its compliance
'th Appendix 1.
This sectio of the SER as been drafted assuming tha the plant will meet Appendix p
1 4
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f-y Table 11.2-1 Desig, parameters of principai components considered in the calculacion of liquid effluents from SHNPP, Units 1&2 Capaci ty Safety Component Number (each)
Class Boron Recycle System 3
Recycle Evaporator F.--d Demineralizer 2
30 ft 3
Recycle Evaporator Feed Filter 2
150 gpm 3
Recycle Holdup Tank 2
84,000 gal 3
._ Recyc.le Evapo.rator Feed Pump 2
30 gpm 3
Recycle Package 2
15 gpm 3 & HMS Recycle Evaporator Concentrate Filter 2
35 gpm N!!S Recycle Evaporator Condensate Demineralizer 2
20 ft3 Recycle Evaporator Condensste Filter 2'
35 gpm -
Recycle Monitor Tank 2
10,800 gal Recycle Monitor Tank Pump 2
30 gpm Eouipment Drain Treatment System 2
350 gal
(
Reactor Coolant Drain Tank Reactor Coolant Drain Tank Pump 4
100 gpm Reactor Coolant Drain Tank Pump Heat Exchanger 2
Waste Holdup Tank s
1 25,000 gal Wahe Evaporawrhu Fump 1
35 gpm Waste Evaporator Feed Filter 1
35 gpm Waste Evaporator Package 2
15 gpm Waste Evaporator Concensate Demineralizer 1
35 gpm Waste Evaporator Condensate Tank Filter 1
35 gpn Weste Evaporator' Condensate Tank 2
10,000 gal Waste Evaporator Cmdensate Tank Pump 2
35 gpm Waste Evaporator C acentrate Tank 1
5,000 gal Waste Evap:rator Concentrate Tank Pump 2
35 gpm Moor Drain Treatment System Floor Drain Tank 4
25,000 gal Floor Drain Tank Pump 4
35 gpm Floor Drain Tank Filter 4
35 gpm Floor Drain Reverse Osmosis Unit
'2 30 gpm
~,
F.loor Drain Reverse Osmosis Feed Pump 2
30 gpm
'r;aste Monitor Tanks 2
25,0g0 gal
~
Waste Monitor Tanks Demineralizer 1
50 ft (30gpm)
Waste Monitor Tanks Pump Chemical Drain Tank 2
35 gpm 2
600 gal Chemical Drain Tank Pump 2'
35 gpm V
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Table 11.2-1
%i. <
(Continued) i i
2 25,000 gal Laundry and Hot Shower Treatment System 2
35 gpm
~ Laundry and Hot Snower Tank 2
35 gpm Laundry and Hot Shower Tank Pump 1
30 gpm Laundry and Hot Shower Tank Filter Laundry and Hot Shower Reverse Osmosis UnitLaundr 50 f t{- (30gpm) 1-0 gpu 1
2 25,000 gal Laundry and Hot Shower Demineralizer 2
100 gpm Treated Laundry and Hot Shower Tank Tank Pump 2
5,000' gal
. Treatad Laundry and Hot Shower 2
35 gpn Reverse Osmosis Concentrate TankReverse Osmosis Conce
" ~
2 10 gpm
^
2 20 gpm Reverse Osmosis Concentrate Package Reverse Osmosis Concentrate Evaporator Distillate Pump 3
15,000 gal Secondary Waste Treatment System 2
100 gpm l
^ Low conductivity Holding Tank' 2
100gpg c.1 d Low Conductivity Holding Tank Pump F~
2 70 ft
'h Secondary Waste Filter 1
25,000 gal i G*
k~
Secondary Waste Demineralizer 2
100 gpa Secondary Waste Sample Tank
?;.
i 15,000 gal
. Secondary Waste Sample Tank Pump 2
35 gpm High Conductivity Holding Tank 2
15 gpm High Conductivity Holding Tank Pump 2
4,000 gal Secondary Waste Evaporator Package Secondary Waste Evaporator Concentrate TankSeco 2
35 gpm
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Gaseous Maste Management System 11.3 f
11.3.1 Summary Odscription The gaseous waste management systems at the SHNPP' include systems which treat the nomal ventilation exhausts; the exhaust from the main condenser mechanical ' vacuum pumps, and the gaseous wastes associated with degassing primary coolant, purging the volume con d
tank, displacir.g cover gases, purging of equipment, gas sampling an
~
;4nal-ysis operations, and boron recycle process operations.
Table 11.2-1 provides a listing of the various normal ventilation systems at the SHNPP and the type of treatment associated wit Additional details are provided in Section 9.4 of the FSAR.
s system.
if a generalization can be made of the normal ventilation exhaust
.h treatment systems at the SHNPP, it is that the exhausts usually flow w
through a medium efficiency filter, a HEPA filter, and a charcoal adsorber.
The RAB normal ventilation system (RABMVS) filters air from the con-
[.
i tinuous can':.inment pijrge exhaust and areas from the RAB which con
.1
'i equipment essential for the safe shutdown of the reactors includin j;
CVCS chiller area, 480 V auxiliary bus area, areas containing non-
)S This system exhausts to the vent stack on J +;.
essential equipment etc.
the roof of the RAB.
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The waste processing areas filtered exhaust system exhausts air from
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11.3.1 the contaminated areas of the WPB and discharges to a vent stack on k
The WPB laboratory areas fume hood exhausts are i Ij the roof of the WPB.
This exhaust is 3
filtered except for the perchloric acid exhaust.
' ~ '
discharged unfiltered to the vent stack on the roof of the WPB.
i The air from the contaminated spaces of the condensate polishing
.demineralizer area is ex'hausted thrcugh the condensate polishing
~
The exhaust is dis-demineralizer area filtered exhaust system.
charged from the vent stack located on each unit's turbine building.
V The condenser vacuum pump effluent treatment system was previously E't I
discussed in Section 10.4.2 of the SER.
: q.
The containment pre-entry purge is filtered by the containment pre-entry purge system. The purge is discharged to the RAB vens swa.
Additional details of the normal ventilation systees are provided in Section 9.4 of the FSAR.
~, '.
NR-The gaseous waste processing system (GWPS) processes gases
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from the volume control tank and vent connections frca the recycle
[',,,:....%
evaporator gas stripper, the reactor coolant drain tank, the dOPI :
pressurizer relief tank and the recycle holdup tanks., The GWPS
:.q ; :
shared between the two units and consists of two waste gas compresse
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9
-- - -_- _________ _ m _-.c-w... n u,, u,..
 
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two catalytic hydrogen recombiners and ten waste gas decay tanks to 11.3.1 accumulate tr.e fission product gases. Eight gas decay tanks are used during norm?1 operation and two are used for shutdown and startup.
Hitrogen with entrained fission gases will be continuously circulated Fresh around the GWPS by one of the trio waste gas compressors.
hydrogen gas is charged to the volume control tank where it is mixed
.. with fission gases which have been stripped from the reactor coolant The contaminated hydrogen into the volume control tank gas space.
gas is continuously vented frca the volume contral tank into the circulating nitrogen stream to transport the fission gases into the GWps. The hydrogen-nitrogen mixture of fission gases is pumped by the waste gas compressor to the hydrogen recotabiner where the re-I
's After combiner converts the hydrogen to a water vapor by exidation.
n removal of the vapor the resulting gas stream is circulated to a Each gas waste gas decay tank and then back to the compressor.
decay tank is valved into the GWPS recir culation loop for one or
~
two days.
Y:
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Continued plant operation results in the buildup of pressure in the
' o7; waste gas decay tank due to the accumlation of non-removable fission 7:.. 4
: y' :
When the pressura in the gas decay tanks reac es 25 psig the gases.
alignment of the GUPS must be changed due to the. design of the e
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w 11.3.1 recombiner. The new alignn, ow from the compressor to the gas decay tanks to' the recunbtner and then back to the compres3or.
This alignment'is suitable for operation up to 100 psig.
The GWPS has an'alyzers to monitor oxygen concentrations between the oxygen supply and the hydrogen recombiner pact: age and downstream of the recombiner. Hydrogen analyzers are located in the process
~
stream entering the recombiner and in the discharge stream from the recombiner.
The applicant has indicated that the normal ventilation system com-plies with the criteria of Regulatory Guide 1.140 and that the GWPS confoms to the criteria of Regulatory Guide 1.143.
~
I,.s s
11.3.2 Evaluation Findings The gaseous waste management system was reviewed with respect to the Acceptance Criteria of SRP 11.3, IWREG-0800.
At the construction pennit st' age the off-gas from the condenser air ejectors was untreated and the ventilations systems were only filtered by HEPA filters except for the exhaust from the WPB, which was also filtered by a charcoal adsorber. The st.aff stated in the December 22, 1972 SER for the CP that treatment of the main condenser
.. r of f-gas would be required to reduce this potential source of iodine-131 to the atmosphere to bring ~the offsite doses into compliance with f
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The applicant has added the condenser effluent treatment e
11.3.2 Appendix I.
system, which can be utilized during conditions of high radioactivity from the mechanical vacuum pumps, and has added charcoal adsorbers to
* ?.
the various ventilation systems which exhaust air from contaiminated These adoitions decrease the quant'ity of iodine released from areas.
the SHNPP and aro therefore acceptable when judged against the design However, it should objective doses of Appendix I to 10 CFR Part 50.
be noted that the staff did not credit the plant with removal of the condenser effluent because the condenser effluent treatment system wi' notbeu*gizedonaroutinebasis.
t The staff has. calculated the doses to offsite individuals utilizing atmospheric dis-the methodology of Regulatory Guide 1.109 and " 3
'r julatory persion parameters calculated in accordance wit-Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-The staff has determined that the proposed gaseou
~
Cooled Reactors".
~
^
~
.,:lt radwaste t".atment systems are capable of maintaining releeies of
'U,.- ".
radioactive materials in gaseous effluents such that the calculated C
7.S :d ind.ividual doses in an unrestricted area from all pathways of expo-
: sNJ4
.& 1 sure are less than 5 mrem to the total body and 15 mrem to any orgar F." ' _ ",
from noble gases and that releases of radioiodine and radioactive material in particulate f.onn result in doses which are less than
~
15 mrem to any organ.
~
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11.3.2 The staff has also considered the potential effectiveness of aug-menting the proposed gaseous radwaste treatment systems using items of reasonably demonstrated technology. The applicant has chosen to show compliance with Section 11.0 of Appendix I to 10 CFR Part 50 by complying with the Annex to Appendix I (PJi 50-2). The SHNPP DES presents a comparison of the doses and releases calculated for the
^
SHHPP with the design objectives of Appendix I and PJ4 50-2. The ypplitant's proposed design complies with the design objectives of Pfi 50-2. Therefore, we have detennined that no further effluent treatment equipment will reduce the cumulative population doses within a 50 mile radius in a cost effective manner.
The staff has also considered the, potential consequences resulting from reactor oparation with 1". of the operating fission, product inventory in the core being released to the primary coolant and has detennined that the concentrations of radioactive materials in gaseous effluents in unrestricted areas will be a small fraction of the limits of Table 2, Column 1 of 10 CFR Part 2O'.
The capability of the proposed gaseous radwaste treatment systems to meet the anticipated demands of the plant due to operational occur-rences was also considered and it was concluded that the system capacity and design flexibility is adequate to meet-the anticipated
.needs of the station.
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The applicant's quality assurance provisions for the gaseous radwast 11.3.2 systems, the quality group classifications used for system component 5-the seismic de' sign applied to the system and the structures huusing the' radwaste systems were also reviewed. The design of the systems and the structures housing these systems meet the criteria set forti in Regulatory Guide 1.143 as indicated by the applicant in the FSAR.
However, the plant does not contain a gas analyzer between the com-I i
y..-
pre'ssors and the gas decay tanks. Such an analyzer is required in accordance with the Acceptance Criteria
* of SRP 11.3. Dcal analyzer:
are required.
The staff has reviewed the nomal ventilation system's design, test and maintenance of the HEPA filters and charcoal adsorbers, with respect to Regulatory Guide 1.140. The applicant has indicated in Chapter.1 of the FSAR, that the nomal ventilation system meets the criteria of this guide.
::.: C w.
,- m ereareruptuediksin
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The/applic-h has not indicated hether
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PS itself an if there are iquid seals anstream o the ru turt 6.r an ex osion will N
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discs, and whet er they are designed such tha
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The above information is required, along with a,canmitment to inst dual analyzers, before the GWPS can be judged to be acceptable.
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Note As noted in Sections 11.1 and 11.4 of this SER, the applic nt has n staff to provided sufficient detail on the VR system to allow th detemine the effluents which s.will result from the ope ation of the
.l Hi!PP cannot Until such informabion is presented, the VR s stem' th Appendix I.
Th s.section of the e
be udged as to its compliance SEi has been drafted assuming that the infomation to be provided
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1-ed in thi ection that the
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pi ll not negate the conclusion expre c,
lNPP will meet the design objectives of Appendrx I.
Si
;f Solid Waste Management Systems l
11.4 (j
E 11.4.'1
 
===System Description===
The solid' waste processing system (SWPS) is designed to process U -[
" wet" solid wastes and '" dry" solid
,.3 general types of solid wastes:
Met solid wastes. consist mainly of spent filter cartridges,
.. ee wastes.
$.j demineralizer resins, filter sludges, chemical drain solutions an
<c Nd bl9 evaporator bottoms which contain radioactive materials recov Dry solid wastes c'orisist mainly liquid streams during processing.
8W of ventilation air filtering media (HEPA, charcoal), contaminated ia clothing, paper, rags, laboratory glassware, and tools.
c The spent filters associated with the various ventilation sy be removed from the filter housing, wrapped, and package
@Di it&s.s The filter sludges from the liquid rad-
: m. ;
using a hydraulic ccmpactor.
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Nomal ventilation system components at the E.
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Table 11.3-1 Shearon Harris Nuclear Power Plant
~
~.
Medium Demister Heater Filter HEPA Charcoal HEPA_
X X'
X RAB Normal Ventilation System X
X X
WP Areas Filtered Exhaust System X
X WPG 1.aboratory Fume Hood
.c _
~
^ Exhaust (except grchlorite)
^
X X
X Condensate Folishing Demineral-izer Area Filtered Exhaust System X
X X
X X
X Condenser Vacuum Effluent Treatment System
* X X
X Continuous Containment Purge
., c.
:.. j
(
(Passes through RAB Nomal Ventilation System and Air-borne Radioactivity Removal System)
X X
X Containment Pre-entry Purge System
, '~
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Credit was
* System will not be used to filter releases on a routiune-basis.
given in the Appendix I evaluation.
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11.4.1 waste systems will be backwashed to a WPB filter backwash storage tank and to the WPB particulate concentrate tank. These sludges may then be solidified or sent to the volume reduction system.
Spent resins will be dewatered and then solidified by cement.
In lieu
~ f solidification, the resins may be shipped dewatered in high integrity o
containers. Evaporator bottoms will be processed in the volume reduc-tion system. Che'mical drain solutions will be solidified.
Compressible low-activity solid waste will be compacted in 55-gallon drums. The compactor is aquipped with a hood, ventilation fan and HEPA filter. The displaced air will be vented through the HEPA filter.
The applicent has indicated that the SWPS has a storage area capable of storing 1020 drums. The applicant has also indicated yhat the SWPS meets the criteria of ETSB 11-1 Rev. I which is the equivalent to Regulatory Guide 1.143.
The :pp1'icant has committed that all radioactive waste will be pack-aged in accordance with appropriate federal and state standards for burial in accordance with 49 CFR 170-179,10 CFR 20, and 10 CFR71.
All drums will be shipped and buried in accordance with 49 CFR 173.
Additional infomation, with respect to the solid radwaste system, is 7
contained in Section 1!.4 of the FSAR.
G e
____.__._________________.____m___
 
j s
11.4.2 Evaluation and findings The staff has reytewed the SWPS in accordance with the acceptance criteria of SRP 11.4, HUREG-0806. The scope of the' review included line diagrams of the system, piping and instrumentation diagrams (P& ids), and descriptive infomation for the SWPS and for those auxiliary supporting systems that are essential to the operation of the SWPS. The applicant's proposed design criteria and design bases for the SWPS, and the applicant's analysis of those criteria and bases have also been reviewed. The capability of the proposed system to process the types and volumes of wastes expected during nomal operation and anticipated operational occurrences in accord-ance with General Design Criterion 60, and provisions for the handling (s j.
of wastes relative to the requirements of 10 CFR Parts 20 and 71 and applicaole DOT regulations have also been reviewed.
The staff will not approve the design of the solid radwaste system until the applicant provides infomation detailing the manner in which various waste components are treated.
Infomation which is missing includes' (1) a de ailed descri ' ion of the volume reduction
. v] -h hde N l
system which addresses;
\\
4af (a) how the s atem operate 2; (b) expect input stream their volumes, and asjociated ac vi ties; (c) iquid and gase s effluents resulting from system operation;
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11.4.2 (d) volume reducti factors achi ed; (e) activity sociated wi th he c
.aole ash; and (f) confo.ance with Regulatorf Guides 8.8,. 1.140, and 1.143, t/
and BTP CMEB 9.5,1 of SRP 9.5.1;
'2 ) a rawing (CAR 5-G-8
) which e,gh ce header h> " id 1)g'4
){'f 5
and e was e concentrate i
If p-the ]) Y f(
mitment to r prtsrah whereby the prese e of {ee water, i
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was contain is verifi and commf+..ent to repro'ressi the
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contain nen free water is cred; JP
,i4) 'a description of the by n'.t symm;
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(5) details on the manner in which the filter sludge from t N~
following filters will be handled:
f, y
(a) reactor coolant; N1 r
(b) seal water ir.jscticr.; '
M (c) seal water return; (d) boric acid; IN (e)
BRS recycle evaporator feed; g-(f) BRS recycle evaporator con $'entrate; PS pj(g)- -seepadsey g(h) recycle evaporator condensate; 7(i), ' fuel _ pool _f.emineca142er1
'( )90% po01 drEIN1'lts.ptM.f.ica.tdrtng and (N) ' fuel poo1TmmerrTnd y U
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details showing that, the vent exhaust from the spent res n i
d by a HEPA s
11.4.2 (6) storage tanks and the decanting tanks are filtere filter in accorda'n.e with BTP ETSB 11-3 of SR the concentrates The applicant has indicated that heat tracing from k is not requir line of the recycle evaporator to the boric acid tan t crysta11ize at because the 4% weight beric acid solutfon will no is required before pabient temperatures and that a 12% weight solution The staff's position is that a 4% by crystallization will occur.
llize at 56-57 F.
Therefore, weight solution of boric acid will crysta t s line of the heat tracing should be included from the cor. centra e recycle evaporator to the boric acid tank.
ll be considered Until the above infomation is provided.the SWPS wi unacceptable.
ara (PCP).
The applicant has no: provided the Process Control Progr h issuance of the The PCP is not required until 6 nonths prior to t e y
The PCP will be judged as to its acceptability Cperating License.
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when it is submitteo.
.>.l d Sampling Systems
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Process and Effluent Radiological Monitoring an o
11.5 i z.
Summary Description d sampling
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11.5.1 The process and efiluent radiological monitoring an
-e ing radioactivity systens are desigreed to provide infomation concern f ' * * '
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11.5.1 levels in systems throughout the plant, indicate radioactive leakage between systems, monitor equipment and perfomance, and monitor and control radicactivity levels in plant discharges to the environs.
At the SHNPP, the airborne ef fluent sampling and monitoring systems
.are located in the plant vents located on the RAB and the WPB. For liquid effluents, the effluent monitor locations are downstream of the pumps of the LMPS waste monitor tanks, the treated laundry and hot ~ shower tanks, and the secondary waste sample tanks. Ef fluent
~
~
monitors are also located to monitor the industrial waste sumps of the turbine buildings, the discharge from the tank area drafn transfer pumps and the service water system.
/.
n.
Table 11.5-1 contains a listing of both the process and effluent monitors for airborne and liquid sources. This Table also includes the type of radioactivity monitored for airborne effluents, the type of monitor used, and the plant specific number of the monitor for ease of reference. Sections 11.5 and 12.3.4 of the FSAR present' a detailed discussion of the process and effluent l'.onitoring system.
11.5.2 Evaluation and Findings The staff has reviewed the process and effluent nonitoring system with respect to the Acceptance Criteria of SRP 11.5, HUREG-0800. As a result of this review, the following evaluation and findings have been made.
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.___.____.___________.E__._._.__.________.___________
 
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11.5.2 Acceptance Criteria II.C.1.a of SRP I'.5 states that the gaseous 1
and liquid process streams and effluent release points should be monitored and sampled according to Tables 1 and 2 of SRP 11.5.
Infomation provided in Section 11.5 of the FSAR indicated that the SHNPP did not meet these criteria in the following' areas:
(1) The turbine gland seal condenser exhaust and the mechanical vacuum pump exhaust are not monitored and sampled in accord-ance with Table 1.
(2) The conderser vacuum pump effluer.t is not sampled in accord-ance with Table 1.
(3) There is no effluent monitor for the turbine building vents (release paints 3A and 38) as required by Table 1 and' sampling i',..
provisicns are not provided.
(4) The ap ican has provided contradic ry in)gmation on the cont nment pr -entry purge and th continuou containment q,.?l\\;
l p ige monitorin features of the HHPP. The s af f's positi n
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that both linet shall be no tored on a conti aus ba s and
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that bc-5 monitors 011, o high radiation signal, isolate curge operation in an automatic fashion.
(,
he servi wa r syste, does not pos ss th capab is to ob ain continuo ample as re red by Tabi gg,
j,,li l The applicant has indicated, in response to a staff question, that the process and effluent monitoring program will meet the guidelines of i
1
 
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b 11.5.2 Position C of Regulatory Guide 4.15,with one e eption. This e ep-tion is that e SHNPP will ke use of "n ionally recogni d stand-ards" and 11 not limi
.hemselves to SS traceable s dards only.
It is e staff's po tion that any nationally re gnized standard" wil be NBS trac ble. Therefo
, the staff d, s not accept this pro-osed deviat n to Position of RegulatoryMuide 4.15.
r The applicant has not addressed the capability of the process and effluent monitoring program to meet the guidelines of Position C and Table 2 of Regulatory Guide 1.97.
pplicant has addressed items II.F.1, d
Attachments 1 and 2 of HUREG-0737 which covers similar criteria o effluent monitors to that proposed by Regulatory uide 1.97.s %'owever, M
[.
t cant'has addr e
uch of t nf required by
.F.1', A tach.
ts 1 and 2.
The applicant h not add ssed the i
fo i wing items f Attachment 1:
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(a) monitoring location or points of ampli ng; (tI) instrumentation r main ste safety and pressure relief valve E /T3 7f/
O (d
des on d M
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11.5.2 (c) capability of the on-site laboratory to analyze or measure these semples; and (d) ions for limit g occu tional dose pers ae g i analysts of sar es.
,N g giu.)
The applicant can not assure representative samples from3veritnrs r-adie::tiv: p* :::: nc =: :nd t:9 centent because the capacity of the recirculation pumpi do not meet the criteria of II.2.a of SRP 11.5.
b Th a pumps which do not comply are the owi ng: M 'M p(
O tt (a
waste holdup tank;
{p (D) was evaporato.ondensate tank; (c) waste mon r tanks; f
- (:. V (d) rec e holduc s_
recycla monite -
ank.
In response to a staff question, the applicant stated that the above pumps could operate at run-out and thus meet acceptance criteria of II.2.a of SRP 11.5.
It is our position that the pumps could not te operated at scie run-out condition for the period of time required to meet this acceptance criteria. Furthennore, the staff finds it
~
difficult to envision the plant operators using these pumps at the run-out condition. The applicant should propose. an alternative
~
means of ensuring tha+. th:. contents of the various liquid waste may be sampled in a repreuntative nanner.
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11.5.2 Other areas of the acceptance criteria of SRP 11.5 which the applicant has not addressed or which deviate from the acceptance criteria include:
(a) capability to r lace \\or decontanin onitors utilize or the pro \\
N ss system r losing 1-'-
gaseous efflu nt withou openi d
qp 9W.
., 6' the capabi ity to isolate the effluent stre
()
the divers al ves oc ted t t-1
'b
. P l* -
mo do not fai in the closed position; [T d'
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~t confoman of n
- ESF instru. tat n to th desig g,.
. of eend 11.5-A of S as not been a ressed; aiid
['
(d) incorporation of administrative controls and procedures to minimize inadvertent or accidental releases of radioactive liquids has not h
been addressed, k
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The turbine building drain monitors and the tank area drain conitors do not provide a record of effluent flow. Therefore, there appears to
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t'e no neans to detemine the quantity of activity released nor the g
v.-
S.,1,4 volume released in accordance with Regulatory Guide 1.21.
It is the
,,l staff's position that the SHNPP possess the capability to detemine the quantity of effluents released from these two sources.
g-The a licant h not provided sufficient 'nfoma on in the FSAR to j
allsw the staff to detemine whether t releases fr the vents of (1e bor/
on recycic system are routed in s' ch a manner that a uate mo:1 toring l
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apd sampling of these urces is present at the SHNPP. Sucb4cfomation (J
i s required.
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Wy ML:r 11.5.2 The ap licant has provided cont adictory infomation on the operation of
-the vent valve on the WPB cooling water surge tank.
Section 9.2.10.2.2 states th' t this valve loses automatically on a high radia-of the FS a
tion signal from the discharge of the WPB cooling water monitor (REM-3544).
he applicant's response FSAR question 460.35 stated that upon rece1 t of an alann from REM-3 4, the operator must take the action to isolat the surge tank. The man er in which the vent valve is operated should be clarified, but in eith r case the vent valve should be isolated 1 mediately because failur of "a seal in either the waste gas compres or or the catalytic recmb ner of the waste gas system could result in new and significant rele se path for effluents.
O As a result of their responses to staff questions on the FSAR, the g.,
U applicant needs to revise various positions of the FSAR. These revisions include:
p 1) igures 9.2-Van 10.1.0-6 show sam ing poin
-11, \\, '
12 b@.- Yp c
of the steam g tor blowdown; an (2) able 9.3.2-2, Figure 9.3.2-2, and Section 9.3.2.2.2 to reflect d Jy A
D {T p, fa,b sampling of the service water system; and Y
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y 3
3 ).
Table
.5.2-re t
. o ' + ri n epi
::tFnts of
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HUR G-0737, Attachments 1 and 2.
~
l The applicant has not addressed the monitoring of t e effluent frcxn l
the volume reduction system. ThiI must be addressed.
48 k_._
 
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The staff's review of the process and effluent monitoring system has 11.5.2 Those items which have not been not addressed some items of SRP 11.5.
addressed will be reviewed at the time the Radiological Effluent Technical Specifications are reviewed. Those areas of the process and effluent monitoring system which will be reviewed at that time include:
icq sampling frequencies, required analyses, instrument alarm /.tjag (1) set points, calibration, and sensitivities; and
~
frequency of routine instrument calibration, maintenance, and
'(2) inspections.
a The process and effluent monitoriig systems cannot be judged as adequacy, until the above items are addressed.
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g Liquid and airborne process and ef fluent. monitor
.y.
system at the Shearon Harris Nuclear Power Plant Table 11.5-1 Monitor Monitor Type Monitoring 4
Number a
Monitor A.
Airborne Process B scin NG 21 REM-3545 Gas Decay Tank S sein, Y sein, 1.
RE-1FL-3E06 P, I, NG S sein Fuel Handling Butidtag RE-1FL-3507 2.
}iemal Exhaust S scin, Y scin.
REM-1FL-3508BSB P, I, NG S scin Fuel Handling Building B scin, y scin, 3.
Emergency Exhaust REM-1FL-3508ASA 6 scin REM-1AV-3531 P, I, NG S scin, Y scin, S scin Reattor Auxiliary Building Momal REM-2AV-3531 P. I, NG S scin, Y scin, 4.
S sein l{
Exhaust
.s i REM-1AV-3532A P,1. NG S scin,'Y scin,
'-i ris
.i S scin Reactor Auxiliary Building Emergency REM-1AV-3532B P. I, NG S scin, Y scin, s
E-S Min REM-2AV-3532A P, I, NG S scin, Y scin,
.~
Exhaust S sein B scin, Y scin.
REM-2AV-3532B P, I, NG B scin x
v-D 30 S scin NG
' ra REM-1TV-3534 S scin NG Condenser Yacutn Pump REM-2TV-3534 t'S 6.
9 Q' Effluent Treatment tfM System S sein, Y scin,
@..I; REN-1LT-3502ASA P, I, NG B scin Continuous Containment
/$.fi Purge REM-1LT-3502BS3 P, I, NG B scin, Y scin, 7.
S sein S scin, Y sein, RD4-2LT-3502ASA P, I, NG B sein S scin, Y scin, P I,NG RDt-2LT-3502BSB B sein
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' :p Table 11.5-1 (Continued) i sx..
, '1; l
v, 9
Monitor Monitor J~
Monito'r Number Monitoring Type
.. y,.
B.
Liquid Process
..a Y sein 1.
Component Cooling Water 1 REM-3501A.
Y scin
. O System.
1 REM-35018 Y sein
~ 71 2 REM-3504 Y sein 2 REM-35018 n
Y scin
.'l 2.
Auxiliary Stems Con-21-REM-3525A.
Y scin densate Tank.
21-REM-3525A Y scin 3.
Steen Generator 1 REM-3527 Y scin Blowdown 2 REM-3527 '
Y scin 4.
Auxiliary Steam 21 REM-3543
.. J. :,l.i Condensate Waste Processing Systen '. '. h:':$,'l- /,
- '\\"]
^
Y sein 5.
Waste Processing 1 REM-3544 Building Cooling Water C.
Airborne Effluent 1.
Plant Yeat. (Release REM-1AV-3509SA P, I, NG S scin, y scin, L.% %
Point 1) 8 sein f.'-[,7?,
REM-2AV-35095A P, I, NG B sein, Y scin, S sein i.. x. ; /.
* fi'* r'
.r.h. 9 2.
Waste Processing Building jjl.ih.s Exhaust Systems -
n:d hi (a) Release Point 5 REM-1WY-3546 P, I, NG B scin, Y scin,
: ~.:
3:i$'
S scin lP' (b) Release Point 5A REM-1WV-3547 P, I, NG B scin, Y scin, B sein
~
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3.
Turbine Building Vent Stack i
(a) Release Point 3A
'' r e
~
Ph:d,.9 d;.]
(b) Release Point 3B
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Table 11.5-1 (Continued)
Monitor Monitor Monitor Number Monitoring Type D.'
Liquid Effluent Y sein 1.
Service Water System REM-1SW-3500ASB Y scin REM-2SW-3500ASB Y scin REM-1SW-3500BSA Y sein REM-2SW-3500BSA Y scin REM-1SW-3500CSA Y scin REM-25W-3500CSA Y scin REM-1SW-3500DSB Y scin REM-25W-3500DSB Y sein 2.
Waste Moni*.or Tanks REM-21WL-3541 Y sein 3.
Turbine Bu;1 ding Drain REM-1MD-3528 Y sci n '--
P.EM-2MD-3528 s.)
4.
Tank Area Drain REM-1MD-3530 Y scin Y sein Transfer Pumps REM-2MD-3530 Y scia l
5.
Treated Laundry and REM-1WL-3540 l
Hot Shower Tank Pumps Y sein 6.
Secondary Waste Sample REM-21WS-3542 Tank Pumps l
P = Particulate I = Radiciodine NG = Noble Gases
~
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l l
l c,., Fi.
pc.,
9
 
i r.- 1..
11.5.7.3 Liquid Tank Failure Accident The staff evaluatbd the consequences of tank failures for tanks located outside the reactor containment which could result in releases of liquids containing radioactive materials to the environs. This review was conducted in accordance with the Acceptance Criteria of SRP 15.7.3, NUREG-0300.
Considered in the evaluation are (1) the radionuclide inventory in each tank assuming a 0.12 percent operating power fission product source term, (2) a tank liquid inventory equal to 80 percent of its design capacity, (3) mit;igating effects incor-porated into the plant design, and (4) the effects of site geology and hydrology.
The results of this analysis were presented in Section 2.4.6 of this SER.
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Latest revision as of 06:07, 26 May 2025

Forwards Meteorology & Effluent Treatment Branch Input to Draft Ser.Assumption That Draft Meets 10CFR50,App I Objectives Will Be Verified When Fluidize Bed Dryer Effluents calculated.NUREG-0737,Item III.D.1.1 Incomplete
ML20079L079
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 01/06/1983
From: Houston R
Office of Nuclear Reactor Regulation
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20079F427 List:
References
FOIA-84-35, TASK-3.D.1.1, TASK-TM NUDOCS 8301260036
Download: ML20079L079 (58)
v • d • e


Text

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Sfiff DISTRIlulTIO!!:

Docket File 50-400 i-Docket File 50-401 (w/o, enc 1)

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I:ETB Reading File.

Oce'< c t "n t. 50 t 0/.* 01 dAMd 6' $3 ADRP Reading File IIETB Docket File C V..*C # FOR:

Thonas ". !'ovah, /.ssistant Director for Licensing, DL FPH:

_R.1.'cync !!ouston,' A:sista.t Dire: tor for P.cdiation Protection, DSI S'JCJt0T:

!!ETB It' L'T FO?. 02/FT S.*.:. ETY E*'AL'JATICt! F.EDO~ti FOP. S!! EAT.0"

!!A?.P.IS, Ut!IT l'OS.1 W.'D 2 Enclosed for ycur n:e is the I;cteorol:7y and Effluent Trettaent tiranch (!'.ETB),

Effluent Trect-.ent Systens Section (ETSS) input to the draft Safety Ev 1uation Rct rt (SER) for'the Shecron !!arris I.iuclear Pcuer Plant (Sit!PP).

t i

Ti 1 r inout-is;c revised version of the draft v.hich we r.revided June 25, 1902.

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Thc nu-!r;r of onen itens ero too nicerous to detail in this nmorandtn.

It sbruld to noted that !'c draft has asstmed that t'10 plant ' sets the detien cNc:tivas of f.ppandix I to 10 CFR Part 50. This esstnption will be vorified once Cerolina Pouer and Light Connany orovides the additiomi infor.tation to allo: 'EE to calculcto the effluente resulting fre. or.: ration of t"e fluidi:c bc:.'r; or.

Car input to iter. III.D.1.1 of EUREG-0737 is not included. The applicant i

re:ent1.v prcvider' this infornation in k1s'enent 3 to the FSAP..

I:ET?'s revist is not ccepleted. The results of this review &,ill be fonverded to you upon ccrpl etion.

If there are questions concerning the ETSS revieu, ple se contabt J. Hc.yes r

(x27~n9) Wo is the reviwer for SI'."PP.

The "Warolory Section inout to the drrf t SEP. ucs tran'itti6 to DL en 10/27/2?.

I ann c'!9rle: ented on 10/2f./'.2. Tuo cPon isse2: rc : in in this area.

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.-.=..c cn D..TalMC~~iBDit:en, Assistant Dirc:ter fer Eadie.tien Pratsetion g

gg Divi Sion of S,este~.s Intecration U

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I. 't _6. 5.,1 Eligineered Safety Feature (ESF) Atmospheric Cleanup System 6.5.1.1 Summary Description The engineered safety feature (ESF) atmospheric cleanup systems at the Shearon Harris Muclear Power Plant (SHHPP) consist of process equipment and instrumentation necessary to control the release of radioactive iodine and particulate material following a design basis accident (DBA). At the SHNPP, there are three filtration systems designed for this purpose. These systems are: (1) Reactor Auxiliary Building (RAB) Emergency Exhaust System; s 12R' Fu'el Handling Building (FHB) Emergency Exhaust System; and (3) control Roon Energency Filtration ' System. The RAB energency air exhaust systtm consists of, in order, a demister, electrical heating coil, pre-filter, HEPA filter, charcoal adsorber, I liEPA filter, and decay heat cooling air connection. The purpose of this system is to limit the potential for post-accident radio-logical releases to contaminated portions of the RAB. Those areas which are filtered include the rooms containing the charging pump, the RHR heat exchanger, containment spray and RHR pumps, and the mechanical, electrical and heating and ventilation penetration areas and rooms.. Upon receipt of a Safety Injection Actuation Signal (SIAS)., air operated valves on the nomal ventilation penetration into areas containing equipment essential for safe shutdown close and both RAD emergency exhausts are automatically energized. Either filter unit may then be manually de-energized from'the control room and placed en standby. ~ ~ } k ,.y, ,. 2

o 4 6.5.1.1 By continually exhausting air a negative pressure of 1/8 inth water gauge (ifGlis established. Pressure is then controlled by the airflow control system which' adjusts the variable inlet vanes of the exhaust fans. The'FHB emergency air exhaust system consists of components which are identical to the RAB emergency exhaust with the exception that j the charcoal adsorber section is two inches deep whila that of the RAB system is 4 inches deep. The purpose of the FHB system is to Saintain the fuel

  • storage building at a negative pressure so that

~ any radioactive iodine or particulates released to the building will be contained within the building and then filtered prior to release. The actuation of the FHB system is from a signal initiated'by one l of the four radiation monitors located around the walls of each of the fuel pools. Both trains will be actu'ated initially. Either train may be manually de-energized frota the Control Room and placed on standby'. Pressure in the FHB is maintained at 1/8 inch ilG and controlled by the a,irflow control system. The control room emergency filtration system consists or two-100% capacity filtration systems. Each filtration system inc1'ud,es, in order, a demister, t:0 electric heating coils arranged in series. f. (one operating and one on standby), a HEPA filter, a charcoal adsorber,' and another HEPA filter. The purpose of the co,ntrol room emergency filtration systen is to limit the amount of radioactivity introduced into the control room following an accident and filter radioactivity .t > Q. /L m

3-3 6.5.1.1 already in the cbntrol rocr. such that doses to control roca operators will be within the design criterion of GDC 19 of 10 CFR Part 50, Appendix A. Upon receipt of a Safety Injection signal (SIS) or a high chlorine concentration signal at the outside air intakes, the outside intake isolation valves will be closed, the control room purge system isolation valves will be closed, one fan'in each emergency filtration train will start and the respective fan valve 2 i opened. ' All isolation valves in the normal exhaust system will close and the exhaust fans de-energized. All of these actions will occur automatically. Upon receipt of a high radiation signal from the radiation monitor located within each air intake, the air intake l on the affected side of the control building will automatically isolate and the emergency filtration system will start. Upon com-pletion of the above automatic functions, the operator will place one _of the emergency filtration trains on standby, select and open one_ emergency outside air intake based upon radiation and chlorine readings, and open exhaust bypass dampers for laboratory and kitchen bypass exhaust. The control room emergency filtration system will process a mixture of control room. air and a small cuantity of outside air through HEPA filters and charcoal adsorbers and maintain the :ontrol envelope e F e e e edsww*am <- g'+e-e se tge ee c om s - we o t w. ., em w e me g os, p. og ,e _#~

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.<.;a 6.5.1.1 under a positive pressure of -rl/8 i :h water gauge. Air is con-tinuously drawn for the supply air ubsys. tem, blended with outside air, precessed through the filtrati n system and supplied to the control room. Sections 6.5.1 and 9.4.1 of the Har is FSAR contain a detailed description the ESF filtratio,n syst as. . 3. 5.1.2. Eval.uation and Findings The staff's review included the cap bility of ESF filter systens to operate after a design basis acc dent; an evaluation of the systems design, design criteria, de ign objectives, components design and qualification testing; and desi n provisions incorporated to. 3i.. ' facilitate operation and maintenanc and testing of components to ensure continued acceptable perfour :nce. The staff's review was based upon the relevant requirement ; of (1) GDC 19 of of, Appendix A to 10 CFR Part 50 for systems desit ied for the habitability of the control room under accident condit: ms; (2) GDC 61 for the design of systems for radioactivity contrt under postulated accident con- ,ditions;.and (3) GDC 64 for the moi :toring of radioactive releases under postulated accident conditici 2. l The ESF filter systems were not re' iewed according to SRP 6.5.1 of NUREG-0800 because the acceptants criteria of this document calls.. for the design, testing, and :onstruction of components of

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i t 5.5.1.2 the ESF filter system to AflSI N509-1980. These standards were not in existence at the time the SHNPP ESF filter systems were designed . nor when the equipment was purchased. Therefore, the review of the ESF filter systems was conducted utilizing SRP 6.5.1, Rev.1, of !!UREG-75/087, which more adequately reflects the criteria which were in effect at the time the SHNPP ESF filter system was designed. . ln those. instances where the equipment was purchased prior to Rev.1, conformance with prior document cri,teria, whether Regulatory Guide 1.52, Rev.1, or SRP_6.5.1, Rev. O, was considered acceptable. As a result of this review, the following evaluations and 51 ridings have been made. 1 The applicant has provided a comparison of the design of the SHNPP ESF filter systems with the regulatory positions of Regulatory Guide 1.52, Rev. 2 March 1978 in a Table of the FSAR. The staff has de-termined that the applicant has proposed few exceptions to Regulatory Guide 1.52 and that these exceptions are trivial in nature and judged to.be acceptabla. The staff credited the applicant with 95% removal efficiency for' methyl radiciodine for the FHB emergency exhaust system and 99% for methyl radiciodine for all other ESF filter systems". As a result of the staff's rev.iew of the applicant's designs, design criteria, and design bases for-ESF atmospheric ' cleanup systeas and ____________[_$__m_ _ _ _.... _ _ ~ _ _ _ _ __Y ^ h 7

, f' -f S. ~ the systems' confomance to applicable regulatio ts', guides and industry 6.5.1.2 standards, the staff has concluded that the ESF atmospheric cleanup systems include the equ'ipment and instrumentation to control the release of radioactive materials in airborne effluents following a design basis accident. The staff finds the proposed ESF atmosphere cleanup systems acceptable and the filter efficiencies given in Table 2 of Regulatory Guide 1.52 appropriate for use in the l ' accident analyses. L 10.4.2 Main Condenser Evacuation System l 10.4.2.1 Summary Description The main condenser evacuation system (MCES) of each unit cons'. ts of two 100% capacity mechanical vacuum pumps.which serve the main At startup, one or both pumps may be operated.to evacuate condenser. the condenser. Once operating pressure is obtained, one pump is placed on standby. On startup, and prior to turbine operation, the p non-condensible gases will be discharged dir,ectly to the atmosphere r. P in the turbine building at without filtration. With turbine operation the discharge from the mechanical vacuum pumps is directed L' to the turbine building vent stack without filtration. ~ The.non-condensible gases flow to a moisture separator tjhere most . of the water vapor is condensed. The condensed water' drains to the i industrial waste sumps. However,'the discharge from these sumps t,t. [A 5 'a Qn. w ~ .? ' ~ " ' ' ~ ^ * ' - = ~ ~ ~.. -.. ____-________I__'__^'____,

. _f \\. 10.4.2.1 - will be directed to the secondary waste system for treatment on de-tection of radioactivity by m6nitor REM-3528. The airborne disc.harge from the mechanical vacuum pumps is monitored for radioactivity. Any radioactivity exceeding the monitor set point will initiate an alarm by the radiation monitors. The applicant has indicated that there is no potentially explosive gas mixture present in the MCES during normal operation, or duri6g shutdown or startup conditions. A more detatied discussion of the MCES is presented in Section 10.4.2 of the FSAR. l-10.4.2.2 Evaluation Findin5s I . The staff's review included the system's capability to process Fi I radioactive gases and the design provisions incorporated to monitor and control releases of radioactive materials in gaseous effluents in accordance with GDC 60 and 64 of Appendix A to 10 CFR Part 50. The quality group classification of equipment and components used to collect gaseous radioactive effluents was reviewed relative to the guidelines of Regulatory Guide 1.26. The staff reviewed the applicant's system descriptions, piping and instrumentation diagrami, and design criteria for components of the MCES with respect to the Acceptance Criteria of SRP 10.4.2 of flVREG-0800. ( '%, + 4 meme s s+hmeemem 4. e w ---4.- apes *= w.a

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~ o "8~ ~ -.f..- 10.4.2.2 The staff, in a question to the applicant, stated that the 14CES contains no provisions for sampling and monitoring discharges frca the turbine building vent during startup operations as specified in Table 1 of SRP 11.5. The applicant, in response to this question, stated that the discharge would be monitored by noble gas monitor RB4-3534 because valve 7AE-B3-1 is ' nomally open butterfly valve which would be open during hogging a [perations, thus resulting in a dual exhaust during these operations. The flow passing by monitor RBi-3534 would allow action to be taken to close valves 7AE-33-1 and 7AE-B9-1 on a high radiation signal and the rerouting of the off-gas through the condenser vacuum penp effluent treatment system (CVFi M. The CYPETS consists.of a demister, an electrical heating er HEPA filter, a 4-inch chercoal adsorber, t another HEPA filter, and two-100% capacity fans in parallel. It is the staff's position that the release of the off gas during hogging operations must be monitored as noted in Table 1 of SRP 11.5. As long as flow is maintained through valves 7AE-B3-1 ak 7AE-B9-1 / no additional monitor is required. However, the staff believes that since the purpose of the hogging operation is to establish a vacuum in.the condenser as soon as possible, there will be occasions where the plant staff will desire to discharge the off gas only to the turbine building atmosphere. 'Therefore, the staff will cake it +- e r =.,-~------n ~w m r---*r-- . m -w

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10.4.2.2 a enliition of the license that no discharges may occur form the nachanical vacuum pumps without the effluent being nonitored. The NRC staff would allow isuch a release only.if there were a conitor on the exhaust to the turbine building, y 3.- N.. The applicant has indicated that the main condenser is constructed to the Heat Exchanger Institute's " Standards for Steam Surface Condensers"(pL.n.x } u ik -.,,.

  • d,..-: Z, !J

/ fy+ ht,.,has.-nut eddressed - ether the MCES cg;d ty is,, con-8 .p sistent with the guidelines given by the above industrial standard py ( AC ~ as required by the Acceptance Criteria of SRP 10.4.2. The oaff requests at the ap icant.provi.b g justificati why. e capacity of t MCES is r o consistent th the guide 'nes o'f the " Standards f Steam S face Condense k The applicant has indicated that the quality group classification pFj (IM to which the liCES is designed is non-nuclear safety, Category 1 ,,,,g f for the condensate vacuum pump effluent treatment syst:n ud non-nuclear safety, Category 2 for the mechanical vacuum pumps. Mc :n'r, he applicant has not indicated, in Secton 3.2 of the FSAR, W these quality group classifications coerelate with Quality Group D of R'egu' tory Guide 1.26. Sch ; c;.. a dv.. e pis, ued. neeus av T.e un w i e coniu n.i i.v '= ; & :. " " ~ h c' m M ".2. u.. ./ With the at.a. g of the above items the staf f'will be able to judge the MCES's conformw.e with the acceptance criteria of SRP 10.4.2 t* b

f'.. ~ 10 ~ x 10.4.2.2 and whether the liCES has met the requirements of GD; 69 and 64 with respect to the control and monitoring of releases of radica:tive materials to the envirbnment and whether the MCES has met the re-quirements of the industrial standard " Standards for Steam Surface Condensers". 10.4.3 Turbine Gland Sealing System 10.4.3.1 Summary Description The turbine gland sealing system provides sealing steam to the main turbine generator shaft to prevent the leakage of air into the turbine casings and the potentini escape of radioactive steam into the turbine building. A portion of the main steam supply.is passed c. through' the t.urbine gfand seals and condensed in.the gland steam condenser. The condensate is returned to the main condenser hot tell ~ while non-condensible gares are discharged by two 1007, capacity blowers to the environment. A core detailed discussion of the turbine gland sealing systen is presented in Section 10.4.3 of the FSAR. 10.4.3.2 E' valuation and Findings m The 'staf f has reviewed the turbine gland sealing system with respect to the Acceptance Criteria of.SRP 10.4.3 of flVREG-0800. The scope of this review included the source of sealing steam'and the provisions incorporated to monitor and control releases of gaseous radioactive effluents in accordance with GD0 60 and 6'4 of Appendix A to 10 CFR 7 >Rj 1 l I

l f. ~ ~ 10.4.3.2 Part 50. The staff has reviewed the applicant's system description and design criteria for the components of the turbine gland sealing systen. QN The applicant has indicated that the quality group classification

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to which the turbine gland sealing system has been designed is ncn-g v h nn. -r 6t4as wot-4dicated,'w)i " nuclear safety, Category ?. i ti Sec.t.o n 3,.-2 o'f-thMSAR, -r =p c h ::W ' [t "a hy;tese Quality Group D of Re ulatory Guide 1.26. S;h + a e r:1 w corr;1:? 9::d: t; b; pr;"4 dad. Th; i :igr :h=1 d conforA to the Acceptance Criteria of SRP 10.4.3. t' The venting of the turbine gland seal condenser's noncondensable gases is not monitored as req'uired by Table 1 of SRP 11.5. The applicant stated in response to a staff qu,th(tions, that they do not consider the turbine gland seal condenser a principal source of radionuclide release and therefore it does not require non'aring because the expected activity is far below guideline values. 1:hile the turbine gland seal condenser is not a principal source, it is, nevertheless, a source and a source which, accorcing to GDC 64 of Appendix A to 10 CFR Part 50, requires monitoring and which as noted e e. P 4 I

12 - 1 10.4.3.2 in Table 1 of SRP 11.5 also requires sampling. Therefore, it is the staff's position that monitoring of the turbine gland seal condenser occur and that the associated sampling also occur. The co initment by the applicant to meet the Acceptance Criteria of . the above SRP will allow the staff to conclude that the turbine gland sealing system meets the requirements of GDC 60'and 64 with respect to the control and monitoring of releases of radioactive ~ ~ maieria'1s to the environment by providing a controlled and monitored turbirie gland sealing system. 11.0 Radioactive Waste Management 11.1 Source Terms l L 11.1.1 Summary Des ~cription The applicant calculated the liquid and gaseous effluents from the Shearon Harris Nuclear Power Plant (SHUPP) utilizing the PWR GALE computer progran. The applicant utilized the source assumptions of -Regdlatory Guide 1.112. " Calculation of Releases of Radioactive ( Materials in Gaseous and Liquid Efflu*ents from Light-Mater-Cooled Power Reactors", and HUREG-0017, " Calculation of Releases of Radio-active Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs)". Gaseous effluents were calculated from such sources as offgases from the main condenser evacuation' system; leak- ~ age _ to containment, the reactor. aux'iliary building, and the turbine building; noble gases stripped fr'om the primary coolant during normal i g y=,, -e -m S, g w-e. en-* - + = w _7e_______e__d__p.______f._ _gyg ,i__1. <-caw r.por.: .e u____.o. 1

. [w _. y .11.1 . operation and at shutdown; and cover and vent gases frca tanks and i equipment containing radioactive material. Liquid effluents were calculated from such sour'ces as shim bleed, leakage collected in 4 equipment and floor drains such as found in as the reactor auxiliary building, fuel handling, waste processing, and turbine buildings, contaminat'ed liquids from anticipated plant operat'fons such as resin sluices, filter backwash, decontamination solutions, sample station drains, and detergent wastes. The staff has perfomed an independent calculation cf the primary l and secondary coolant concentrations and of the release rates'of radioactive materials using the information supplied in the appli-( cant's FSAR, the GALE computer program, and the methodology presented s, Table 11.1-1 presents the principal parameters which in HUREG-0017. were used in this independent calculation of the source tems. These source terms were utilized in Sections 11.2 and 11.3 to calculat,e individual doses in accordance with the mathematical models and guidance contained in Regulatory Guide 1.109, " Calculation of Annual. ' Average Doses to Man From Routine Releases of Reactor Effluents for the Pur. pose of Evaluating Compliance with 10 CFR Part 50, Appendix I." Liquid effiuents occur from the waste monitoring tanks, the treated laundry and the hot shower storage tanks and the secondary waste sample tanks. The sources of wastes to these tanks are discussed in a E w -. ~

11.1 Section 11.2 of this SER. One source of waste to the waste monitor tanks which is not discussed in Section 11.2 is that originating from the baron recycle system (BRS). Distillate from the BRS evaporators can be pumped to the waste monitor tank for discharge offsite. The staff's estimate of the liquid effluents was based upon the information presented in Tables 11.1-1 and 11.1-2. The applicant as'sumid that floor drain wastes would be treated by the reverse ~ esmosis (RO) unit of the floor drain treatment subsystem. The stcff calculated liquid effluents assuming that the floor drains would be treated by the RO unit. However, the results indicated that over t. 5 curies per year per unit would be reicased based upon t'.m 7taff I \\ projected inputs to the floor drain treatment subsystem. this would not comply with one of the requirements of the Annex to Appendix I of 10 CFR Part 50 which the applicant chose to use to show compliance with Section II.D of Appendix I, the staff assumed that wastes collected by the floor drain tanks would be treated by the waste evaporator in the equipment drain treatment subsystem. The applicant had indicated in the FSAR that these evaporators would be available to treat the floor drain wastes when they contained high activity. The staff then calculated the effluents from floor drains based upon the the use of this evaporator. With it's use the effluents frcm the SHNPP could satisfy the criterion of Secti,on A.2 of the Annex to Appendix 1. %. s ' t ..=w.=

. e f. 11.1 In its evaluation, the staff determined that adequate holdup and processing time were available for the treatment of the floor drain wastes and the equipment d' rain wastes. The applicant assumed in his analysis that the wastes collected by the secondary waste low conductivity holding tank would be processed by an evaporator in addition to a inixed bed decineralizer. The staff's review of the applicant's description of this system in-dicat'ed that these wastes would usually be treated only by a de-mineralizer. Therefore, in their analysis, the staff assumed the latter made of treatment. /' The holdup time calculated by the staff for the treatment of the i regenerative solutions from the condensate polishing system (input s to secondary waste high conductivity holding tank) was calculated to be.less than 2' days. Since the secondary waste evaporator, which was intended for Units 3 and 4, is available for processing the contents of the high conductivity holding tank'if the evaporator for Units 1 and 2 becomes inoperable; no alternative treatment scheme hao to be considered in lieu of the evaporator even though less than 2' days holdup was avt.ilable for treatment of the regenerants. The staff assumed that chemical drain wastes from the chenical drain tank of Units 1 and 2 and the concentr. ate from the laundry and hot e, t [..

.,n -. shower RO unit would be sent to the R0 concentratts tank a 11.1 The applicant by the R0 concentrates evaporator' prior to discharge. did not include this source in their evaluation of effluent release All detergents wastes were considered by the staff to be collected and treated by the laundry and hot shower RO unit and then disc'harged. Airborne effluents occur from the building ventilation systems, frol ~ '

the. continuous and pre-entry containment purges, from the gaseou waste processing system (GUPS), the main condenser evacuation system, All airborne effluents except and the turbine gland steam condenser.

those released from the turbine gland steam condenser, the main con- ~ denser mechanical vacuum pump, and the G'JPS are passed through a H The continuous con-filter and charcoal adsorber prior to discharge. tainment purge is filtered by a HEPA filter and charcoal adscrber in the airborne radioactivity renoval system ( ARRS) inside the containment. Additional infomation utilized by the staff in its estimate of air-Addi tional borne releases is provided in Tables 11.1-1 and 11.1-2. details on the liquid and gaseous radwaste syste.ns are contained in Sections 11.2 and 11.3 of this SER. e to process evap-The applicant is installing a fluidized bed drye + orator concentrates (bottoms), and filter sludges for' the purpose 9 9 e e O, ,,,{ @ f,, ~ * " ~ ON . 7. . s. s; ::*. -m-

l ) x 11.1 of reducing the volume of solid radwaste shipped offsite. The opera-tion of this volume reduction (VR) equipment will result in additional liquid and airborne effluants. Airborne effluents will result from ~ the VR system's offgas and will be discharged on a continuous basis while the system is operating. There are no ifquid effluents which will be discharged directly off-site from the VR equipment operation. However, based upon FSAR Figure 11.4.2-2, decantabination solutions,

condensate from the scrubbers and leakage from pumps, pipes, etc.

will result in additional quantities of wastes being treated by the floor drain treatment system. Ultimately, some of these wastes will be discharged offsite from the waste monitor tanks and scoe will again be treated in the VR system. r \\ 11.1.2 Evaluation and Findings The applicant has'~notliFesented any detail on the VR system. In particular, the applicant has not addressed (1) the volume of waste to be handled by the VR system; (2) the quantity of aircorne radio-active effluents released from the VR system; (3) the additional voluae of wastes to be treated by the liquid waste processing system as a result of operation of the VR system; and (t.) thi additional radioactive liquid effluents resulking from operation of the VR 7 system. The staff has estimated the qtiantity of wastes to be treated by the VR system and the radioactivity associated with these wastas. The ( _ t e 4 d e 5'S-.--.

o 18 [ ( 11.1.2 staff has estimated the additional amount of radiaoctivity released as airborne effluents from the VR system and as liquid effluents from the liquid radviaste system. These releases were included with the releases 15 calculated using flVREG-0017 and the total quantity of effluents was W FCS presented in Section 5 of the SHNPP Environmental Statement (ttt). Tables 11.1-1 ar.d 11.1.2 of this SER present assumptions.which were,, -<w 5 g,gy, open fim s; utilized in the calculation of effluents esulting frem YR w.gac.t. g The ap'pli antias not filed with the Co'm issiot detafis on the VR ~ sy tim design a\\ / n its interface wi various pla t systems such as prpcess and efflue t montoring, uch infomation w 11 be required i \\ prior to approval o the plant' radwaste VR system in ' Jinn to 'q tye information outlin abov. 9 9 9 N. gum m3

_ 19 ~.c (. Table 11.1-1 Principal parameters and conditions used in releases of radioactive material in liouid and gaseous effluents from Shearon Harris !!uclear Power Plant Reactor power level (MWt) 2900 Plant capacity factor 0.80, Failed fuel 0.12% Prinary systen 5 Itass of coolant (1b) 3.42 x 10 Letdown, rate ! gal / min) 60 3 Shim bleed rate (gal / day) 1.44 x 10 Leakage to secondary system (ib/ day) 100 U Leakage to containment building (ib/ day) b Leakage to auxiliary building (1b/ day) 160 Frequency of degassing for cold shutdowns (times /yr) 2 c Letdown cation demineralizer flow (gal / min) 6.0 Secondary system 7 Steam flow rate (1b/hr) 1.2 x 10 5 liass of liouid/ steam generator (ib) 1.01 x 103 liass of ster.n/ steam generator (ib), 9.00 x 1 / Secondary coolant mass (1b) 1.53 x 1 Rate of steam leakage to turbige area (1b/hr) 1.7 x 10 6 2.3 x 10 Containnent building volume (f t ) Trecuency of containment purges (times /yr) 4 i Containment 1cw volume purge rate (ft"/ein) 17g0 Containment atmosphere cleanup rate (ft<nin) 10 Pre-purge claanup time duration thr) 16 locine partition factors (gas /licuid) Leakage to auxiliary builcing 0.0075 Leakage to turbine area 1.0 liain condenser / air ejector (volatile species) 0.15 Liould radwaste system decontamination factors -i.2 q Boron Recycle Equipment Drain Secondary taste System Treatment High Conductivity ,.i Material System Sub-tvstem 10f 10l 6 Iodine 10 3

i
Cesina, 2x10 10 10 Rubidium 4

4 5 Other 10 10 10

  • This value is constant and corresponds to 0.12% of the operating power product source term a's given in 14UREG-00i7 ( April 1976).

b N) %/ day of the primary coolant noble gas inventory and 0.001%/ day of the primary coolant iodine inventory.

n h}s

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~ Table 11.1-1 (continued) Secondary Waste Low Laundry and Hot Shower Conductivi ty R.O. Concentrate Subsystem Subsystem Material 10f 2 Iodine 10 Cesium,. rubidium 2 10 2 4 Other 10 10 Liouid Maste Inouts Process Flow Rate Fraction Fraction Collection Time Stream (gal / day) of PCA Discharged time (days) (days) Shimaleea Rate (5RS) 1440 1.0 0.1 23.3 3.11 , Equipment Drains (EDTS) 250 1.0 0.1 24.4 0.46 R.O. Concentrates Wastes 838 0.002 1.0 2.23 0.17 Bl owdown 119000 0.0 0 0 Floor Drains (FDTS) 935 0.11 1.0 21.4 0.46 Regenerant Solution (SWTS) 6000 1.0 0.50 0.21-Detergent Wastes 450 1.0 6 1 Low Conductivity Holding Tank 19000 8.7x10 1.0 0.47 0.13 Source of Volume Reduction System Wastes Volume / Year / Unit 1. Evaporator Botton.s. 3 (a) Recycle Evaporator 1,025 ft3 (b) Waste Evt;;rator 960 ft 3 (c) Secondary Waste Evaporator 4,675 ft3 (d) RC Concencrate 876 ft 2. Filter Sludge ft Gaseous Maste Inputs There is continuous low volume purge of volume control tank Holdup. time for xenon (days) 70 Holdup time for Krypton (days) 70 Fill time of decay tanks (days) 35 9 t 1 em fM' t 4

, _f-- Table 11.1-2 Individuci Ecuipment Decontamination Factors All nuclides except iodine Iodine 1. Evaporators 10f Secondary Waste and Waste 103 Recycle 10 10 ~ ~ U

Cesium, Other Anions Rubidium

?!uclides 2. 03 min N.11zers Secondary Maste, tiixed Bed 10 2 i 10 CYCS Laundry Reverse Osmosis 1 10 10 Package and L'aste lionitor Tank, / Catior Bed i Recycit. Evaporator Feed, tiixed Bed 10 2 10 ' 2 Recycle Evapora*ar Condensate, 10 1 1 Anion Bed Decontacination Factors Iodine Others 3. Volune Reduction Eo,uipment Fluidized Bed Dryer and Gas / Solids 2 100 Separator Scrubber /Preconcentrator 3 100 HEPA Filter 1 100 Charccal Adsorber 100 1 y/.4 Tr uss,m BJidev$ F. \\ 4'< p. leo M *dt+ 4 All IJuclides 4. Reverse Osmosis Units Laundry and Hot Shower 30 /

~ 22 - 11.2 Liquid Radwaste System 11.2.1 Summary Decription The liquid waste processing system (LWPSI at the SH!:PP consists of process equipment and instrumentation necessary to collect, process, monitor, and recycle and/or discharge radioactive liquid wastes. The LWPS is designed to collect and process wastes based on the origin of the waste in the plant and the expected levels of radioactivity. - All'1fquid waste is processed on a batch basis to permit optimum f control of releases. Before liquid waste is released, sanples are analyzed to determine the types and amounts of radioactivity present. e Based on the results of the analysis and the waste treatment system ( utilized, the waste may be recycled for eventual reuse in the pla~nt, retained for further processing, or released to the environment under con ' rolled conditions. A radiation monitor in the discharge line from the various discharge tanks will automatically terminate liquid waste discharges if radiation measurements exceed a predetermined level. An alarm will bc simultaneously actuated in Units 1 and 2's control room, in the WPB control room and the Health Physics control room. The LMPS at the SHUPP is comprsed of the following subsystems: (1) the equipment drain trestment; (2) the floor drain treatment; (3) the laundry and het shower treatment; and (,, (4) the secondary wasta treatment. e m -m

..I 11.2.1 The SHl:PP's has been designed so that liquid wastes from the reactor coolant and its associated subsystems are separated into three main streams - recyclable reactor grade, nonrecyclable, and secondary waste. The recyclable reactor grade stream consists of tritiated wastes collected in the equipment drains. This strean is treated by the equipment drain treatment subsystem. The nonrecyclable equipment stream consists of nonreactor grade water sources and is collected and pr.ocessed through either the floor drain treatment subsystem or the laundry and hot shower treatment subsystem. The secondary waste l l stream con,ists of regenerant solutions from ~the condensate polishing I l system and backflush from the electrcmagnetic filters of the steam (.- generator blowdown system and is collected and processed in the secondary waste treatment subsystem. ~ The above systems are shared vwincan as t.n u...it; at the SHl:PP. There are two floor drain treatment subsystems and two secondary waste treatment subsystens shared between the t<to units. All other shared systens are single subsystems. All releases are monitored before discharge to the cooling tower blowdown. The discharge valve is interlocked with a process r'adiation monitor and will close automatically if the radioactivity in the liquid should exceed a predetermined limit or if the ' dilution flow afforded by the cooling tower blowdown falls below a preset value. Additichal details on the liquid radwaste treatment system follow. ) 9 4

n . L. n 11.2.1 The equipment drain treatnent subsystem collects reactor grade water fron eouipment leaks and drains, valve leakoffs, pump seal leakoffs, tritiated water sources and tank overflows. These wastes are collected in the waste holdup tank and then processed via filtratio,n - and evaporation. After processing, these wastes are either sent to the reactor makeup water storage ttnks or to the waste monitor tank for discharge or to the waste holdup tank for additional treatment. 1 - The floor drain treatment subsystem collects and processes water frcm the floor drains of the reactor auxiliary building (RAB), fuel handling. building (FHB), waste processing building (WPB), tank areas (reactor makeup, water storage and condensate storage tanks) and portions of -[ i ~ the hot shop. - The waste is collected in the floor drain tank and n~. p processed by filtration and treatment in the floor drain treatment subsystem reverse osmosis (RO) unit and then collected n the waste monitor tanks. From the waste monitor tanks, the wastes may be dis-charged to the cooling tower blowdown line, pumped to the condensate storage tank, recycled to the waste holdup tank for treatment in the c equipment drain treatment subsystem, or pumped directly to the waste ' processing system (WPS) waste evaporator for treatment. The latter route will be utilized when radioactivity levels are such that filtration and reverse osmosis are insufficient to reduce the radioactivity to acceptable levels. 'h t '* ^

~ ~~~~ . g ~. The laundry and hot shower treatment subsystem collects, in the laundry 11.2.1 hot shower tank, detergent waste from the k'PB, the FHB and the hot shop. The applicant expects this waste to be of a quality such that treatment

However, for removal of radioactivity will not noma'ily be required.

if analysis indicates that treatment is required it will be routed to the laundry and hot shower RO unit. The permeate from the RO unit will and then routed to the treated laundry be passed through a demineralizer The contents of this tank can be recycled for -and hot shower tank. ~~ ~ ~ f urther treatment or discharged via cooling to'wer blowdown or pumped to the condensate storage tank. The secondary waste treatment subsystem is designed to treat wastes This water will contain radio-( generated from secondary systems. activity only if primary to secondary leakage occurs in,the steam The secondary waste treatment subsystem consists of one generators. subsystem to treat high conductivity wastes and one to treat low conductivity wastes. Low conductivity wastes such as the backflush from the' electromagnet'c filters of the steam generator blowdown system and the low conductivity wastes from the condensate polishing system are collected in the low conductivity holding tanks. These wastes are filtered and passed through a demineralizer and then collected in the secondary waste From the secondary waste sample tanks the water is sample tanks. o s ?, w N-sl L: -. -.. ~ _.....

.,-~ 11 2.1 either recycled to the condensate storaje tank, discharged to the cooling tower blowdown or to the neutralization basin or recycled back to the low conductivity holding tanks. The main source of high conductivity wastes is the regenerant solutions from the condensate polishing system. This waste is collected in the high conductivity holding tank, processed by an evaporator and the evap' orator distillate discharged to the low ^ ~ ~ clo'nductivity system upstream of the demineralizer. From the demineralizer, treatment is the same as for the low conductivity subsystem. Turbine building equipment drains and curbed area oil equ'ipment and { floor drains below the operating ceck are collected in the industrial waste sumps of the turbine building. Drains below ground elevation are collected in a condensate pump area sump. This sump and the in-dustrial waste sumps discharge through a radiation monitor. The contents of these sumps will normally go to a yard oil separator and then to the cooling tower blowdown. If the monitor detects high radiation in the discharge from one of these pumps, the discharge will be directed to the low conductivity holding tank for treatment. The secondary waste subsystem also collects 1) 'the waster from the chemical drain tank which are not sent to the solid waste processing system for solidification, and 2) the concentrated wastes from the i s.

( i, _ 27 waste evaporator, the reversa osmosis units, and the seconcary waste 11.2.1 These wastes are collected in the R0 concentrate tank ard evaporator. The distillate from are processed in the RO concentrate evaporator. this evaporator goes to the treated laundry and hot shower storage tank for discharge. The evaporator concentrate goes to the waste evaporatdr concentmte tank for solidification or for treatment in the volume reduction system. The liquid waste system consists of a number of cross-ties which allows alternative treatment schemes to those discussed above. Further detail on the liquid waste system and these treatment schemes is provided in Section 11.2 of the SHUPP FSAR. ~ 11.2.2 Evaluation and Findings (' -ed with respect to the ' Acceptance Criteria '~ The LWPS system was r: ~ ~ ~ ~ of Standard-Review Plen 11.2, NUREG-0800. The staff's r'evies con-sidered the capability of the proposed LWPS to meet the anticipated demands of the plant due to anticipated operational occurrences. The potential consequences resulting from reactor operation have also ^ been considered and the staff has detennint4 the concentrations of radioactive materials in liquid effluents in unrestricted areas to be a small fraction of the limits in Table II, Column 2 of Appendix B to 10 CFR Part 20. a. e b .f .iiN 3

7.

28 - p. q... 11.2.2 The staff has also considered the potential consequences resulting. from reactor operation wiih 17. of the operating fission product in-ventory in the core being released to the primary coolant and has determined that the concentrations of radioactive materials in liquid 1 effluents in unrestric ced' areas will be a small fract' ion of the limits of Table 2, Column 2 of Appendix B to 10 CFR Part 20. As discussed in Section 11.1 of this SER, the.eteff calculated liquid effluents using thz GALE computer program based upon the treatment systems for liquid effluents described above. These source terms were presented in, Appendix D of the SHNPP DES. The staff calculated the doses to offsite individuals utilizing the methodology of Regulatory Guide 1.109 and the liquid dispersion parameters calculated in accordance with Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents fr ct Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I". The staff has deterriined that the proposed liquid radwaste~ treatment systems are capable of maintaining releases of racioactive materials i in liquid etfluents such that the calculated individual doses in an unrestricted area from all pathways of exposure are less than 3.orem to the ' total body and 10 mrem to any organ. l The staff has calculated, as noted in Section 11.1, The release of radioactive materials in liquid effluents exclusive of tritium and ~ noble gases and has found it to'be less than 5 Ci/yr per reactor ~ O in i um _..O

o i 29 -

B_,,

11.2.2 and the annual dose to any organ of an individual in an unrestricted area to be less than 5 millirem per year total from both reactors. Therefore, in accordance with the option to Section II.D of Appendix I as provided in the Annex to Appendix I of 10 CFR Part 50, the staff finds that the liquid radwaste system is capable of reducing liquid radioactive effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a, Appendix I to 10 CFR Part 50, - and the Annex to Appendix 1. The SHMPP DES presents a' comparison of the PJi 30-2 and Appendix I design objective doses with the doses calculated for the liquid e source tems and a comparison of the R!i 50-2 curie limitation with the projected releases for the SHNPP. The design of th_e liquid radwaste system presented in the FSAR is different from that which was proposed at the Construction Pemit (CP) stage. At the CP stage the steca generator blowdown liquid was to be discharged. Although no process treatment system was proposed, the applicant made a commitment to install equipment capable cf re-ducing the level of activity in the blowdown stream by a factor of 3000 or greater. The applicant has since decided to install an electromagnetic fiiter to remove magnetite and other spinel type oxides which are magnetic and to remove a portion of the nonmagnetic ~ particulates. The filter is flush'ed and the water is collected in the settling tank. The flush water is then pumped to the secondary ) i 1 1

u 30 - ~; ~. I; The steam generator blowdown s_, waste low conductivity holding tank's. 11.2.2 The con-passes from the electromagnetic filter ^o the condenser. densate polishing system provides some removal capability fo radionuclides. t s The staff has assessed the overall capability of the radwast failure by to process waste in the event of a single major equipment and a comparison.of the design flows to the potential process rout i Based upon this review, the staff has detemined ~ equipment capacities. ts that the radwaste system will be adequate to process was e. liquid rad-The staff has considered the capabilities of the proposed, f the plant due waste treatment system to, meet the anticipated demands o p'* p-l d d that the to antir.ipated operational oc.currences and have cenc u e ti-system capacity and design flexibility are adequate to m cipated needs of the plant. i i ns The staff has reviewed the applicant's quality assurance prov i se- [ ,l, for the li'. id radwaste systems, the quality group classifica for system components, and the seismic design applied to y The design of the systems and str +.ures housi hotrsing these systems. Guide 1.14: lt these systems meet the criteria as set forth in Regu a ory ,7, e

  1. ^

S -ey a .~ CQL +,

  • 3,# sd swa

-p;;, ~~l~ hut.G;t._ d,, me.-.w 1----___ ~ _ _ _ _ _ _ _ _

i I ine staff has rev'. sed the provisions incorporated in the applicant's 11.2.2 design to control the release of radioactive materials in liquids due to inadvertent tank overflows and conclude that the measures proposed by the applicant are consistent with the criteria as set forth in s Regulatory Guide 1.143. Note A noted i Sections 11.1 and 11.4 of this SER, appi cant has J.ot provided ufficient detail on the VR syst to allow e staff to assess the c tability of the liquid radw te system to ocess the additional li uid waste generated by e VR system or t effluents resulting from this processing Until such'infoma iea 7 is presented, the SHN cannot be judg as to its compliance 'th Appendix 1. This sectio of the SER as been drafted assuming tha the plant will meet Appendix p 1 4 S o O G =# M 23 .m - -.-r ._s.+.w. =

I ~ f-y Table 11.2-1 Desig, parameters of principai components considered in the calculacion of liquid effluents from SHNPP, Units 1&2 Capaci ty Safety Component Number (each) Class Boron Recycle System 3 Recycle Evaporator F.--d Demineralizer 2 30 ft 3 Recycle Evaporator Feed Filter 2 150 gpm 3 Recycle Holdup Tank 2 84,000 gal 3 ._ Recyc.le Evapo.rator Feed Pump 2 30 gpm 3 Recycle Package 2 15 gpm 3 & HMS Recycle Evaporator Concentrate Filter 2 35 gpm N!!S Recycle Evaporator Condensate Demineralizer 2 20 ft3 Recycle Evaporator Condensste Filter 2' 35 gpm - Recycle Monitor Tank 2 10,800 gal Recycle Monitor Tank Pump 2 30 gpm Eouipment Drain Treatment System 2 350 gal ( Reactor Coolant Drain Tank Reactor Coolant Drain Tank Pump 4 100 gpm Reactor Coolant Drain Tank Pump Heat Exchanger 2 Waste Holdup Tank s 1 25,000 gal Wahe Evaporawrhu Fump 1 35 gpm Waste Evaporator Feed Filter 1 35 gpm Waste Evaporator Package 2 15 gpm Waste Evaporator Concensate Demineralizer 1 35 gpm Waste Evaporator Condensate Tank Filter 1 35 gpn Weste Evaporator' Condensate Tank 2 10,000 gal Waste Evaporator Cmdensate Tank Pump 2 35 gpm Waste Evaporator C acentrate Tank 1 5,000 gal Waste Evap:rator Concentrate Tank Pump 2 35 gpm Moor Drain Treatment System Floor Drain Tank 4 25,000 gal Floor Drain Tank Pump 4 35 gpm Floor Drain Tank Filter 4 35 gpm Floor Drain Reverse Osmosis Unit '2 30 gpm ~, F.loor Drain Reverse Osmosis Feed Pump 2 30 gpm 'r;aste Monitor Tanks 2 25,0g0 gal ~ Waste Monitor Tanks Demineralizer 1 50 ft (30gpm) Waste Monitor Tanks Pump Chemical Drain Tank 2 35 gpm 2 600 gal Chemical Drain Tank Pump 2' 35 gpm V S l ~-

' M'*.~: I . ~ ~- .;..s.: Table 11.2-1 %i. < (Continued) i i 2 25,000 gal Laundry and Hot Shower Treatment System 2 35 gpm ~ Laundry and Hot Snower Tank 2 35 gpm Laundry and Hot Shower Tank Pump 1 30 gpm Laundry and Hot Shower Tank Filter Laundry and Hot Shower Reverse Osmosis UnitLaundr 50 f t{- (30gpm) 1-0 gpu 1 2 25,000 gal Laundry and Hot Shower Demineralizer 2 100 gpm Treated Laundry and Hot Shower Tank Tank Pump 2 5,000' gal . Treatad Laundry and Hot Shower 2 35 gpn Reverse Osmosis Concentrate TankReverse Osmosis Conce " ~ 2 10 gpm ^ 2 20 gpm Reverse Osmosis Concentrate Package Reverse Osmosis Concentrate Evaporator Distillate Pump 3 15,000 gal Secondary Waste Treatment System 2 100 gpm l ^ Low conductivity Holding Tank' 2 100gpg c.1 d Low Conductivity Holding Tank Pump F~ 2 70 ft 'h Secondary Waste Filter 1 25,000 gal i G* k~ Secondary Waste Demineralizer 2 100 gpa Secondary Waste Sample Tank ?;. i 15,000 gal . Secondary Waste Sample Tank Pump 2 35 gpm High Conductivity Holding Tank 2 15 gpm High Conductivity Holding Tank Pump 2 4,000 gal Secondary Waste Evaporator Package Secondary Waste Evaporator Concentrate TankSeco 2 35 gpm .e.14 .2l;Q y'4;. i, 3??$N", .su $.c$c.5N 1 ,3

  • it.

,T '1h# sen iTd'?'- jr.?;1 s*. '.; J. p *. "} ~ gige. '. '? Ha uPsi 4 ~~',[',7 =-.%.- ~ .-r*b w ? .4 z____ r- __ _

.r. w.-__ 34 - n. (: Gaseous Maste Management System 11.3 f 11.3.1 Summary Odscription The gaseous waste management systems at the SHNPP' include systems which treat the nomal ventilation exhausts; the exhaust from the main condenser mechanical ' vacuum pumps, and the gaseous wastes associated with degassing primary coolant, purging the volume con d tank, displacir.g cover gases, purging of equipment, gas sampling an ~

4nal-ysis operations, and boron recycle process operations.

Table 11.2-1 provides a listing of the various normal ventilation systems at the SHNPP and the type of treatment associated wit Additional details are provided in Section 9.4 of the FSAR. s system. if a generalization can be made of the normal ventilation exhaust .h treatment systems at the SHNPP, it is that the exhausts usually flow w through a medium efficiency filter, a HEPA filter, and a charcoal adsorber. The RAB normal ventilation system (RABMVS) filters air from the con- [. i tinuous can':.inment pijrge exhaust and areas from the RAB which con .1 'i equipment essential for the safe shutdown of the reactors includin j; CVCS chiller area, 480 V auxiliary bus area, areas containing non- )S This system exhausts to the vent stack on J +;. essential equipment etc. the roof of the RAB. e .h 6 a 49 _jn w) 2$$ yg% ~'~~~ ~~ ps.'g. ______- _.. w._ g a ~ ' ~ - = - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

~; +'i 35 - &'l y:;,.. The waste processing areas filtered exhaust system exhausts air from

,$l u

. ~. 11.3.1 the contaminated areas of the WPB and discharges to a vent stack on k The WPB laboratory areas fume hood exhausts are i Ij the roof of the WPB. This exhaust is 3 filtered except for the perchloric acid exhaust. ' ~ ' discharged unfiltered to the vent stack on the roof of the WPB. i The air from the contaminated spaces of the condensate polishing .demineralizer area is ex'hausted thrcugh the condensate polishing ~ The exhaust is dis-demineralizer area filtered exhaust system. charged from the vent stack located on each unit's turbine building. V The condenser vacuum pump effluent treatment system was previously E't I discussed in Section 10.4.2 of the SER.

q.

The containment pre-entry purge is filtered by the containment pre-entry purge system. The purge is discharged to the RAB vens swa. Additional details of the normal ventilation systees are provided in Section 9.4 of the FSAR. ~, '. NR-The gaseous waste processing system (GWPS) processes gases ? ;. k'( P. : ', ' from the volume control tank and vent connections frca the recycle [',,,:....% evaporator gas stripper, the reactor coolant drain tank, the dOPI : pressurizer relief tank and the recycle holdup tanks., The GWPS

.q ; :

shared between the two units and consists of two waste gas compresse ,e l' e n kh! m e$, X.-@#o. 9 -- - -_- _________ _ m _-.c-w... n u,, u,..

,y u a. -J o 4 36 - two catalytic hydrogen recombiners and ten waste gas decay tanks to 11.3.1 accumulate tr.e fission product gases. Eight gas decay tanks are used during norm?1 operation and two are used for shutdown and startup. Hitrogen with entrained fission gases will be continuously circulated Fresh around the GWPS by one of the trio waste gas compressors. hydrogen gas is charged to the volume control tank where it is mixed .. with fission gases which have been stripped from the reactor coolant The contaminated hydrogen into the volume control tank gas space. gas is continuously vented frca the volume contral tank into the circulating nitrogen stream to transport the fission gases into the GWps. The hydrogen-nitrogen mixture of fission gases is pumped by the waste gas compressor to the hydrogen recotabiner where the re-I 's After combiner converts the hydrogen to a water vapor by exidation. n removal of the vapor the resulting gas stream is circulated to a Each gas waste gas decay tank and then back to the compressor. decay tank is valved into the GWPS recir culation loop for one or ~ two days. Y:

^

Continued plant operation results in the buildup of pressure in the ' o7; waste gas decay tank due to the accumlation of non-removable fission 7:.. 4

y' :

When the pressura in the gas decay tanks reac es 25 psig the gases. alignment of the GUPS must be changed due to the. design of the e 5;ni i.. M.ibil \\- ' e.. s - i. 4 M k% _ _ m__.

f -c~. {.:. ~ w 11.3.1 recombiner. The new alignn, ow from the compressor to the gas decay tanks to' the recunbtner and then back to the compres3or. This alignment'is suitable for operation up to 100 psig. The GWPS has an'alyzers to monitor oxygen concentrations between the oxygen supply and the hydrogen recombiner pact: age and downstream of the recombiner. Hydrogen analyzers are located in the process ~ stream entering the recombiner and in the discharge stream from the recombiner. The applicant has indicated that the normal ventilation system com-plies with the criteria of Regulatory Guide 1.140 and that the GWPS confoms to the criteria of Regulatory Guide 1.143. ~ I,.s s 11.3.2 Evaluation Findings The gaseous waste management system was reviewed with respect to the Acceptance Criteria of SRP 11.3, IWREG-0800. At the construction pennit st' age the off-gas from the condenser air ejectors was untreated and the ventilations systems were only filtered by HEPA filters except for the exhaust from the WPB, which was also filtered by a charcoal adsorber. The st.aff stated in the December 22, 1972 SER for the CP that treatment of the main condenser .. r of f-gas would be required to reduce this potential source of iodine-131 to the atmosphere to bring ~the offsite doses into compliance with f / t;- .N,. .=

rJ

, P

f..
f. ' ',

Q. The applicant has added the condenser effluent treatment e 11.3.2 Appendix I. system, which can be utilized during conditions of high radioactivity from the mechanical vacuum pumps, and has added charcoal adsorbers to

  • ?.

the various ventilation systems which exhaust air from contaiminated These adoitions decrease the quant'ity of iodine released from areas. the SHNPP and aro therefore acceptable when judged against the design However, it should objective doses of Appendix I to 10 CFR Part 50. be noted that the staff did not credit the plant with removal of the condenser effluent because the condenser effluent treatment system wi' notbeu*gizedonaroutinebasis. t The staff has. calculated the doses to offsite individuals utilizing atmospheric dis-the methodology of Regulatory Guide 1.109 and " 3 'r julatory persion parameters calculated in accordance wit-Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-The staff has determined that the proposed gaseou ~ Cooled Reactors". ~ ^ ~ .,:lt radwaste t".atment systems are capable of maintaining releeies of 'U,.- ". radioactive materials in gaseous effluents such that the calculated C 7.S :d ind.ividual doses in an unrestricted area from all pathways of expo-

sNJ4

.& 1 sure are less than 5 mrem to the total body and 15 mrem to any orgar F." ' _ ", from noble gases and that releases of radioiodine and radioactive material in particulate f.onn result in doses which are less than ~ 15 mrem to any organ. ~ s:

L f l-- 11.3.2 The staff has also considered the potential effectiveness of aug-menting the proposed gaseous radwaste treatment systems using items of reasonably demonstrated technology. The applicant has chosen to show compliance with Section 11.0 of Appendix I to 10 CFR Part 50 by complying with the Annex to Appendix I (PJi 50-2). The SHNPP DES presents a comparison of the doses and releases calculated for the ^ SHHPP with the design objectives of Appendix I and PJ4 50-2. The ypplitant's proposed design complies with the design objectives of Pfi 50-2. Therefore, we have detennined that no further effluent treatment equipment will reduce the cumulative population doses within a 50 mile radius in a cost effective manner. The staff has also considered the, potential consequences resulting from reactor oparation with 1". of the operating fission, product inventory in the core being released to the primary coolant and has detennined that the concentrations of radioactive materials in gaseous effluents in unrestricted areas will be a small fraction of the limits of Table 2, Column 1 of 10 CFR Part 2O'. The capability of the proposed gaseous radwaste treatment systems to meet the anticipated demands of the plant due to operational occur-rences was also considered and it was concluded that the system capacity and design flexibility is adequate to meet-the anticipated .needs of the station. i Q9 .A j 3 N d d j ..--.___._..2_.

,~

5

'z; - i.' f ~ * ^ The applicant's quality assurance provisions for the gaseous radwast 11.3.2 systems, the quality group classifications used for system component 5-the seismic de' sign applied to the system and the structures huusing the' radwaste systems were also reviewed. The design of the systems and the structures housing these systems meet the criteria set forti in Regulatory Guide 1.143 as indicated by the applicant in the FSAR. However, the plant does not contain a gas analyzer between the com-I i y..- pre'ssors and the gas decay tanks. Such an analyzer is required in accordance with the Acceptance Criteria

  • of SRP 11.3. Dcal analyzer:

are required. The staff has reviewed the nomal ventilation system's design, test and maintenance of the HEPA filters and charcoal adsorbers, with respect to Regulatory Guide 1.140. The applicant has indicated in Chapter.1 of the FSAR, that the nomal ventilation system meets the criteria of this guide.

.: C w.

,- m ereareruptuediksin .l, I The/applic-h has not indicated hether .;;a x. / PS itself an if there are iquid seals anstream o the ru turt 6.r an ex osion will N ~ discs, and whet er they are designed such tha /

  • P.~

$7 cause the pemanent oss'of the seals. ,v ~.. .: ; e.. The above information is required, along with a,canmitment to inst dual analyzers, before the GWPS can be judged to be acceptable. / ,, ' -} e,.

  • [

s hk $?:El:? si.e.on < ?rr. r.:t I W Wd _ _-_ _ _ _- ~_c?? - ~?" = ~;- -;-~ ~ --

V 41 - ~ ~ ** ~. Note As noted in Sections 11.1 and 11.4 of this SER, the applic nt has n staff to provided sufficient detail on the VR system to allow th detemine the effluents which s.will result from the ope ation of the .l Hi!PP cannot Until such informabion is presented, the VR s stem' th Appendix I. Th s.section of the e be udged as to its compliance SEi has been drafted assuming that the infomation to be provided ~ i \\ 1-ed in thi ection that the ~ ~ ' pi ll not negate the conclusion expre c, lNPP will meet the design objectives of Appendrx I. Si

f Solid Waste Management Systems l

11.4 (j E 11.4.'1

System Description

The solid' waste processing system (SWPS) is designed to process U -[ " wet" solid wastes and '" dry" solid ,.3 general types of solid wastes: Met solid wastes. consist mainly of spent filter cartridges, .. ee wastes. $.j demineralizer resins, filter sludges, chemical drain solutions an <c Nd bl9 evaporator bottoms which contain radioactive materials recov Dry solid wastes c'orisist mainly liquid streams during processing. 8W of ventilation air filtering media (HEPA, charcoal), contaminated ia clothing, paper, rags, laboratory glassware, and tools. c The spent filters associated with the various ventilation sy be removed from the filter housing, wrapped, and package @Di it&s.s The filter sludges from the liquid rad-

m. ;

using a hydraulic ccmpactor. N.0 i ^

  • e n.

w :# -~ '963 t i.2.. ',, -'Neo y g W[ M g g

...; r ~, _ _ - _ _ _ _ _ I- ^ ~ ~.. Nomal ventilation system components at the E. ,;T. Table 11.3-1 Shearon Harris Nuclear Power Plant ~ ~. Medium Demister Heater Filter HEPA Charcoal HEPA_ X X' X RAB Normal Ventilation System X X X WP Areas Filtered Exhaust System X X WPG 1.aboratory Fume Hood .c _ ~ ^ Exhaust (except grchlorite) ^ X X X Condensate Folishing Demineral-izer Area Filtered Exhaust System X X X X X X Condenser Vacuum Effluent Treatment System

  • X X

X Continuous Containment Purge ., c.

.. j

( (Passes through RAB Nomal Ventilation System and Air-borne Radioactivity Removal System) X X X Containment Pre-entry Purge System , '~ fr f. ' .o -l ?- '. y~;.,.;^' 7~,., Credit was

  • System will not be used to filter releases on a routiune-basis.

given in the Appendix I evaluation. N, g g Yhh'$b ^ 6 % ; w A ;+; OD5Id3h DMIf1 s b Bn ~~~-:. _ x.x. c ___-_____.____=____-_________:-_--

r. f.,3 - 11.4.1 waste systems will be backwashed to a WPB filter backwash storage tank and to the WPB particulate concentrate tank. These sludges may then be solidified or sent to the volume reduction system. Spent resins will be dewatered and then solidified by cement. In lieu ~ f solidification, the resins may be shipped dewatered in high integrity o containers. Evaporator bottoms will be processed in the volume reduc-tion system. Che'mical drain solutions will be solidified. Compressible low-activity solid waste will be compacted in 55-gallon drums. The compactor is aquipped with a hood, ventilation fan and HEPA filter. The displaced air will be vented through the HEPA filter. The applicent has indicated that the SWPS has a storage area capable of storing 1020 drums. The applicant has also indicated yhat the SWPS meets the criteria of ETSB 11-1 Rev. I which is the equivalent to Regulatory Guide 1.143. The :pp1'icant has committed that all radioactive waste will be pack-aged in accordance with appropriate federal and state standards for burial in accordance with 49 CFR 170-179,10 CFR 20, and 10 CFR71. All drums will be shipped and buried in accordance with 49 CFR 173. Additional infomation, with respect to the solid radwaste system, is 7 contained in Section 1!.4 of the FSAR. G e ____.__._________________.____m___

j s 11.4.2 Evaluation and findings The staff has reytewed the SWPS in accordance with the acceptance criteria of SRP 11.4, HUREG-0806. The scope of the' review included line diagrams of the system, piping and instrumentation diagrams (P& ids), and descriptive infomation for the SWPS and for those auxiliary supporting systems that are essential to the operation of the SWPS. The applicant's proposed design criteria and design bases for the SWPS, and the applicant's analysis of those criteria and bases have also been reviewed. The capability of the proposed system to process the types and volumes of wastes expected during nomal operation and anticipated operational occurrences in accord-ance with General Design Criterion 60, and provisions for the handling (s j. of wastes relative to the requirements of 10 CFR Parts 20 and 71 and applicaole DOT regulations have also been reviewed. The staff will not approve the design of the solid radwaste system until the applicant provides infomation detailing the manner in which various waste components are treated. Infomation which is missing includes' (1) a de ailed descri ' ion of the volume reduction . v] -h hde N l system which addresses; \\ 4af (a) how the s atem operate 2; (b) expect input stream their volumes, and asjociated ac vi ties; (c) iquid and gase s effluents resulting from system operation; ('i, - u> i O g

t o [_, 45 - 4._. / 11.4.2 (d) volume reducti factors achi ed; (e) activity sociated wi th he c .aole ash; and (f) confo.ance with Regulatorf Guides 8.8,. 1.140, and 1.143, t/ and BTP CMEB 9.5,1 of SRP 9.5.1; '2 ) a rawing (CAR 5-G-8 ) which e,gh ce header h> " id 1)g'4 ){'f 5 and e was e concentrate i If p-the ]) Y f( mitment to r prtsrah whereby the prese e of {ee water, i [ \\ .V. was contain is verifi and commf+..ent to repro'ressi the [ contain nen free water is cred; JP ,i4) 'a description of the by n'.t symm; [L }) (5) details on the manner in which the filter sludge from t N~ following filters will be handled: f, y (a) reactor coolant; N1 r (b) seal water ir.jscticr.; ' M (c) seal water return; (d) boric acid; IN (e) BRS recycle evaporator feed; g-(f) BRS recycle evaporator con $'entrate; PS pj(g)- -seepadsey g(h) recycle evaporator condensate; 7(i), ' fuel _ pool _f.emineca142er1 '( )90% po01 drEIN1'lts.ptM.f.ica.tdrtng and (N) ' fuel poo1TmmerrTnd y U / S.,.) e j I!!' h.* J

pn,. p.r.. -.~ l (% details showing that, the vent exhaust from the spent res n i d by a HEPA s 11.4.2 (6) storage tanks and the decanting tanks are filtere filter in accorda'n.e with BTP ETSB 11-3 of SR the concentrates The applicant has indicated that heat tracing from k is not requir line of the recycle evaporator to the boric acid tan t crysta11ize at because the 4% weight beric acid solutfon will no is required before pabient temperatures and that a 12% weight solution The staff's position is that a 4% by crystallization will occur. llize at 56-57 F. Therefore, weight solution of boric acid will crysta t s line of the heat tracing should be included from the cor. centra e recycle evaporator to the boric acid tank. ll be considered Until the above infomation is provided.the SWPS wi unacceptable. ara (PCP). The applicant has no: provided the Process Control Progr h issuance of the The PCP is not required until 6 nonths prior to t e y The PCP will be judged as to its acceptability Cperating License. (%j ~ q,9 ~. when it is submitteo. .>.l d Sampling Systems ', ;; :.] Process and Effluent Radiological Monitoring an o 11.5 i z. Summary Description d sampling .f ~ 11.5.1 The process and efiluent radiological monitoring an -e ing radioactivity systens are desigreed to provide infomation concern f ' * * ' . SD ' \\ {l..

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i 47 - C-4..- \\.... - 11.5.1 levels in systems throughout the plant, indicate radioactive leakage between systems, monitor equipment and perfomance, and monitor and control radicactivity levels in plant discharges to the environs. At the SHNPP, the airborne ef fluent sampling and monitoring systems .are located in the plant vents located on the RAB and the WPB. For liquid effluents, the effluent monitor locations are downstream of the pumps of the LMPS waste monitor tanks, the treated laundry and hot ~ shower tanks, and the secondary waste sample tanks. Ef fluent ~ ~ monitors are also located to monitor the industrial waste sumps of the turbine buildings, the discharge from the tank area drafn transfer pumps and the service water system. /. n. Table 11.5-1 contains a listing of both the process and effluent monitors for airborne and liquid sources. This Table also includes the type of radioactivity monitored for airborne effluents, the type of monitor used, and the plant specific number of the monitor for ease of reference. Sections 11.5 and 12.3.4 of the FSAR present' a detailed discussion of the process and effluent l'.onitoring system. 11.5.2 Evaluation and Findings The staff has reviewed the process and effluent nonitoring system with respect to the Acceptance Criteria of SRP 11.5, HUREG-0800. As a result of this review, the following evaluation and findings have been made. 's 6 f .___.____.___________.E__._._.__.________.___________

~ . 4,..- 11.5.2 Acceptance Criteria II.C.1.a of SRP I'.5 states that the gaseous 1 and liquid process streams and effluent release points should be monitored and sampled according to Tables 1 and 2 of SRP 11.5. Infomation provided in Section 11.5 of the FSAR indicated that the SHNPP did not meet these criteria in the following' areas: (1) The turbine gland seal condenser exhaust and the mechanical vacuum pump exhaust are not monitored and sampled in accord-ance with Table 1. (2) The conderser vacuum pump effluer.t is not sampled in accord-ance with Table 1. (3) There is no effluent monitor for the turbine building vents (release paints 3A and 38) as required by Table 1 and' sampling i',.. provisicns are not provided. (4) The ap ican has provided contradic ry in)gmation on the cont nment pr -entry purge and th continuou containment q,.?l\\; l p ige monitorin features of the HHPP. The s af f's positi n 'q,,.tu \\ /. that both linet shall be no tored on a conti aus ba s and \\ e V that bc-5 monitors 011, o high radiation signal, isolate curge operation in an automatic fashion. (, he servi wa r syste, does not pos ss th capab is to ob ain continuo ample as re red by Tabi gg, j,,li l The applicant has indicated, in response to a staff question, that the process and effluent monitoring program will meet the guidelines of i 1

~ ~ s (Lu - Yy &$ h ~ ~ b 11.5.2 Position C of Regulatory Guide 4.15,with one e eption. This e ep-tion is that e SHNPP will ke use of "n ionally recogni d stand-ards" and 11 not limi .hemselves to SS traceable s dards only. It is e staff's po tion that any nationally re gnized standard" wil be NBS trac ble. Therefo , the staff d, s not accept this pro-osed deviat n to Position of RegulatoryMuide 4.15. r The applicant has not addressed the capability of the process and effluent monitoring program to meet the guidelines of Position C and Table 2 of Regulatory Guide 1.97. pplicant has addressed items II.F.1, d Attachments 1 and 2 of HUREG-0737 which covers similar criteria o effluent monitors to that proposed by Regulatory uide 1.97.s %'owever, M [. t cant'has addr e uch of t nf required by .F.1', A tach. ts 1 and 2. The applicant h not add ssed the i fo i wing items f Attachment 1: '~ / (a) monitoring location or points of ampli ng; (tI) instrumentation r main ste safety and pressure relief valve E /T3 7f/ O (d des on d M %ach and ~ 14WofPrftmrWM (e) ca pact e sed: y mahiya,,o,nem- [ b"N 'T Yb f l

w -% .s ~. b f40% N-SW ~ N Ow:e..LL. /Lc Nu gt tsclu.u.pe~G k~tJi' 'L. a i ms A /w-c L ur&--. ' .s A.l,a:.c ,.-u ~ 3 a u n n f u. ' a A w. d % 4 ~f'0*~ u),u.ecc:~ &.~f.,n ~ s..., e a.C-..e-yax an ,, a.(s~ a.~ k m, se e w a n ~-L~ L i p a ~ p a. s s.-( ~ ~GlL., a.~t

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' " p~ L p l.L u c s y s u W ra M G, = %. L%~. ~ pp ny _.a.~ u e & upa, se su.,,, 'pc w. _ i:Cc L,. %. <. ,ae,~.t'a.. k L:t.ywyycvc- ,p'.e.7u'aE s R&_cJf.u.,nt oucc & L./u<g,k amcy~ & det, r 1 r ,,,, s.. i A % C;L v p,u us r t ic. y:~ELGz e/ /$,*LEst.. e /ya cc,(. g v )/.t..w~-%duu.- c o c. <. A in. ua. i 6 g n. +- [ >%) .l

e ~ ~ 11.5.2 (c) capability of the on-site laboratory to analyze or measure these semples; and (d) ions for limit g occu tional dose pers ae g i analysts of sar es. ,N g giu.) The applicant can not assure representative samples from3veritnrs r-adie::tiv: p* :::: nc =: :nd t:9 centent because the capacity of the recirculation pumpi do not meet the criteria of II.2.a of SRP 11.5. b Th a pumps which do not comply are the owi ng: M 'M p( O tt (a waste holdup tank; {p (D) was evaporato.ondensate tank; (c) waste mon r tanks; f - (:. V (d) rec e holduc s_ recycla monite - ank. In response to a staff question, the applicant stated that the above pumps could operate at run-out and thus meet acceptance criteria of II.2.a of SRP 11.5. It is our position that the pumps could not te operated at scie run-out condition for the period of time required to meet this acceptance criteria. Furthennore, the staff finds it ~ difficult to envision the plant operators using these pumps at the run-out condition. The applicant should propose. an alternative ~ means of ensuring tha+. th:. contents of the various liquid waste may be sampled in a repreuntative nanner. 9 D e l l

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\\ 11.5.2 Other areas of the acceptance criteria of SRP 11.5 which the applicant has not addressed or which deviate from the acceptance criteria include: (a) capability to r lace \\or decontanin onitors utilize or the pro \\ N ss system r losing 1-'- gaseous efflu nt withou openi d qp 9W. ., 6' the capabi ity to isolate the effluent stre () the divers al ves oc ted t t-1 'b . P l* - mo do not fai in the closed position; [T d'

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~ -( ~t confoman of n - ESF instru. tat n to th desig g,. . of eend 11.5-A of S as not been a ressed; aiid [' (d) incorporation of administrative controls and procedures to minimize inadvertent or accidental releases of radioactive liquids has not h been addressed, k Y\\ v 3 g. The turbine building drain monitors and the tank area drain conitors do not provide a record of effluent flow. Therefore, there appears to \\ f,9 L t'e no neans to detemine the quantity of activity released nor the g v.- S.,1,4 volume released in accordance with Regulatory Guide 1.21. It is the ,,l staff's position that the SHNPP possess the capability to detemine the quantity of effluents released from these two sources. g-The a licant h not provided sufficient 'nfoma on in the FSAR to j allsw the staff to detemine whether t releases fr the vents of (1e bor/ on recycic system are routed in s' ch a manner that a uate mo:1 toring l \\ / apd sampling of these urces is present at the SHNPP. Sucb4cfomation (J i s required. f,'k kh Jr 'y- .J _- - --- _. rz

.+ h+# (([/'/ [k Iga !b> IMAGE EVALUATION j/ $k// TEST TARGET (MT-3) ff +k\\ NNN 's NNNI 1.0 52 05 men g~u E 511 l,l [8 UlO=3 l.8 1.25 1.4 l 1.6 4 150mm 6" 4 %* / 4 / uh t+w/ s'7/// <>++%e o + d ~ ~ - - ~' 7

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%'e$ $7 I l.0 if 2 E ?c mM W'== l,l bb 1.8 1.25 1.4 l.6 l I 4 150mm 4-6" 7/ 4% / 4 bs? e+s.h $o% b - g%l'o i x.a^ W 4,, g </jt% $' M* e.

b.tk-V6 b - 52 i v Q-.. Wy ML:r 11.5.2 The ap licant has provided cont adictory infomation on the operation of -the vent valve on the WPB cooling water surge tank. Section 9.2.10.2.2 states th' t this valve loses automatically on a high radia-of the FS a tion signal from the discharge of the WPB cooling water monitor (REM-3544). he applicant's response FSAR question 460.35 stated that upon rece1 t of an alann from REM-3 4, the operator must take the action to isolat the surge tank. The man er in which the vent valve is operated should be clarified, but in eith r case the vent valve should be isolated 1 mediately because failur of "a seal in either the waste gas compres or or the catalytic recmb ner of the waste gas system could result in new and significant rele se path for effluents. O As a result of their responses to staff questions on the FSAR, the g., U applicant needs to revise various positions of the FSAR. These revisions include: p 1) igures 9.2-Van 10.1.0-6 show sam ing poin -11, \\, ' 12 b@.- Yp c of the steam g tor blowdown; an (2) able 9.3.2-2, Figure 9.3.2-2, and Section 9.3.2.2.2 to reflect d Jy A D {T p, fa,b sampling of the service water system; and Y .j.,o 6 y 3 3 ). Table .5.2-re t . o ' + ri n epi

tFnts of

-~ Y @Y h HUR G-0737, Attachments 1 and 2. ~ l The applicant has not addressed the monitoring of t e effluent frcxn l the volume reduction system. ThiI must be addressed. 48 k_._

crnw ~_ - .' 5 $ - j s. The staff's review of the process and effluent monitoring system has 11.5.2 Those items which have not been not addressed some items of SRP 11.5. addressed will be reviewed at the time the Radiological Effluent Technical Specifications are reviewed. Those areas of the process and effluent monitoring system which will be reviewed at that time include: icq sampling frequencies, required analyses, instrument alarm /.tjag (1) set points, calibration, and sensitivities; and ~ frequency of routine instrument calibration, maintenance, and '(2) inspections. a The process and effluent monitoriig systems cannot be judged as adequacy, until the above items are addressed. a t .3 t t a

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M.E a __u _ :-- ~. g Liquid and airborne process and ef fluent. monitor .y. system at the Shearon Harris Nuclear Power Plant Table 11.5-1 Monitor Monitor Type Monitoring 4 Number a Monitor A. Airborne Process B scin NG 21 REM-3545 Gas Decay Tank S sein, Y sein, 1. RE-1FL-3E06 P, I, NG S sein Fuel Handling Butidtag RE-1FL-3507 2. }iemal Exhaust S scin, Y scin. REM-1FL-3508BSB P, I, NG S scin Fuel Handling Building B scin, y scin, 3. Emergency Exhaust REM-1FL-3508ASA 6 scin REM-1AV-3531 P, I, NG S scin, Y scin, S scin Reattor Auxiliary Building Momal REM-2AV-3531 P. I, NG S scin, Y scin, 4. S sein l{ Exhaust .s i REM-1AV-3532A P,1. NG S scin,'Y scin, '-i ris .i S scin Reactor Auxiliary Building Emergency REM-1AV-3532B P. I, NG S scin, Y scin, s E-S Min REM-2AV-3532A P, I, NG S scin, Y scin, .~ Exhaust S sein B scin, Y scin. REM-2AV-3532B P, I, NG B scin x v-D 30 S scin NG ' ra REM-1TV-3534 S scin NG Condenser Yacutn Pump REM-2TV-3534 t'S 6. 9 Q' Effluent Treatment tfM System S sein, Y scin, @..I; REN-1LT-3502ASA P, I, NG B scin Continuous Containment /$.fi Purge REM-1LT-3502BS3 P, I, NG B scin, Y scin, 7. S sein S scin, Y sein, RD4-2LT-3502ASA P, I, NG B sein S scin, Y scin, P I,NG RDt-2LT-3502BSB B sein ~'

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,-t~ .gj; ...-3.J 4 9-- }:..: ; [j <R ' :p Table 11.5-1 (Continued) i sx.. , '1; l v, 9 Monitor Monitor J~ Monito'r Number Monitoring Type .. y,. B. Liquid Process ..a Y sein 1. Component Cooling Water 1 REM-3501A. Y scin . O System. 1 REM-35018 Y sein ~ 71 2 REM-3504 Y sein 2 REM-35018 n Y scin .'l 2. Auxiliary Stems Con-21-REM-3525A. Y scin densate Tank. 21-REM-3525A Y scin 3. Steen Generator 1 REM-3527 Y scin Blowdown 2 REM-3527 ' Y scin 4. Auxiliary Steam 21 REM-3543 .. J. :,l.i Condensate Waste Processing Systen '. '. h:':$,'l- /, - '\\"] ^ Y sein 5. Waste Processing 1 REM-3544 Building Cooling Water C. Airborne Effluent 1. Plant Yeat. (Release REM-1AV-3509SA P, I, NG S scin, y scin, L.% % Point 1) 8 sein f.'-[,7?, REM-2AV-35095A P, I, NG B sein, Y scin, S sein i.. x. ; /.

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.r.h. 9 2. Waste Processing Building jjl.ih.s Exhaust Systems - n:d hi (a) Release Point 5 REM-1WY-3546 P, I, NG B scin, Y scin,

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3:i$' S scin lP' (b) Release Point 5A REM-1WV-3547 P, I, NG B scin, Y scin, B sein ~ ~ 3. Turbine Building Vent Stack i (a) Release Point 3A r e ~ Ph:d,.9 d;.] (b) Release Point 3B .f %[ s 1.1 Q)- m

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. --p - Table 11.5-1 (Continued) Monitor Monitor Monitor Number Monitoring Type D.' Liquid Effluent Y sein 1. Service Water System REM-1SW-3500ASB Y scin REM-2SW-3500ASB Y scin REM-1SW-3500BSA Y sein REM-2SW-3500BSA Y scin REM-1SW-3500CSA Y scin REM-25W-3500CSA Y scin REM-1SW-3500DSB Y scin REM-25W-3500DSB Y sein 2. Waste Moni*.or Tanks REM-21WL-3541 Y sein 3. Turbine Bu;1 ding Drain REM-1MD-3528 Y sci n '-- P.EM-2MD-3528 s.) 4. Tank Area Drain REM-1MD-3530 Y scin Y sein Transfer Pumps REM-2MD-3530 Y scia l 5. Treated Laundry and REM-1WL-3540 l Hot Shower Tank Pumps Y sein 6. Secondary Waste Sample REM-21WS-3542 Tank Pumps l P = Particulate I = Radiciodine NG = Noble Gases ~ l h l l l c,., Fi. pc., 9

i r.- 1.. 11.5.7.3 Liquid Tank Failure Accident The staff evaluatbd the consequences of tank failures for tanks located outside the reactor containment which could result in releases of liquids containing radioactive materials to the environs. This review was conducted in accordance with the Acceptance Criteria of SRP 15.7.3, NUREG-0300. Considered in the evaluation are (1) the radionuclide inventory in each tank assuming a 0.12 percent operating power fission product source term, (2) a tank liquid inventory equal to 80 percent of its design capacity, (3) mit;igating effects incor-porated into the plant design, and (4) the effects of site geology and hydrology. The results of this analysis were presented in Section 2.4.6 of this SER. 7 O f '- = ? -}}

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