ML20080K815
| ML20080K815 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/14/1983 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079F427 | List:
|
| References | |
| FOIA-84-35 NUDOCS 8309290412 | |
| Download: ML20080K815 (60) | |
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DISTRIBUTION:
Docket File 50-400 f.-
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. Docket File 50-401 (w/o enc 1) l r:: '
METB Docket Files N.
METB Reading File ADRP Reading File Docket !!os. 50-400/401 SEP 141983 MEMORAllDUM FOR: Thomas 11. Novak, Assistant Director for Licensing, BL FROM:
Daniel R. Muller, Assistant Director for Radiation Protection DSI
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SUBJECT:
IETB IUPUT FOR SAFETY EVALUATION REPORT FOR SHEARON HARRIS, UNIT N05. 1 AND 2 Enclosed for your use is the Effluent Treatment Systems Section, METB, input to the Safety Evaluation Report (SER) for Shearon Harris Nuclear Power Plant.
- He delayed transmitting this to you based upon an August 24 meeting with CP&L in which they promised to respond to our open items by September 1.
They have not responded. Thus, we are going forward with our SER input.
Since the draft SER is on CRESS, we have marked-up our copy of the draft SER to reflect changes in the status of open items rather than retype the SER.
If there are, questions concerning this review, please contact J. Hayes (x27649) who is the reviewer for this facility.
Originalsignedl@
DanielR.Mullerj Daniel R. Muller, Assistant Director for Radiation Protection Division of Systens Integration l
Enclosure:
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6.5.1 Engin2:; red. Safety Feature (ESF) Atmospheric Cleanup. System 6.5.1.1 Summary Description i
t The engineered safety feature (ESF) atmospheric cleanup systems at the Shearon Harris Nuclear Power Plant (SHl!PP) 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; (2)
Fuel Handling Building (FHB) Emergency Exhaust System; and (3)
. Control Roon Emergency ' Filtration System.
The RAB emergency air exhaust system consists of, in order, 'a demister, d,
electrical heating coil, pre-filter, HEPA filter, charcoal adsorber, HEPA filter, and decay heat cooling air connection. The purpose V
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 normal ventilation penetration into areas containing equipment essential for safe shutdown close and both RAB emergency exhausts are automatically energized. Either filter unit may then be manually de-energized from'the control room and placed on standby.
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6.5.1.1 By continually exhausti.ng dir a negitive~ pressure of 1/8 inch water p..
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gauge ( G)is established.
Pressure Ts'then controlled by the airflow
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control system which adjusts the variable inlet vanes of the exhaust fans.
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The FHB. emergency air Exhaust system consists of components which are identical to the RAB emergency exhaust with the exception that the charcoal adsorber section is two inches deep while that of th.e RAB system is 4 inches deep. The purpose of the FHB system is to maintain the fuel storage building at a negative pressure so that an[ 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 of the four radiation monitors located around the walls of each g,,
of the fuel pools. Both trains will be actu'ated initially. Either train may be manually de-energized frcxn the Control Room and placed on standby.
Pressure in the FHB is maintained at 1/8 inch WG and controlled by the airflow control system.
The control root; energency filtration system consists of two-1005 capacity filtration systems. Each filtration system inciud,es, in order, a demister, two electric heating coils arranged in series (one operating and one on standby), a HEPA filter, a charcoal adsorber,'
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and another HEPA filter. The purpose of the co,ntrol room emergency filtration system is to limit the amount of radioactivity introduced i -
E into the. control room following an accident and filter radioactivity
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Upon receipt of a 3afety Injection signal (SIS) or a high chlorine concentratio'n 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 respe,ctive fan valves opened. All isolation valves in the normal e'xhaust 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 on the affected side of the control building will automatically
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isolate and the emergency filtration system will start. Upon com-
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plation of the above automatic functions, the operator will pisci 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 quantity of outside air through HEPA tilters and charcoal adsorbers and maintain the control envelope
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- 6.5.1.1 under a positive pressure of +1/8 ' inch water gauge. Air is con-g tinuously drawn for the supply air s'ubsystem, blended with outside air,'pr.ocess,ed through the filtration system and supplied to the control rocm.
Sections 6.5.1 and 9.4.1 of the Harris FSAR contain a detailed description the ESF filtration systems.
6.5.1.2 Evaluation and Findings
, The staff's review included the capability of ESF filter systens to operate after a design basis accident; an evaluation of the systems design, design criteria, design objectives, components design and qualification testing; and design provisions incorporated to facilitate operation and mair.tenance and testing of components to e(;
ensure continued acceptable performance.
staff's review was based upon the relevant requirements of (D GC019 of of, Appendix A to 10 CFR Part 50 for' systems designed for the habitability of the control room under accident conditions; (2) GDC 61 for the design of systers for radioactivity control under postulated recident con-ditions; and (3) GDC 64 for the monitoring of radioactive releases under postulated accident conditions.
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The ESF filter systems were.not reviewed according to SRP 6.5.1 of NUREG-0800 because the acceptance criteria of f.his document calls for the design, testing, and construction of components of' a #
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g 6.5.1.2 the ESF filter system to ANSI H509-1980. 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
' NUREG-75/087, which more adequately reflects the criteria which were in effect at the time the SHHPP ESF filter systra was designed.
In those instances where the equipment was purchased prior to Rev.1,
, conformance with prior document criteria, 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 findings have r
been made.
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The applicant has provided a comparison,,of the design of the SHHPP 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 Regulatcry Guide 1.52 and that these exceptions are trivial in nature and judged to be acceptable.
The staff credited the applicant with 955 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 review cf the applicant's designs, de' sign criteria, and design bases for ESF atmospheric ' cleanup systems and p(.
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6.3.1.2 the systems' conform'ance to applicable Fegulations', guides and industry standards, the staff has concluded that the ESF atmospheric cleanup systems include the equipment.and instrumentation to control the release of radioactive. materials in airborne effluents following a 7_
design basis accident.
The staff finds the proposed ESF atmosphere C-cleanup systems acceptable and the filter efficiencies 'given in Table 2 of htegulatory Guide 1.52 appropriate for use in the accident analyses.
10.5.2 '
Main Condenser Evacuation System
- 10. 4.2.1. Summary Description The main condenser evacuation system (MCES) cf each unit consists C.
y(r of two 1005 capacity mechanical vacuum pumps which. serve the main condenser. At startup, une or both pumps may be operated.to evacuate the condenser. Once operating pressure is obtained, one pump is placed on standby. On startuji, and piior to turbine ope, ration, the'
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non-condensible gases will be discharged directly to the atmosphere in the turbine building area without filtration. With turbine operation the discharge from the mechanical vacuum pumps is diracted
.to the turbine building vent stack without filtration.
Th'e non-condensible gases flow to a moisture separator where most-of the water vapor is condensed. The condensed water' drains to the
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industrial waste sumps. However, the discharge from these sumps
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0.4.2.1 will be dire'cted to t'he secondary waste 's'ystem for treatment on de-tection of radioactivity by monitor RD1-3528. The airborne discharge from the mechanical vacuum pumpi 's monitored for radioactivity. Any radioactivity exceeding the. monitor set point will initiate an alam by the radiation monitors. The applicant has indicated that there is no potentially explosive gas mixture present in the MCES during normal operation, or during shutdown or startup conditions. A more 1
detailed, discussion of the MCES is presented in Section 10.4.2 of the.FSAR.- -
10 4.2.2 Evaluation. Findings The staff's review included the system's capability to process 1.,,
, radioactive gases and the design p.'ovisions incorporated to monitor l
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and control releases of radioactive material.s in gaseous effluents L
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 revier:ed the applicant's system descriptions, piping and instrumentation diagrams, and design criteria for ' components of the HCES with respect to the
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Acceptance Criteria of SRP 10.4.2 of NUREG-0800.
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10.4'.2.2 The staff, in a ghestion to the applit:a'nt, stated' that the 11CES
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-4 JrN The flow passing by monitor R94-4594 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 pump effluent
{b treatment system (CVPETS). The.CVPETS consists,of' a demister, an electrical heating coil, a HEPA filter, a 4-Inch charcoal adsorber, s
another HEPA filter, and two-1005 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.
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g The applicant has responded by clarif,ing the description of how the hogging s.~..
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During hogging operations the vacuum pumps.will discharge to the atmosphere via vent'line 7AE12-19-1 through valve 7AE-Bg-1. This release path is unmo'nitore'd. During hogging operations a portion of the vacuum pump exhaust w'111 be routed through the normal vacuum. pump exhaust path, line 7AE12-g-1, through valve 7AE-B3-1 past noble gas monitor RE-1TV-3534.
INSERT 2 l
As long as flow is directed past radiation monitor RE-1TV-3534, the app'licant i
would have a measurement.of the concentration of noble gases released during hogging operations. In order for the applicant to have an estimate of the noble gases released via the unmonitored vent line, there must be some means of determining the flow rate past the radiation monitor and via the unmonitored release point.
It does not appear that the applicant has such~ capabilities. Since the radiation monitor does not have the capability of continuous sampling for radiciodines and particulates, there is no means available for determining their release during hogging operations and the requirements of Table 1 of SRP 11.5 cannot be met. It is the. staff's position that no release may occur from line 7AE12-19-1 unless...
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of,the license that n diiichar es may occur fom the me anical acuum pumps withou the effluent being renitored The
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!n the exhaust-the ine building.
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to the Heat Exchanger nstJ'tute's " Standards for Steam Surface S' '
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'h sistent with the guidelina given by the above industrial standard as required by the Acceptance Criteria of SRP 10.4.2.
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requests at the ap icant rovid justificati why
.e capacity of t MCES is i consistent th the Duide nes of the " Standards d
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The applicant has indicated that the quality group classification
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to which the llCES is designed is non-nuclear safety, Category 1
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for the condensate vacuum pump effluent treatnent systen and non-
.V nuclear safety, Category 2 for the mechanical vacuum pu ps. tic.:: =, l1 he applicant has not indicated, in Secton 3.2 of the FSAR, he.+ M
.2 these quality group classifications currelate with Quality Group D I
of R'egulatory Guide 1.26. k;h ;. w... 2Gv. accus peu..wed.
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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 potential escape of radioactive steam into A portion of the main steam supply is passed
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the turbine building.
through the turbine gland seals and condensed in.the gland steam The condensate is returned ter the main condenser h 7-condenser.
while non-condensible gases are discharged by two 1005 capacity A'more detailed discussio,n of the blowers' to the environment.
turbine gland sealing system is presented in Section 10.4.3 of the FSAR.
10.4.3.2 Evaluation and Findings The staff has reviewed the turbine gland sealing systo with respect 2
The scope.
to the Acceptance Criteria of SRP 10.4.3 of HUP.EG-0800.
p of this review included the source of sealing steam'and the provision incorporated to monitor and control releases of gaseous radioacti effluents in accordance with GDC 60 and 64 of Appendix A to 10 C,FR (t.
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The sta~ff has reviewed the~ applicant's ' system description' and design criteria for the cc:sponents of the turbine gland sealing
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system.
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The applicant has indicited that the quality group classification
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to which the turbine gland sealing system has been designed is non-4 y kunk s e
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nuclear, safety, Category 7.
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T' dui;r th=ld conforf to the Acceptance Criteria of SRP 10.4.3.
s.h The venting of the turpine gland seal condenser's noncond.ensable '
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--7 10.4;3.2 ta.-Tebie-1-M 3r 11.5 m: r:;r' er rf '. 7. ' TL. ;' --, it i s the staff's position that
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The commitment by the applicant to meet the Acceptance Criteria of fo.f3 th; 0::: SRP will allow the staff to conclude that the turbine
. gland sealing system meets the requirements of GD:: 60'end 64 with respect to the control and monitoring of releases of radioactive materials to the environment by providing a controlled and monitored
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thrbine gland sealing system.
'11.0 Radioactive Waste Management 11.1 Source Terms 11.1.1' Summary Des'cription
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The applicant calculated the liquid and gas'eous effluents from the Shearon Harris Nuclear Power Plant (SHilPP) utilizing the PWR GALE i-computer program. The applicant utilized the source assumptions of Regulatory Guide 1.112. " Calculation of Releases of Radioactive Materials in Gastous and Liquid Effluents fro i Light-Mater-Cooled Power Reactors", and !!UREG-0017 " Calculation of Releases of Radio-active'Haterials ir Gaseo'us and Liquid Effluents from Pressurize'd Water Reactors (PWRs)". Gaseous effluents were calculated from such sources as offgases from the main condenser evacuation'syste::i; leak-age to containment, the reactor auxiliary building, and the turbine, building; noble gases stripped from the primary coolant during nomal s -
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operation and at shut'down; and cover and vent gases from tanks 1.1 1
Liquid effluents were equipment containing radioactive material.
calculated from such sources as shim bleed, leakage collected in equipment and floor drains' such as found in as the reactor auxilia building, fuel' handling, wast $ processing, and turbine buildings, contaminated liquids from anticipated plant operat' ions such as resin sluices, filter backwash, decontamination solutions, sample station I
drr. ins, and detergent wastes.
The staff has perfomed an independent calculation of the primary
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and secondary coolant concentrations and of the release rates
- of radioactive materials using the infomation supplied in the appli-
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cant's FSAR, the GALE computer program, and the methodology Table 11.1-1 presents the principal parameters which k
in NUREG-0017.
were used in this independent calculation of the source terms. These c
source tems were utilized in Sections 11.2 and 11.3 to c individual doses in accordance with the mathematicaT m guidance contained in Regulatory Guide 1.109, Calculation l'
Average Doses to Man Froca Routine Releases of Reactor Effluen
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Aj the Pur. pose of Evaluating Compliance with 10 CFR Part 50, Append j
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Liquid effluents occur from the waste monitoring. tanks, the tre 3I laundry and the hot shower storage tanks and the secondary waste The sources of wastes to these tanks are discusse sample tanks.
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11:1 Section 11.2 of this SER. One source of waste to' the waste moniNr u ~
tanks which is not discussed in Section 11.2 is that originating fro:n the boron recycle system (BRS).
Distillate frces 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 infonnation presented in Tables 11.1-1 and 11.1-2. The applicant assumed that floor drain wastes would be treated by the reverse osmo' sis ~(RO) unit of the floor drain treatment subsystem. The staff
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calculated liquid effluents assuming that the floor drains would be treated by the RO unit. However, the results indicated that over a-5 curies per year per unit would be released based upon the staff V.('-
projected in' puts to the floor drain treatmenti subsystem. Since this s,
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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 l
l had indicated in the FSAR that these evaporators would be available to l
l treat the floor drain wastes when they contained high activity. The l
l staff then calculated the effluents from floor drains based upon the the use of this evaporator. With it's use the effluents from the SHNPP '
could satisfy the criterion of Section A.2 of the Annex to Appendix 1.'
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In its evaluation, the staff detemined that adequate holdu
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.1.1 processing time were available for the treatment of the wastes and the equipment drain wastes.
by The applicant a.ssumed. in his analysis that the wastes
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be processed the secondary waste low conductivity holding tank would The by an evaporator in addition to a mixed bed demineralizer.
iri-staff's review of the applicant's description of this system de-dicated that these wastes would usually be treated only by a d the mineralizer. Therefore, in their analysis, the staff assume
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latter mode of treatment.
The holdup time calculated by the staff for the treatment (input regenerative solutions from the condensate polishing syste l lated to secondary waste high conductivity holding tank) was ca cu hich
.. Sjnce the secondary waste evaporator, w
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to be less than 2 days.
i the was intended for Units 3 and 4, is available for process ng t
contents of the high conductivity holding tank if the evapo h e for Units 1 and 2 becomes inoperable; no alternative tr j
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than had to be considered in lieu of the evaporator even thou l:;
2' days holdup was available for treatment of the regene l drain The staff assumed that chemical drain waste d
and hot tank of Units 1 and 2 and the concentrate from the laun ry e
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k and treated shower RO unit woifid be sent to the'R0 concenva The applicant f{
11.1 by the RO concentrates evaporator' prior to discharge.
l did not include this source in their evaluation d and All detergents" wastes were considered by the staff to d then discharged.
treated by the laundry and hot shower RO unit an from Airborne affluents occur from the building ventilation syst the gaseous the continuous and pre-entry contaiment purges, from d nser evacuation system,
, este processing system (GWPS), the main con eA w
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and the turbine glanii steam condenser.
h ain con-those released from the turbine gland steam condenser, t e HEPA denser mechanical vacuum pump, and the GWPS are The continuous con-filter and' charcoal adsorber prior to discharge.
l adsoiter in tainmer.- - age is filtered by a HEPA filter and charcoa ide the containment.
the airborne radioactivity removal system (ARRS) ins
.A f air-Additional infomation utilized by the staff in its estimat
~.
Additional borne releases is provided in Tables 11.1-1 and 11.1-2.
d details on the liquid and gaseous radwaste systems
.~
in Sections 11.2 and 11.3 of this SER.
The applicant is installing a fluidized bed dryer to pro 1 *:
L,..
orator concentrates (bottoms), and filter sludges for t O
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- m..,/
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ep.o,
(*.* 4 a Y hY dnitW%f.
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L-The opera-of reducing the volume of so.id radwaste shipped offsite.
l 11.1 tion of this volume reduction (VR) equipment will result in additional s.
liquid and airborne effluents. Airborne effluents will result fras the VR system's offgas'and will be discharged on a continuous basis while the s'ystem is operating. There are no liquid effluents which will be discharged directly off-site from the YR equipment operation.
However, based upon FSAR Figure 11.4.2-2, decontamination solutions, condensate from the scrubbers and leakage from pumps, pipes, etc.
~
~ w(11 result in additional quantities of wastes being treated by the floor drain treatment system. Ultimately, some of these wastes will c
be discharged offsite from the was.te monitor tanks and some will again be treated in the VR system.
~
'1 11.1.2 Evaluation and Findings In st s not presented any detail on t VR sy\\
The appl n.
N parti lar, the'a plicant has not addressed
) the volume o waste -
N.
to handled by t VR system; (2) the q ntity 'of airborne dio-1
\\
ac ive effluents rei ased from the VR s tem; (3) the additiona s.
a _
v lume of wastes to b treated by the iquid waste processing sy tem
,. 7 s h a result of operatio of the VR,ystem; and (4) the additional i
adioactive liquid effluents,,y1' ting from operation of the VR
.. r stem.
f-The staff has estimated the quantity of wastes to be treated by the The VR system and the radioactivity associated with these wastes.
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9.111'T.2' staff has estimated the additional amount of radiaoctivity released as airborne effluents from the YR system and as liquid effluents from the liquid radwaste system. -These releases were included with the releases ~
is
~
calculated using HUREG-0017 and the total quantity of effluents was presented in' Section 5 of the SHNPP Environmental Statement
).
Tables 11.1-1 and 11.1.2 of this SER present assumptions,which wer oper4 %,
% sP.fitf-utilized i,n the calculation of effluents resulting fromi!", %,.:r..m..t.
e The a l'icant as not filed with the mmissio details on the VR sy em-design 6n its interface wi various pla t systems such as pr cess and. efflue t tr.ontoring.
uch information w 11 be required p1 ior to approval o the plant' radwaste VR system in to tige information outlin abov.
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Table 11.1-1 Principal parameters and conditions used in releases of radioactive material in liauid and l
gaseous effluents from Shearon Harris Huclear Power Plant 2900 Reactor power level (MWt)
Plant capacity f actor O.80 "
0.12*.
Failed fuel Prinary system 5
hass of. coolant (1b) 3.42 x 10 60 Letdown' rate (gal / min) 3 Shim bleed rate (gal / day) 1.44 x 10 Leakage to secondary system (ib/ day) 100 Leakage to containment building (1b/ day)
'b 160
. Leakage to auxiliary building (ib/ day)
Frequency of degassing for cold shutdowns (times /yr) 2 Letdown cation'.demineralizer flow (gal / min) 6.0 Secondary system 7
Steam flow rate (1b/hr) 1.2 x 10 5
Mass of liquid / steam generator (1b) 1.01 x 10 Mass of steam / steam generator (1b) 9.00 x 10 1.53 x 1 C(~
Rate of steam leakage to turbige area (1b/hr)
Secondary coolant mass (1b) 1.7 x 106 Containnent building volume (ft )
2.3 x 10 Frecuency of containment purges (times /yr)
'4 containment low volume purge rate tfts/ min)_
1730 containment atmospnere cleanup rate (fts/ min) 10*
16 Pre-purge cleanup time curation thr) locine partition factors (gas / liquid) 0.0075 t.eakage to auxiliary builoing 1.0 Leakage to turbine area Main condenser / air ejector (volatile species) 0.15 Liouid radwaste system decontamination factors Boron Recycle Equipment Drain Secondary Kaste System Treatment High Conductivity
. Material System Sub-system 5
10 10 lodine 10 4
105 3
- Cesium, 2x10 10
.. y 4
5 Rubidium 4
10 10 Other 10 "This value is constant and corresponds to 0.12% of the operating power pr.oduct source term as given in HUREG-0017 (April 197E).
1%/ day of the primary coolant noble gas inventory and 0.001%/ day of the prieary coolant iodine inventory.
~
Table 11.1-1
. 6L (continued) -
[-
~
V_
Secondary Vaste Low Laundry and Hot Shower Conductivity R.O. Concentrate Subsystem Subsystem e
Materiai 2
3 lodine 10 104 Cesium, rubidium 2
10 2
4 Other 10 -
10 Liouid Maste Inputs Process Flow Rate Fraction Fraction Collection Time Stream (gal / day) of PCA Discharged time (days) (days)
-Mtrtmoietc Rate (BRS) 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 Low Conductivity Holding Tank 19000 8.7x10-6 1.0 0.47 0.13
- Sturce of Volume Reduction System Wastes Volume / Year / Unit 1.
Evaporator Bottoms 3
(a) Recycle Evaporator 1,025 f (b) Waste Evaporator 960 f (c)
Secondary Waste Evaporator 4,675 ft
~
3 (d). R0 Concentrate 876 ft 2.
Filter Sludge ft Gaseous *1!aste Inouts There is continuous. low volume purge of volu:ae control tank Holdup time for xenon (days) 70 Holdup time for Krypton (days) 70 Fill time of decay tanks (days) r 35 e
S 4
4
- e see h ew
__g em Me m e
- ee e e-e e ee* weep = ee ee ee e s e
~
Table 11.1-2 l
Individual Eautoment Decontamination Factors All nuclides except iodine Iodine
~
1.
Evaporators Secondary Waste and Itaste 10l 10f Recycle 10 10
- Cesium, Other -
l t
Anions Rubidium iluclides 2.
Demineralizers 2
2 Secondary !!aste, Mixed Bed 10 2
- 10 CYCS Laundry Reverse Osmosis 1
10 10 Package and Waste. lionitor Tank, r'
Cation Bed
(.
Recycle Evaporator Feed, Mixed Bed 10 2
10 2
(
Recycle Evaporator Condensate,
-10 1
1 Anion Bed Licents.inet'en-Factors Iodine Others 3.
Volume Reduction Equipment Fluidized Bed Dryer and, Gas / Solids 2
100 Separator
~
~
Scrubber /Preconcentrator 3
100 HEPA Filter 1
100 Charccal Adsorber 100 1
g.34cTrussey,BJld% I' N*
(eo 188 E.bnf e,ph All fluclides
- 4.
- Reverse Osmosis Units Laundry and Hot Shower 30
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Liquid Radwaste Sistem 11.2 Summary Decription i ts of The liquid waste' processing system (LWPS) at the SHH 11.2.1 llect, process, process ' equipment and 'irtstrumentation necessary to c i
id wastes.
i monitor, arid recycle and/or discharge radioactive l qu d on the origin The LWPS is designed to collect and process wastes ba f radioactivity.
of the waste in the plant and the expected levels o timum
~
All liquid waste is processed on a batch basis' to pem Before liquid waste is released, samples are control of releases.
dioactivity present.
analyzed to determine the types and amo;mts of ra t system Based on the results of the analysis and the waste tre in the plant, utilized, the waste may be recycled for eventual reuse irottient under.
retained for further processing, or relea I
controlled conditions.
liquid from the various discharge tanks will automatically detemined waste discharges if radiation measurements exceed a p kn Units 1 and 2's An alarm will be simultaneously actuated Physics control level.
control room, in the WPB control room and the Health
-..'. i room.
tems:
The DPS at the SHNPP is composed of the followi
=... :.
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the equipment drain treatment; (1) the floor drain treatment;
{-
(2) the laundry and hot shower treatment; and
~
(3) the secondary waste treatment.
(4) 1
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i 11.'2.1 The SmPP% has been designed so that-1,1 quid wastes frcen the reactor coolant and its associated subsystems are separated into three main streams - recyclable reactor grade, nonrecyclable, and secondary wa:te. The recyclable reactor grade stream consists of tritiated wastes collected in the ecivipment drains. This streai'i is treated by the equipment drain treatment subsystem. The nonrecyclable equipment stream consists of nonreactor grade water sources and is collected and processed through either the floor drain treatment subsystem or e.
3.heelaundry and hot shower. treatment subsystem. The secondary waste stream consists.of regenerant solutions from the condensate polishing system and backflush fra::: the electromagnetic filters of the steam generator blowdown system and is collectec and processed in the secondary
'A_
waste treatment subsystem.
f
-Q The above systems are shared between the two units at the SmPP.
There are two floor drain treatment subsystems and two secondary waste treatment subsystens shared between the two units. All other shared
,systens are single subsystems.
i _
~
i All releases are monitored before discharge to the cooling tower blowdown. The discharge valve is interlocked with a process radiation 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.,
Additional details op the liquid r'adwaste treatment system follow.
em e
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es
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e emen estum se e 4 = **e6 e ensme-p
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, -11.2.1 The equipment drain treatment subsystem colle' cts reactor grade water
~
from eouipment leaks and drains, valve leakoffs, pump seal leakoffs, tritiated water sources and tank overflows. These wastes are
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collected in the waste holdup tank and then processed via filtration and evaporation. After processing, these wastes are either sent to the reactor makeup water storage tanks or to the waste monitor tank for discharge or to the waste holdup tank for additional treatment.
The floor drain treatment subsystem collects and processes water from
~
~
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 the hot shop. 'The waste is collected in the floor drain tank and y,.
processed by filtration and treatment in,t,he floor drai treatment subsystem reverse osmosis (RO) unit and then collected in the waste monitor tanks. From the waste. monitor tanks, tha 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 equipment drain treatment subsystem, or pumped directly to the waste processing system (WPS) waste evapor'ator for treatment. The latter route I
will be utilized when radioactivity levels are such that filtration and reverse osmosis are insufficient tn reduce the radioactivity to r
acceptable levels.
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11.2.1 The laundry :nd hot shower treatment subsystem collects, in the laundry hot shower tank, detergent waste from the WPB, the FHB and the hot shop.
The applicant expects this waste to be of a quality such that treatment.
for receval of' radioactivity will not noma 11y be required. However, 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 be pa,ssed through a demineralizer and then routed to the treated laundry and hot shower tank. The contents of this tank can be recycled for
~ '
fur.ther' treatment or discharged via cooling tower blowdown or pumped to. the condensate storage tank.
The secondary waste treatment subsystem is designed to treat wastes Q
generated from secondary systems. This water will contain radio-1.
j 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 was'tes such as the backflush from the electr,ccagnetic filters of the steam generator blowdown :yste!2 and the low cpnductivity 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 sample tanks. From the secondary waste sample tanks the' water is
- r
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-=
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either recycled to the condensate stoiage tank, discharged to t
[
11.2.1 cooling tower blowdown or to the neutralization basin or rec back to the low conductivity holding tanks.
The main, source of high conductivity wastes is the regenerant
~
This waste is solution's from the condensate polishing system.
collected in the high conductivity holding tank, processed by a evaporator and the evaporator. distillate discharged to the From the c,onductivity system upstream of the demineralizer.
demineralizer,, treatment is the same as for the low conduc
- ~ -
t a
subsystem.
Turbine building equipment drains and curbed area oil floor drains below the operating deck are collected in th Drains below ground elevation waste sumps of the turbine building.
This sump and the in-
.x are collected in a condensate pump area sump.
dustrial waste sumps discharge through a radiation monitor d
contents of these sumps will norraally go to a yard oil separa l
If the monitor detects hsgli j.
then to tht cooling tower blowdown.
mediggian in the. discharge from one of these pumps, the t
f-will be directed to the low conductivity holding tank for treat The secondary waste subsystem also collects 1) the wa p:
i chemical drain tank which are not sent to the solid waste system for solidification, and 2) the concentrated wa
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11.2.1 waste evaporator, the reverse osmosis units, and the secondary waste
~ '
evaporator. These wastes are collected in the RO concentrate tank and e
are p'rocessed in the RO concentrate evaporator. The distillate from this evaporstor goes to the treated laundry and hot shower storage
' tank for discharge. The evaporator concentrate goes to the waste evaporator concentrate 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 SHl.'PP FSAR.
(
11.2.2 Evaluation and Findings gk.
The LWPS system was reviewed with respect t: - s ' Acceptance Criteria of Standard Review Plan 11.2, NUREG-0800. Tu staff's review con-sidered the capability of the proposed LWPS to meet the anticipated demands of the plant due to anticipated operational oc'currences.'
The potential consequences resulting frcxs reactor oNration have also been considered and the staff has determined the concentratichs of radioactive materials in liquid effluents in unrestricted areas to be h small fraction of the limits in Table II, Column 2 of Appendix B to 10 CFR Part 20.
f e
l 4
_.- 7.
lting The staff has also considered the potential consequenc m,
c d t in-from reactor operation with 1% of the operating fission 1.2.2 d has ventlery in the core being released to the primary coola l
in liquid detamined that the concentrations of radioa t' ion of the limits effluents in unrestricted
- areas will be a small f As discussed of Table 2 Column 2 of Appendix B to 10 CFR Part 20.
ffluents in Section 11.1 of this SER, the staff calculated liquid t systems for using the GALE computer program based upon the trea ted
' liquid effluents described above. These source te in Appendix D of the SHHPP DES.
i11 ing the The staff calculated the doses to offsite individuals u dispersion methodology of Regulatory Guide 1.109 and the liquid Guide 1.113, parameters calculated in accordance with Regulatory fEstimating Aquatic Dispersion of Effluents fr Appendix 1",.
Routine Reactor Releases for the Purpose-of-Imple t eatment The staff has determined that the proposed liquid ra i
materials systems are capable of maintaining releases of ra l
doses in an in liquid effluents such that the calculated individua J.
lc less than 3 neem unrestricted area from all pathways of exposure are l. ','
to the total body and 10 mrem to any organ.
The release of
.J..
The staff has calculated, as noted in Section 11.1, L -
- 1. <
f tritium and f
radioactive materials in liquid effluents exclusive o reactof l'
noble gases and has.found it to be less than S Ci/y f;.'
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-r x y; N$& <. l{
l:t> V. -
IG*.md.
NNiSi
. 1 2
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and the annual dose to any organ of an individual in an unrestricted t h ' 11.2.2 area to be less than 5 millirem per year total 'from both reactors.
Ther,efore, in accordance with the option to Section II.D of App as provided in the Anner to Appendix I of 10 CFR Part 50, the staff h, 1 -
~ ~ -
finds that the liquid radwaste system is capable of reducing liquid i
l radioactive effluents to "as low as is reasonably achievable" levels
~
in accordance with 10 CFR Part 50.34a, Appendix 1 to 10 CFR Part 50, 4
- j and the Annex to Appendix 1.
9 l
s j
The SHHPP DES presents a comparison of the'R!i 50-2 and Appendix I
~
4 y
design objective doses with the doses calculated for the liquid cd -
source terms and a comparison of the RM 50-2 curie limitation with i
- i e.ig,--
the projected releases for the SHNPP.
f.:
y;p The design of the liquid radwaste system presented in t'he FSAR is -
different from that which was proposed at the Construction Pemit s
At the CP stage the steam generator blowdown liquid was l:2.i (CP) stage.
- j. '
Although no process treatment ' system was proposed,
, s.9] _
the applicant made a commitment to install equipment capable of re-y.
to be discharged.
ay ygg
.ducing the level of activity in the blowdown. stream by a fac, tor of s.,4
~ '
~~
' f<.]
The applicant has since decided to install an kN' 3000 or greater.
qN gc.
electromagnetic filter to remove magnetite and other spinel type Q'
.?
oxides which are magnetic and to remove a portio,n of the nonmagne m-The filter is flushed and the water is collected f ri y
..,M particulates.
The flush water is then pumped to the secon the settling tank.
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s a w.,
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e
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~ 11.'2.2 waste low conductivity holding tank's7 ' he steam generator blowdown
~
T passes from the electromagnetic filter to the condenser. The con-densate polishing system provides some removal capability for radionuclides The staff has assessed the overall capability of the radwaste systems to process waste in the event of a single major equipment failure by a comparison of the design flows to the potential process routes and
. equipment capacities. Based upon this review, the staff has determined that ty radwaste system will be adequate to process wastes.
The staff has considered the capabilities of the propose (liquid rad-waste treatment system to meet the anticipated demands of the plant due to anticipated operational occurrences and have concluded that the
!. V l
system capacity and design flexibility are adequate to meet the anti-l cipated needs of the plant.
l The staff has reviewed the applicant's quality assurance provisions for the li id radwaste systems, the quality group classifications used for system components, and the seismic design applied to structures housing these systems. The design of the systems and structures housing these systems meet the criteria as set forth in Regulatory Guide 1.143.
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- n..
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11.2.2 The staff has reviewed the provisions incorporated in the applicant's 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 Regulatory Guide 1.143.
No noted i Sections 11.1 and 11.4 of this SER, appl cant has ot.provided ufficient detail on the VR syst to allow e staff to assess the e ability of the liquid radw te system to access the additional li uid waste generated by e VR system or t
, effluents resulting from this processing Until such'informa ion n./-
is. presented, the SH cannot.be jud as to its compliance th
,4 _
Appendix 1.
This sectio of the SER as been' drafted as,suming tha itM phat ""' meet Appendix I
9 t
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Table 11.2-1 Design parameters of principal ec::iponent's considered in the calculation of liquid effluents from SHNPP, Units 1&2,
Capacity Safety Number
- (each)
Class Component Boron Recycle System 3
Recycle Evaporathe Feed Demineralizer 2
30 ft 3
Recycle Evaporator Feed Filter 2
150 gpm 3
Recycle Holdup Tank 2
84,000 gal 3
Recycle Evaporator Feed Pump 2
30 gpm 3
Recycle. Package 2
15 gpm 3 & NHS' Recycle Evaporator Concentrate Filter 2
35 gpm NHS Recycle Evaporator Condensate Demineralizer 2
20 ft3
. Recycle Evaporator Condensate Filter 2
35 gpm -
Recycle lionitor Tank 2
10,800 gal Recycle Monitor Tank Pump 2
30 gpm Equipment Drain Treatment System
'./.
Reactor Coolant Drain Tank 2
350 gal J[
' Reactor Coolant Drain Tank Pump 4
100 gpm N...
Reactor Coolant Drain Tank Pump Heat Exchanger 2
c l
Waste Holdup Tank 1~
25,000 gal l
Waste Evaporator Feed Pump 1
35 gym Waste Evapora+.or Feed Filter 1
35 gym l
Uaste Evaporator Package 2
15 gpm Waste Evaporator Condensate Dcmineralizer 1
35 gpm Waste Evaporator Condensate Tank Filter 1
35 gpm Waste Evaporator Condensate Tank 2
10,000 gal Maste Evaporator Cundensate. Tank Pump 2
35 gpm Waste Evaporator Cencentrate Tank 1
5,000 gal Maste Evaprator Concentrate Tank Pump 2
35 gpm l
Floor Drain Treatment System l
Floor Drain Tank 4
25,000 gal Floor' Drain Tank Pump 4
35 gpm l
4 35 gpa Floor Drain Tank Filter-Floor Drain Reverse *0smosis Unit
'2 30 gpm
~,
Floor Drain Reverse Osmosis Feed Pump 2
30 gym l
Waste Monitor Tanks 2
25,0g0 gal (30gpm), "
Waste Monitor Tanks Demineralizer 1
50 ft i
Waste Monitor Tanks Nrp 2
35 gpm Chemical Drain Tank 2
600 gal -
Chemical Drain Tank Pump 2'
35 gpm e
L... -
L-
,....._,7.x.
.,.. -. = -.
(*,,
g.
1 T.'
Table 11.2-1 (Continued)
~
~
Laundry and Hot Shower Treatment System Laundry and Hot Shower Tank 2
25,000 gal Laundry and Hot Shower Tank Pump 2
35 gpm -
p-Laundry and Hot Shower Tank Filter 2
35 gpm Laundry and Hot Shower R: verse Osmosis Unit 1
,30 gpm l
Laundry and Hot Shower Reverse Osmosis Feed Pump 1-30 gpm Laundry and Hot Shower Demineralizer 1
50 ft* (30gpm) l Treated Laundry and Hot Shower Tank 2
25,000 gal Treated Laundry and Hot Shower Tank Pump 2
100 gpm Reverse Osmosis Concentrate Tank 2
5,000 gal Reverse Osmosis Concentrate Evaporator Feed Pump 2
35 gpm Reverse Osmosis Concentrate Package 2
10 gpm
~-
Reverse Osmosis Concentrate Evaporator 2
20 gpm Distillate Pump Secondary Waste Treatment System
~
Low conductivity Holding Tank 3
15,000 gal Low Conductivity Holding Tank Pump 2
100 gpm Secondary Waste Filter 2
100 g
~(r Secondary Waste Domineralizer 2
70 ft Secondary Waste Sample Tank 1
25,000 gal Secondary Waste Sample Tank Pump 2
100 gym High conductivity Holding Tank.
1 15,000 gal High Conductivity Holding Tank Pump 2
35 gpm Secondary Waste Evaporator Package 2
15 gpm Secondary Waste Evaporator Concentrate Tank
,2 4,000 gal Secondary Waste Evaporator Concentrate Tank Pump
.2 35 spm s
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.3.)
11.3
' Gaseous Waste 14anagement System 11.3.1 Summary Description The gaseous waste managerent 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 contre
~
tank, dis' placing cover gases, purging of equipment, gas sampling ant analysis operations, and boron recycle process operations.
' ~
~
I Table 11.2-1 provides a listing of the various nomal ventilation systems at the SHNPP and the type of treatment associated with each system. Additional details are provided in Section 9.4 of the FSAR.
If a generalization can be made of the nomal ventilation exhaust treatment systems at the SHNPP, it is that 'he~ exhausts usually flow through a medium efficiency filter, a HEPA filter, and a charcoal adsorber.
The RAB nomal ventilation system (RABHVS) filters air from the con-tinuous con'.iircent purge exhaust and areas from the RAB which conte equipment essential for the safe shutdowa of the reactors including CYCS chiller area, 480 Y auxiliary bus area, areas containing non '
' essential equipment etc. This system exhausts to the vent stack on the roof of the RAB.
- am
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. - --...:.t...
m
_.,._ m m__,, _ _ _ _ __
=
36 -
r-s.,
p f7.:--
7 two catalytic hydrogen recombiners an2 ten waste. gas decay tanks to 11.3.1 accumulate the fission product gases. Eight gas decay tanks are used l-during normal operation and two are used for shutdown and startup.
Nitrogen with entrained fission gases will be continuously circulated around the GWPS b'y one of the two waste gas compressors.' Fresh hydrogen gas is charged to the volume control tank where it is mixed with fission gases which have been stripped from the reactor coolant into the volume control tank gas space. The contaminated hydrogen gas'is continuously vented from the volume control 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 recombiner where the re-
\\(
combiner converts the hydrogen to a water vapor by oxidation. After removal of the vapor the resulting gas stream is circulated to a waste gas decay tank and then back to the compressor. Each gas decay tank is valved into the GWPS recirculation'loep for one.or two days.
Continued plant operation results in the buildup of pressure in the waste gas decay rank due to the accumlation of non-removable fission gases.
When the pressure in the gas decay tanks reaches 25 psig the
.. ?
alignment of the GUPS must be changed due to the. design of the '
f 6
a W=y
e 37 -
7 g
f
~
.~3.1 recombiner. The riew alignment has f13w'from the compressor to the I
11 gas decay tanks to the recombiner and then back to the compressor.
~
This, alignment is suitable for operation up to 100 psig.
The GWPS has analyzers E monitor oxygen concentrations between the oxygen supply and the hydrogen recombiner package.and downstream of the recombiner. Hydrogen analyzers are located in the process stream entering the recombiner and in the discharge stream from the reeombiner.
The applicant has indicated that the normal ventilation system com-plies with the criteria of Regulatory Guide 1.140 and that the GWPS t'
confoms to the criteria of Regulatory Guide 1.143.
~
11.3.2 Evaluation Findings The gaseous waste management system was reviewed with respect to the l
Acceptance Criteria of SRP 11.3, HUREG-0800.
At the construction pemit stage the off-gas from' the condens' r air e
ejectors was untreated and the ventilations systems were only i
filtered by HEPA filters except for the exhaust from the WPB, w'11ch -
was also filtered by a charcoal adsorber. The staff stated in the December 22, 1972 SER for the CP that treatment of the main condenser r
off-gas would be required to reduce this potential source of iodine-131 to the atmosphere to bring the offsite doses into compliance w.ith e
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11.3.2 Appendix 1.
The applicant has added the condenser effluent treatment system, which can be utilized during conditions of high. radioactivity 1
from the mechanical vacuum pumps, and has added charcoal adsorbers to,
the various ventilation systems which exhaust air from contaiminated areas. 'These additions decrease the quantity of iodine' released from the SHHPP and are therefore acceptable when judged against the design objective doses of Appendix I to 10*CFR Part 50. However, it should l
. be.noted that the staff did not credit the plant with removal of the
~
' condenser effluent because the condenser effluent treatment system will not be ized on a routine basis.
The staff has calculated the doses to offsite. individuals utilizing l
the methodology of Regulatory Guide 1.109 and the atmospheric dis-x~
persion parameters calculated in accordance with Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and
~
Dispersion of Gaseous Effluents in Routine Releases from Light-Water-
~
Cooled Reactors. The staf f has detennined that the proposed gaseous radwaste t c.atment ' systems are capable of maintaining releases of radioactive materials in gaseous effluents such that the calculated ind.ividual doses in an unrestricted area from all pathways of expo.
sure are less than 5 mrem to the total body and 15 mri!m to any organ from noble gases and that releases of radiciodine and radioactive material in particulate form respit in doses which are less than
- 15 mrem to any organ.
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11.3.2 The staff has also considered the potenti?1 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 II.D of Appendix I to 10 CFR Part 50 by complying with the Annex to Appendix I (RM 50-2). The SHNPP
' FES GE.5 presents a comparison of the doses and releases calculated for the SHWPP with the design objectives of Appendix I and EM 50-2. The applicant's proposed design complies with the design objectives
^
'of Mt 50-2..Therefore, we have detemined that no further effluent treatment equipment will reduce the cumulative population doses within a 50 mile radius in a cost effective manner.
Cf The staff has also considered the potential consequences resulting from reactor operation with 1". of the operatihg fission, product s
inventory in the core being released to the primary coolant and has determined that the concent. rations of radioactive mnterials in gaseous effluents in unrestricted areas will be a small fraction of the limits of Table 2, Column 1 of 10 CFR Part 20.
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 J
l capacity and design flexibility is adequate to m,eet the anticipated L,
.needs of the station.
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The applicant's q'uality assurance privisions for the gaseous radwaste 11.3.2 systems, the quality group classifications used for system components, the seismic design applied to the system and the structures housing the radwaste systems were also reviewed. The design of the systems e
and the structures housing these systems meet the criteria set forth in Regulatory Guide 1.143 as indicated by the applicant in the FSAR.
i However, the plant does not contain a gas analyzer between the com-Such an analyzer is required in pressors and the gas decay tanks.
Dual analyzers accordance with the Acceptance Criteria of SRP 11.3.
are required.
The staff has reviewed the nomal ventilation system's design, testing and maintenance of the #nEPA 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.
ic-)t has not indicated ether ere are.ruptu e di s in 1
The<ap
^ 'PS itself 'an if there are iquid seals wnstream o the ru ure 1
p.-
dises, and whet ey they ar designed such tha an ex osion will t
c
.cause the permanent oss' of the seals.
U r
The above information is required, along with a,canmitment to install j
I dual analyzers, before the GWPS can be judged to be acceptable.
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gy
- 3. 3..,-.
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41
'I C.
' Note has not
'a d 11.4 of this SER, the applic As noted Sections 11 aff to sufficient detail dn the VR system to allow th provide ion of the
\\
11 result from the ope ne the effluents whichi date n is presented, the
- .P,P cannot IJntil such informa
~
VR s stem.
Appendix I.
Th s section of the
'e udged as to its compliance w be provided b
he infomation
, has been drafted assuming that SE ed in this etion that the 11 not negate the conclusion expre w"
g Append I.
5JNPP will meet the design objectives l
Solid Waste Management Systems
=
11.4
System Description
ess two 11.4.1
~
The solid waste processing system (SWPS) is designed
" wet" solid wastes and " dry" sol.id
- of solid wastes:
I general.'Vat solid wastes consist mainly of spent filter ca N.
i and wastes.
dsmineralizer resins. filter sludges, chemical drain so
~
ed from evaporator bottoms which contain radioactive mater Dry solid wastes consist mainly liquid streams during processing.
t inated of ventilation air filtering media (HEPA, charcoal), con
~
l clothing, paper, rags, laboratory glassware, and too s.
i stems will The spent filters associated with the various ventilat d for disposal be removed from the filter housing, wrapped, and pa
~
e The filter sludges from the liquid rad-
~
using a hydraulic compactor.
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Table '11.3-1 Nomal ventilatio'n system components at the
.Shearon Harris Nuclear Power Plant
[
~
g Medium Demister Heater Filter HEPA Charcoal HEPA X
X' X
RAB Hor:ial Ventilation System X
X X
WP Areas Filtered Exhaust System i
WPG Laboratory Fume Hood X
X Exhaust (except perchlorite)
/
. Condensate Polishing Demineral-X X
X izer Area Filtered Exhaust System Condenser Vacuum Effluent X
X X
X X
X Treatment System
- X X
X Continuous Containment Purge (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 not
- 5ystem will not be used to filter releases on a routiune ba:;is.
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 De sol'idified or sent to the volume reduction systein.
Spent resins will be dewatered and then solidified by cement.. In lieu of solidification, the resins may be shipped dewatered in high integrity containers. Evaporator bottoms will be processed in the volume reduc-tion system.
Chemical drain solutions will be solidified.
~
~
Compressible low-activity solid waste will be compacted in 55-gallon
~
drums. The cc:npactor is equipped with a ' hood, ventilation fan and HEPA filter. The displaced air will be vented through the HEPA filter.
The applicant has indicated that the SVPS has a storage. area capable
/1'(
of storing 1020 drums. The applicant has also. indicated,that the SWPS meets the criteria of ETSB 11-1 Rev. I which is the equivalent to Regulatory Guide 1.143.
The" applicant has ccomitted that all radioactive waste will be pack-aged in accordarice 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 r
contained in Section 11.4 of.'e FSAR.
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. t 1.4.-2 Evaluation and Findings
'., ~
The staff has reviewed the SWPS 1E accordance with the acceptance criteria. of SRP 11.4, HUREG-0800. The scope of thi review included a
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 rev.iewed. The capability of ' he prope' sed t
system to proces5.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 of wastes relative to the requirements of 10 CFR Parts 20 and 71 1,
and applicable DOT regulations have also been reviewed.
The staff will not.yy, ove i.;,e desigr. cf th; sclid radwaste system until the, applicant provides infomation detailing the manner in which various waste components are treated. Infomation which is J
missing includes
- K'.;dv il eu u.w,;
L;wn vi v e vuiuwe re uction 4+ b sy e N _.
t
-(a) ho the s tem operates; (b) expect input stream thei volumes, and associated ac vities, (c) iquid and gas s effluents resul ng from system operation; Q.
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11.4.2 (d) volume reducti factors achi ed; (e) activity sociated wi he disposable ash; and
(.f) confo.ance with Re u atory Guides 8.8,1.140, and 1.143, A
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and BTP CMEB 9.5'-f of SRP 9.5.1;
)
a rawing (CAR-E
') which d p h'e re5M ce header and e was e concentrate 1$ b
.i imitment to a p gr whereby the prese of ree water i the was contain is verifi and commi ent to repro ssi the y.
~
- cont'ai n w en free water is ered; k
gL}fstr $ pHm
-, ' - ~,,,, y,r h description of the r:" d t s.,;Htem; kud a fs Crnpune to sitt sI I
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details on the manner in which the filter sludge from t[
following filters will be handledM Ass <5c r*U #*"N h
/-
(a) reactor coolant;[
(b) seal water injection (c) seal water return; (d) boric acid; M
BRS recycle evaporator feed; f i
(e) n' y
(f)
BRS recycle evaporator conc'entrate;
[2I i,,1 _ _.... =, u gm. a~a W,~
c
-.y i 7
M) recycle evaporator condensate; YW 5
%9ue
. On.rvw CCnd '
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- Md ag.that the vent exhaust from the spent ri :in 41.4.2 storage tanks and the decanting tanks are filtered by i liEPA
~
filter in accordance with BTP ETSB 11-3 of SRP 11.4.
e The applican as a cated that heat tracing from the conc Wates
]
line of e recycle evap rator to the boric acid tank is, o required becaus the 4% weight bori acid solution will not cry tall' te at ambie t temperatures and tha a 12% weight solution s requ' ed before cry 111zation will occur.
e staff's position s that a %% by we ght solution of boric acid wi 1 crystallize a 56-57 F.
Therefore,,
h at tracing should be included fr the conce trates line f the rycycle evaporator to the boric acid ta
- e -
Until the above infomation is provided the SWPS will be cc sidered V
unacceptable.
4 The applicant has not provided the Process Control Program PCP).
The PCP is not required until 6 months prior to the issuanc of the Operating License. The PCP will be judged as to its accept bility.
when it is submitted. '
11.5 Process and Effluent Radiological tionitoring and Sampling ! stens 11.5.1 Summary Description The process and effluent radiciogical raonitoring and sampli ig systems are designed to provide infomation concerning rad' activity
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INSERT 3
- building, The applicant has indicated that portions of the reactor auxiliary id' solutions.,are with piping systems which could contain stagnant boric ac tures
~
equippedwithspaceheatersorhheat"tracedtomaintain. tempera 7
The applicant did not specify what t 70'F during operating modes 1-5.
le evaporator means are being utilized for the concentrates line of the recyc to the boric acid tank.
~~
i t i ed
' ~
it is the staff's position that boric acid solutions should be ma n a n Crystalization at 3 70'F for all modes of operation not just modes 1-5.
In addition, the applicant would not be a function of the operating mode.
did not specify what means were utilized to ensure that the pipin iliary building
~
are maintained at 2 70 F for those portions of the reactor aux Some automatic means should be available to which utilize space heaters.
f it is start the heaters when the temperature approaches 70 F..There ore, ters are the staff's position that the applicant should specify what parame monitored to result in automatic initiation of these heaters.
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g levels in systems throughout the plantrindicaf.e radioactive leakage
- 11. 5.~1 between systems, monitor equipment a'nd perfonnance, and monito'r and s
control radioactivity levels in plant discharges to the environs.
~
k At the SHNPP, the airborne effluent sampling and monitoring systems For
.are located in the plant vents located on the RAB and the.WPB.
liquid eff}uents, the effluent monitor locations are d'ownstream of
,the pumps of the i.WPS waste monitor tanks, the treated laundry and Effluent hot shower tanks, and the secondary waste sample tanks.
inoni~ ors are also located to monitor the industrial waste sumps of t
the turbine buildings, the discharge from the tank area drain transfer pumps and the s' rvice water system.
e Table 11.5-1 contains a listing of both the process and effluent This Table also includes monitors for airborne and liqui,d sources.
(
the type of radioacti,vity monitored for airborne affluents, 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 monitoring system.
11.5.2
, Evaluation and Findings
~
The staff has reviewed the process and effluent monitoring system with As a respect to the Acceptance Criteria of SRP 11.5, HUREGgB00.
result of this review, the following evaluation and Nndings have been made.
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Acceptance Criteria II.C.I.a of SRP n.5 states that the gaseo T
11.5.2 be and liquid process streams and effluent release points shou
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5 monitored and sampled according to Tables 1 and 2 'of SRP Infonnation provided. in Section 11.5 of the FSAR indicated
.,--s the SHNPP did not meet these criteria in the following' a The turbine gland seal condenser exhaust and the m (1) vacuum pump exhaust are not monitored and sampled ance with Table 1.
The condenser vacuum pump effluent is not sampled in
.. (2).
~
ance with Table 1.
There is no effluent monitor for the turbine building vents (3)
(release points 3A and 38) as required by Table 1 an
, provisions are not provided.
p o..;..... 05:
a im nas providea contracic-ry r
4trF -1'mr app 11can entry purge and th continuou containment con inment pr p ge monitorin features of the HNPP. The s ff's po tored on a conti ous ba s and 4
s that both line shall be mehigh radiation signal, isolate I
that bc 5 monitors 11, o 9 urge operation in an automatic f ashion.
W
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he servi wa r syst does not pos ss t capab i,g 9y red by Tabi ob ain continuo ample as re t
.e t-The applicant has indicated, in response to a sta f*
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process and effluent monitoring program will me (4 W F N
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.C Position C of Regulatory Gui$e 4.15,wiaWMme-e eption. This e ep-11.5.2 tion is that e SHHPP will ke use of "n ionally recogni d stand-ards",and 11 not limi hemselves to S traceable s dards only.
it is e staff's tion-that any nationally r nized standard" wil be 125 trac le. Therefo
, the staff d s not accept this pro-
' osed deviat n to Position of Regulatory..
ide 4.156 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
pplicant has addrnssed items II.F.1, d
Attachments 1 and 2 of NUREG-0737 which covers similar criteria o
'owever, d uide 1.97.
effluent monitors to that proposed by Regulatory t
app icant has addr och of t f
required by
(
.F.1', A tac ts 1 and 2.
The applicant h not add' ssed the q
following items f Attachment 1:
l (a
monitoring lo tion or points of ampling; (t )
instrumentation r main ste safety and pressure relief yalve discharge; c
and 2
-(
(e)/ca ilitftf-performi
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.1 ment 2, the applicant has not addressed:
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capability of the on-site laboratory to analyze or measure these sampless and (d) isions for limitM tional dose
~
pers el in th 1
(analys s of sar es..
,74 pq).JJq The applicant can not assure representative samples frcrqveritnrs r:dit :ti" pre ::: stc;;. : :.nd t:9 00. tent; because the capacity of the recirculation pump \\ donot meet the criteria of II.2.a of SRP 11.5.
Th e pumps which do not comply are the #
owi ng:,
r
'(a waste holdup tank; g*
(b) was evaporato oondensate tank; (c) waste mon r tanks; (d) rec e holdup b k;
(
recycle monitor holdu nk.
L d th!t t'
^ eve _
+a a
e**## q""; tic,, LL; esf'::ct tit?
ir. ::prata p;--@, wou a c operate at r ua,;t !ad +h"e ma' accap'~r :r'. i.s. io vi^
11.7..a of My 11.3.
It 15 Ou~ pv>!'wl0L that wiis e.*,.; 20Cld "et D*
cperai.eu a1.
..e sun vas cuadisivu Te. th: M ri-d of tie 7:~;2***d +1
'mee;. nis o.ucpwants ;r aria-Furtherm ra. tbo e+=<< <<ad: 't
~
difficult to envipMuuw operawrs using $nese pumps at the ppm
,rar-: t :;nditien. jthe applicant should propose. an alternative r
means of ensuring that the contents of the various liquid waste may be sampled in a represantative manner.
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11.5.2
-Othe area) of the acceptance criteria of SRP 11.5 which the applicant has not addressed or which deviate from the acceptance c (a
capability to r antami-n T vni ^wu uunze der e
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s gase sseffiti nt withou opent the pro ss system r losing g',
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the capab ity to isolate the effluent stre
)
he divers alves oc ed t
i l( F 84 mo do not fai in the closed position; q
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t confoman of n
- ESF ins tat n to th desig uida f{-
of nd 11.5-A of S ar not been a ressed; and
}1rfdnco'rporation of administrative controls and procedures to minimize j
inadvertent or accidental releases of radioactive liquidsy ~+ -
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r The turbi.le building drain monitors and the tank area drain monitors 7
"J(
do not provide a record of effluent flow. Therefore, there appears to L
}.'Q.' 9 be no means to determine the quantity of activity released nor the l
{.',
' volume released in accordance with Regulatory Guide 1.21'.
It is the
' (.. ' staff's position that the SHHPP possess the capability to determine g'
the quantity of effluents released from these two source
\\
The ap151icant h not provided sufficient nfomatton in the FSAR to N
all w the staff to detennine whether t releases fr the vents of
'e b
on recycle system are routed in s ch a manner that a quate mo. toring a d sampling of these urces is p es~ent at the SHNPP. Su omation i s required.
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the staff has luddthatthe/hr mt ',. e ;;L p -
Based upon th f 4 &ef -hus fann
$4L n baaldtwy i
effluent re'1 ease points;3A and 3B shoul'd be the pointsof monitoring and j
not he condenser vacuum puinp effluent alone. This change would (1) result t
'n the monitoring of'a,petential effluent release source (condensate i
Q u ctclu tt.t b y ib-Pre.%.:c nmsk wo sche n; polishing cubicles), (2) allow isokinetic samples to be taken, and (3) minimize the potential damage of high humidity air on the sampler's charcoal adsorber.
S T b
SQ %-@.
The applicant has proposed a method for determining the release of radio-
' activity from the' safety relief valves and the atmospheric steam dump valves which is similar to that proposed for the Waterford Plant. The r
staff is assessing this method at this time. Based upon the determination Mg made in the Waterford review,'the ac::eptability of the method proposed for Shearon Harris will be the same.
O O
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e The ap licant has' provided cent adictoh infomation on the operation of
~
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11'. 5.' 2 Section 9.2.10.2.2 the vent valve on the WPB coolir.g water surge tank.
~
states that this valve kloses automatically on a high radia-of the FS tion signal from the discharge of the WPB cooling water monitor g
(REM-3544)'.
he applicant's response FSAR question 460.35 stated t of an alarm from REM-3 4.the operator must take the that upon rece action tb 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 diately because failur of a seal in either the waste gas c'ompres or or the catalytic reemb ner of the waste gas new and significant rele se path for effluents.
system could result in As a result of their responses to staff questions on the FSAR, the Om applicant needs to revise va'inue nacitinm nf tha re".
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1) igures 9.2-Yan 10.1.0-6 show sat ing poin
-11,. 12f
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& an of the steam g tor blowdown; t,.
flec
. g ]able 9.3.2-2, Figure 9.3.2-2, and Section 9.3.2.2.2 to re
'.,3, l
rab sampling of the service water system;emad yl@ ',h f '.M..
nts of L
o.
3). Table
.5.2-re o.
rin
> (l
/
- HUR G-0737 Attachments 1 and 2.
.t ant has not add ssed the m itoring qf th flue from e app the volume eduction stem. This must addr sed.
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~ ~11.'5.2 The staff's reviek 'of the process anieffluent monitoring system has E'
not addressed some items of SRP 11.5. Those it' ems which have not been addr,essed will be reviewed at the time the Radiological Effluent Technical Specifications. are reviewed. Those areas of the process and efflueni monitoring system which will be reviewed at that time incJude:
(1) sampling frequencies,' required analyses, instrument alam/
set points, calibration, and sensitivities; and (2) frequency of routine instrument calibration, maintenance, and
/
.. inspections.
The process and effluent monitoring systems cannot be judged as to their adequacy until the above items are addressed.
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Table 11.5-1 Liquid and airborne process and effluent monitoring system at the Shearon Harris Nuclear Power Plant Monitor Monitor Monitor Number Monitoring Type A.
Airborne Process
~
1.
Gas Decry Tank 21 REM-3545 NG 3 sein 2.
Fuel Handling Building RE-1R-3506 P. I, NG S sein, Y scin, Nonnal Exhaust RE-1R-3507 8 sein 3.
Fuel Handling Building REM-1R-3508BSB P. I, N G' 8 sein, Y scin, Emerge.ncy Exhaust 8 scin REM-1R-3508ASA 8 scin, y scir.,
8 scin
(
4.
Reactor Auxiliary REM-1AV-3531 P. I, NG S scin, Y scin, Building Normal S scin Exhaust REM-2AV-3531 P. I, NG S scin, Y scin.
4 S.scin q
E.
Reactor Auxiliary R:
\\V-3532A P. I. NG S sein,'Y scin, N..
Building Emergenc;y S sein Exhaust RE.i AV-3532B P I,NG S scin, Y scin, 8 scin REM-2AY-3532A P. I, NG S scin, Y scin.
S sein REM-2AY-35325 P. I, NG S scin, Y scin, 8 sein 6.
Condenser Vacusa Pump
' REM-1TV-3534 NG B sein Effluent Treatment REM-2TV-3534 NG S scin System 7.
Continuous Containment REM-1LT-3502ASA P. I, NG S sein, Y sein, j
Purge B sein REM-1LT-3502BSB-P,1. NG
.S scin, Y sein, 8 scin RDl-2LT-3502ASA P. I, NG S sein, Y scin, 8 sein R5M-2LT-3502BSS P I,NG S scin, Y scin, 3 sein f
w Sul C dwn.
.y.w.uw g w:.,
j
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. Y, d
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Table 11.5.
(Continued)
~
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e i
Monitor Monitor
' Number Monitoring Type Monitor B.
Liquid Process 1.
Component Cooling Water 1 REM-3501A Y sein j
Systan..
Y sein 2 REM-35018
~
Y sein 2 REM-3501A Y sein 2.
Auxill'ary ' Steam Con ;,.
21-REM-3525A Y sein
~.
. -REM-3525A densate Tank. -
Y sein 21 3.
Stene Generator
' 1 REM-3527 Y scin Blowdown 2 REM-3527
~
Y sein 4.-
Auxiliary Steam 21 REM-3543 l
Y sein Condensate Waste.'.
F
..n, Processing System -5.l.,l.:.,.
p-
,.~.i.,
5.
Waste Processing 1 REM-3544 Y'scin s
Building Cooling Water 7
C.
Airborne Effluent 1.
Plant Vent (Release REM-1AV-35095A P. I, NG S sein, y scin, Point 1) 8 sein i
REM-2AV-35095A P,1, NG S sein, Y scin, 8 sein 2.
Waste Processing Building Exhaust Systems 1
(a) Release Point 5 REM-1WV-3546 P. I, NG S sein, Y sein, S sein l
(b) Release Point 5A REM-1WV-3547 P,1 NG S scin, Y scin.
S sein 3.
Turbine Building Vent Stack L-(a) Release Point 3A
.~
(b) Release Point 3B
- q.j*
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_ a '.: 5' i.*' ct % ::4 9.,7* %,7;
- 1-
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f r
j Q
-.=-
Table 11.5-1
~;' i' "
(Continued).
\\. - -
Monitor Monitor Monitor Number Monitoring Type _
D.
Liquid Effluent Y sein 1.
Service Water System REM-ISW-3500ASB Y 5cin REM-25W-3500ASB Y sein REM-1SW-3500BSA
- Y sein REM-25W-3500BSA Y scin REM-1SW-3500CSA Y sein REM-2SW-3500CSA Y sein
~
REM-1SW-3500DSB -
Y scin
~
l' REM-2SW-3500DSB Y scin 2.
Waste Monitor Tanks REM-21WL-3541 Y sein 3.
Turbine Building Drain REM-1MD-3528 Y scin..
REM-2MD-3528 Y sein ;
~
4.
Tank Area Drain REM-1MD-3530 '
Y scin 'I Transfer Pumps REM-2MD-3530
,. ~
_'/[
Y sein x-5.
Treated Laundry'and REM-1WL-3540 Hot Shower Tank Pumps Y sein I
6.
Secondary Waste Sample REM-21WS-3542 Tank Pumps
~
- = Particulate 1 a.Radiciodine NG = Noble Gases I.(
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11.5.7.3 Liquid Tank Failure Accident The staff evaluated 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 aceordance with the Acceptance Cr'iteria of SRP 15.7.3, NUREG-0800. 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) mitigating effects. incor-porated into the plant design, and (4) the effects of site geology and hydrology.
L <r The results of this analysis were presented in Section 2.4.6 of this
\\
SER.
l l
1 I
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f DISTRIBUTION:
Docket File 50-400
~
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. Docket File 50-401 (w/o encl) b, METB Docket Files METB Reading File ADRP Reading File Docket Isos. 50-400/401 SEP 141983 g(jg MEMORANDUM FOR: Thomas M. Novak,- Assistant Director for Licensing, DL
(
FROM:
Daniel R. Muller, Assistant Director for Radiation Protection, DSI
SUBJECT:
I;ETB INPUT FOR SAFETY EVALUATION REPORT FOR SHEAR 0H HARRIS, UNIT HOS. 1 AND 2 Enclosed for your use is the Effluent Treatment Systems Section, IETB, input to the Safety Evaluation Report (SER) for Shearon Harris Nuclear Power Plant.
'~
~We delayed transmitting this to you based upon an August 24 meetingsfith CP&L in which they promised to respond to our open items by September 1.
They have not responded. Thus, we are going forward with our SER input.
Since the draft SER is on CRESS, we have marked-up our copy of the draft SER to reflect changes in the status of open items rather than retype the SER.
, ~
If there are questions concerning this review, please contact J. Hayes (x27649) who is the reviewer for this facility.
f' Originalsignedhgl Denfel R.Mu!!ad Daniel R. Muller, Assistant Director for Radiation Protection Division of Systems Integration
Enclosure:
As stated cc:
R. Mattsca R. Capra W. Gamill G. Y,nighton B. Buckley C. Willis samummme A3 00 h&4// l~ n O
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Engineered Safety Feature (ESF) Atmospheric Cleanup. System 6.5.1-Summary Description
- a..
1.5.1 1 The engineered sa'fety feature (ESF) atmospheric cleanup sy the Shearon Harris Nuclear Power Plant (SHl!PP)' consist of pro f
equipment and instrumentation necessary to control the rele radioactive iodine and particulate material following a desy accident (DBA). At the SHNPP,' there are three filtration systems These systems are:
designed for this purpose.
Reactor Auxiliary Building (RAB) Emergency Exhaust System; (1)
Fuel Handling Building (FHB) Emergency Exhaust System (2)
Control Room Emergency Filtration System.
~
~
~ (31 The RAB emergency air exhaust system consists of, in o electrical heating coil, pre-filter, HEPA filter, charcoal adso The purpose HEPA filter, and decay heat cooling air connection.
of this system is to limit the potential for. post-accident rad Those areas logical releases to contaminated portions of the RAB.
i which are filtered include the rooms containing the charg ng p d the the RHR heat exchanger, containment spray and RHR pumps, a i
eas mechanical, electrical and heating and ventilation penetrat on Upon receipt of a Safety Injection Actuation Signal and rooms.
ilation penetration
.(SIAS).,. air operated valves on the nomal vent
, (-
ntial for safe shutdown close into areas containing equipment. esse N-Either and both RAB emergency exhausts are automatically ene
~
control filter unit may then be manually de-energized from the room and placed on standby.
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By continually exh usting a'ir a negitive' pressure of 1/8 inch wate
- 6. 5.1.1
? -(O gauge (MG)is established.
Pressure is then controlled by the airflow a
control system which adjusts the variable inlet vanes of the exhaust fans.
The FHB emergency air exhaust system consists of coaponents w are identical to the RAB emergency exhaust with the exception that the charcoal adsorber section is two inches deep while that of the The purpose of the FHB system is to RAB system is 4 inches deep.
that
~~
- -. maintain the fuel storage building at a negative pressure so any radioactive iocine or particulates released to the building be contained within the building and then filtered prior to releasa.
~
The actuation of the FHB system is from a signal initiated'by one of the four radiation monitors located around the walls Either Both trains will be actuated initially.
(
of the fuel pools.
train may be manually de-energized from the Control Room an Pressure in the FHB is maintained at 1/8 inch MG on standby.
controlled by the airflow control system.
energency filtration system censists of two-1007, '
n The control room 2,.,
Each filtration system inc1'udes, in capacity filtration systems.
h order, a demister, two electric heating coils arrangeo in series f,qd
~
(one operating and one on standoy), a HEPA filter, a charcoa
- i.
and another HEPA filter. The purpose of the co,ntrel room emergenc filtration system is to limit the amount of radioactivity introduc
~into the control rooi following an accident ard filter radioac 7'e0!
n twea bk
~
t f.
~
~
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+i:..
already in the contr'o1 roos such that do'ses to control roem operators
- b ';. 6.5.1.1
.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 F
high chlorine concentration signal at the outside air intakes, the
~
outside intaN 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 valves All isolation valves in the normal exhaust system will opened.
cUse and the exhaust fans de-energized.
All of these actions will occur automatica1ky. Upon receipt of a high radiation signal from the radiation monitor located within each air intake, the air intake on the affected side of the control building will automatically isolate and the e'mergency filtration system will start. Upon com-s -~.
i plation of the above automatic functions, the operator will place one of the emergency filtration trai-on standby, select and open one emergency outside air intake based upon radiation and chlorine readings, and open exhaust bypass danpers for laboratory and kitchen
,f.i bypass exhaust.
,d The control room emergency filtration system will process a mixture of control room air and a small quantity of outside air threugh M
HEPA filters and charcoal adsorbers and maintain the control envelope
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Air is con-(f
'6.5.1.1 under a positive pressure of +1/8 inch water gauge.
tinuously drawn for the supply air s'ubsystem, blended with outside air, pr.ocess,ed throuch the filtration system and supplicd to the control rocm.
Sections 6.5.1 and 9.4.1 of the Harris FSAR contain a detailed description the ESF filtration systems.
l
'6.5.1.2 Evaluation and Findings
' The staff's review included the capability of ESF filter systens
~
~
to operate after a design basis ac'cident an evaluation of the systems design, design criteria, design objectives, components desi-and qualificatica testing; and design provisions incorporated to facilitate operation and' maintenance and testing of components to
.( -
ensure continued acceptable performance. The staff's review was L
k based upon the-relevant require:nents of (1) GDC 19 of of, Appendix ;
to 10 CFR Part 50 for' systems designed for the habitability of the control room under accident conditions; (2) GDC 61 for the design of systems for radi.oactivity control under postulated accident con-
~
ditions; and (3) GDC 64 for the monitoring of radioactive releases under postulated accident conditions.
b;.,
j i.;.
- The ESF filter systems were not reviewed according to SRP 6.5.1
+
i' of NUREG-0800 because the acceptance criteria of this document calls for the design, testing, and construction of cc'nonents of
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f These standards were not the ESF filter system to ANSI H509-1980.
1 6.5.1.2 in existence at the time the SHNPP ESF filter systems were d Therefore, the review of the nor when the equipment was purchase 6.
ESF filter systems was~ conducted utilizing SRP 6.5.1, Rev.1 HUREG-75/087, which more adequately reflects the criteria wh were in effect at the time the SHNPP ESF filter system was de In those instances where the equipment was purchased prior t
~
confomance with prior document criteria, whether Regulato As 1.52, Rev.1, or SRP 6.5.1, Rev. O, was considered acceptab a result of this review, the folicwing evaluations and findings been made.
The applicant has provided a comparison, of the design o ESF filter systems with the regulatory positions of Regulato The staff has de 1.52, Rev. 2 March 1978 in a. Table of the FSAR.
termined that the applicant has proposed few exceptions t Guide 1.52 and that these exceptions are trivial in nature to h acceptable.
~
- e..
The staff credited the applicant with 955 removal efficienc 7.;:
f;.1 methyl radiciodine for the FHB emergency exhaust sys methyl radiciodine for all other ESF filter systems".
As a result of the staff's review of the applicant's design g
W w
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?..J s~l Sy2*f!* '
fevs -o;Mn if%$;b.9
- M%v.
' * * * * *'*'enh,._ygg#g.,,
a the systems' confordance to applicable r'egulations, guides and
~
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6.5.1.2 standards, the staff has concluded that the ESF atmospheric clean systems include the equipment and instrumentation to control t release of racloactive materials in airborne effluents following a The staff finds the proposed ESF atmosphere design basis accident.
cleanup systems acceptable and the filter ef ficiencies "given in TabTe 2 of Regulatory Guide 1.52 appropriate for use in the accident analyses. -
Main Condenser Evacuation System 10.4.2 10.4.2.1 Summary Description The main condenser evacuation system (MCES) of each unit con of two 100% capacity mechanical vacuum pumps which serve th At startup, one or both pumps may be operated.to evacuate condenser.
Once operating pressure is obtained, one pump is the condenser.
On startup, and prior to turbine ope. ration, the placed on standby.
non-condensible gases will be discharged directly to the atmosph
~
\\!ith turbir.e
~. ;
in the turbine building area without filtration.
d operation the discharge from the mechanical vacuum pump i.,~
6
.to the turbine building vent stack without filtration.
(;j,
Th'e non-condensible gases flow to a moisture separator where a"
The condensed water' drains to the of the water vapor is condensed.
However, the discharge from the'se sumps industrial waste sumps.
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a.
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7-g, will be direc'ted to t'he secondary waste system for treatment on de-
~
10.4.2.1 The air 6orne di: charge tection of radioactivity by monitor RD1-3528.
Any ft om the mechanical ~ vacuum pumps it monitored for radioactivity.
radioactivity exceeding the. monitor set point will initiate an alarm The applicant has indicated that there by the radiittion monitors.
is no potentially explosive gas mixture present in the MCES during A more normal operation, or during shutdown or startup conditions.
detailed discussion of the MCES.is presented in Section 10.4.2 of the'FSAR.
10.4.2.2 Evaluation Findings The staff's review included the system's capability to process radioactive, gases and the design provisions incorporated to monitor
-ffluents and control releases of radioactive material.s in gasc -
10 CF.Part 50.
2,3 ynMance with GDC. 0 and 64 of Appendix A to 6
The quality group classification of equipmeni. and components used to collect gaseous radioactive ef fluents was reviewed relative to The staff revieved the the guidelines of Regulatory Guide 1.26.
applicant's system descriptions, piping and instrumentation diagrams, and design criteria for components of the MCES with respect to the Acceptance Criteria of SRP 10.4.2 of IWREG-0800.
m e
4 4
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2' 10.4.2.2 The staff, in a q0estion to the applihant, stateo that the MCES-contains no provisions for sampling ap4 monitoring discharges feem.
4topgdp )
..;t during start (up operations as specified
"-t'
^-
+
g in Table 1 of SP.P 11.5. _
_The apprea*
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Ja--sti^ h, the:
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..; ;4 du *a;-+5::: :;:n ti ns, gem 17g:nq The flow passing by monitor ".:". 2:M would allow action to be taken to close valves 7AE-B3-1 and 7AE-B9-1 on a high radiation signal and the rerouting of the off-gas through the condenser vacuum pump effluent
(-
treatment. system (CVPETS). The CVPETS consists,of a demister, an g
(
electrical heating coil, a HEPA filter, a 4-Inch charcoal adsorber, another HEPA filter, and two-100f. capacity fans in parallel.
It is the staff's pcsition that the release of the off gas during f) hogging operations must be monitored as noted in' Table 1 of SP,P 11.5.
')/
a e laaa c
'1 ~ 4 e m 4 n+ained -through wh- ",'. : ',,L:,.)L, TKE:B9:'l-e ee-tenadmitor-tom.
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o INSERT 1 (e,
The applicant has responded by clarifying the description of how the hogging x
operatior, occurs. During hogging operations the vacuum pumps.will discharge This to the atmosphere via vent'line 7AE12-19-1 through valve 7AE-59-1.
release path is unmonitored. During hogging opersilons a portion of the vacuum pump exhaust will be routed through~the normal vacuum. pump exhaust
~
path, line 7AE12-9-1, through valve 7AE-83-1 past noble gas monitor RE-1TV-3534
~-
INSERT 2
~
As long as flow is directed past radiation monitor RE-1TV-3534, the applicant would have a measurement of the. concentration of noble gases released during hogging operations.
In order for the applicant to have an estimate ofthenoblegasesreleasedviatheunmonitoredvenYline,theremustbe some means of determining the flow rate past the radiation monitor and via the unmonitored release point. It does not appear that the applicant has such capabilities.
Since the radiation moniter does not have the capability of continuous sampling for, radiciodines and particulates, there is ne means available for determining their release during hogging operations and the
~
~{
' 2 requirements of Table 1 of SRP 11.5 cannot be met.
It is the. staff's position that no release may occur from line 7AE12-19-1 unless...
(continue with original text)
Ou bp of j
9 e
- z w ~ ? ergj 4 4 ~~ -a f.W-Y:l1 } ~ - -
'[5NM VP~ fy ,( y I ll..(~ ~... ( of the' license that n dischar es nay occur fom the ~ (, 10.4.2.2 a en.
- 1 mac anical cuum pumps withou the effluent being nonttored The N C staff wotf}d allow such release only if thera va _
conitor n the exhaust. the ine building. The applicant has indicated that the main coridenser is etnstructed to the Heat Exchanger nst tute's " Standards for Steam Surfacef Condensers"gn)-Qh t i m...vi addcc Ed.c.;th: he'liCES eepees y is con-4 g sistent with the guidelines given by the above industrial standard - ~ The aff as required by the Acceptance Criteria of SRP 10.4.2. requests at the ap icant provid:-[justificati. why '. e capacity of th MCES is consistent th the guide nes of the " Standards 6 f Steam 5 face Condense ~ The applicant has indicated that the quality group classification s to which the 11CES is designed is non-nuclear safety,-Cetzgery 1 for the condensate vacuum pump eff!"ent treatnent systen ud non-2-c u:'! r, nuclear safety, Category 2 for the mechanical vacuun pu ps. b he applicant has twt indicated, in Secton 3.2 of the FSAR, 'e these quality group classifications currelate with Quality Group D of R'egulatory Guide 1.26. Such :. -. 6.i.. i.aL ~ x w v..oca. ^ a '.t. The doisa snouio cum.un.i iv,J. A c = ; t :. '. :. " " ' " ' " l ~ ()$' Y f Y f m th the e = < r.s cf = e = t = = c... = : n z btd Jwse the ncESN gon om se with the acceptance criteria of SRP 10. ( +;. ; ~. qm 4 J, s enw :; I c A.x..u D 2 d ? _'j n. w ^ ' ' " ' - - - - - - - - _. _. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _
~ -, u. - ' -. r .~ (. g ~ 10.4.2.2 and wee 4her the MCES has aet the requirements of GD; 60 and 64 with g respect to the control and monitoring of releases of radioactive ~ materials to the environment, sad ""eth:r th: MCE S:: ;t ti.; ce- ~ -w 4ce.Tib.t s i-sne incustrias s canuaru " Star.d:rd: fer Ste-- :_rf::e a Condensers". 10.4.3 Turbine Gland Sealing System 10.4.3.1 Summary Description The turbine gland sealing system provides sealing stema to the main turbine generator shaft to prevent the leakage of air into the turbine casings and the potential escape of radioactive steam into the turbine building. A portion of the main steam supply is pas:ed through the turbine gland seals and condensed in.the gland steam i \\s_. condenser. The condensate is returned te the main condenser hotwell ~ l_. while non-condensible gases are discharged by two 100% capacity blowers' to the environment. A'more detailed discussion of the turbine gland sealing systen is presented in Section 10.4.3 of.the FSAR. ^,- 10.4.3.2 Evaluation and Findings , ~ - , The staff has reviewed the turbine gland sealing system with respect A,.,,, n-to the Acceptance Criteria of SRP 10.4.3 of !!UREG-0800. The scope . ff. : ' of this review included the source of sealing steam'and the provision incorporated to monitor and control releases of gaseous radioactive e'ffluents in accordance with GDC 60 and 6'4 of Appendix A to 10 C[FR A- .p,,, h? Ammn %w Ms+1.
1 U 10.4.3.2 Part 50. The staff has reviewed the'~ app 1'icant's ' system description ~ \\-' and design criteria for the ccaponents of the turbine gland sealing system. The applicant has indicited that the quality group classification i to which the turbine gland sealing system has been desi.gned is non I m' k u ras s -44(cated nuclear. safety, Category ?. iIlSecton W h h W, 4rt'p ch::M b d"' e %sp';tese Quality Group D of Regulatory Guide 1.26. %:h - [t cc r:. corrcht c"
- d::t: i. pr:!*d. Tu d::i;r :h::'.d conforr to the Acceptance Criteria of SRP 10.4.3.
The venting of the turbine gland sehl condenser's noncond.ensable ' -v r M k w ble1ofSgP11.5N#"**'bAMb'WIC 7me. as req red by gases is net monitorec(or'dt!N'5 L f b di tvo 4 4 R w p led c. Y o Q a wo T T gtf rar, +h=* +kay da t,.^ app'ictr.t :ttte_ i Y';s n:. L o6W $Yo ~ th M 'ks
- x f mm r.. :.urt n: ;nad.c x..d;;x ; pr'- ';2' W
e O bid 5 w h hhh h 5h b h bh W whd BON $ h N $ h h k0 N d dI biOc^.2-SC the LKi^. t d ??t#"# ty $ 70.^ b '. ;, 3"#d?'#"" '!:' 2 0 _ 'n'u ei e r--n 1 -._ &Jg t._ g & G440 3G GI he UI4MC 4 AJ G & 4& 64W w to f6 4 4 6w E y am 6 .s W be. wwg a w c' b6$U bas 4 ad 6 66
- a*
_t. __..n-- t- ~~~ en .r ww www w-i ws b o ek C D ) g G DQU[h@ dIid G A w l.i & W h Ts 4 6 4 w a s g www w i w a tsy 9 a e Apje.ndir-A-to-t0-f"" P a -t :',. equ2 res c.ani wr I ns a..! i:' :: -ets i &l e 4 e .e e n. et-* g 4 ? \\
- s $2. ' ) i $ '
r.pi: ;l dw.' c. l \\ Y. '. *: ~1y ? kl. h dd, ;M_. cx -- - ____-m m__ m_
. ~ ~ .u (y' ta.-Te&ie-1-of-SRP 11.5 :1;; requ'~ r ;1'q.' Ec ;'- , it is 10.4.3.2 loen the staff's position thatje:my:4 of the turbine gland sealW Psdicah* ,~. r. bM 'i ht f*h"*h'n e.thmsl W *CbdweenN condenser scar :Sth;t t:.
- et;d x,, ' ; :1:e ecrer.
[s,.e y orth ~ ~ The commitment by the applicant to meet the Acceptance Criteria of 'fo.%3 th; 5:?e 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 . materials to the environment by providing a controlled and conitored turbine gland sealing system. 11.0 Radioactive Waste Management 11.1 Source Terms ~e 11.1.1 Summary Des'cription ( The applicant calculated the liquid and gas'eous effluents from the Shearon Harris Nuclear Power Plant (SHt!PP) utilizing the PWR GALE The applicant utilized the source assumptions of computer progran. Regulatory Guide 1.112, " Calculation of Releases of Radioactive liaterials in Gaseous and Liquid Effluents from Light-Mater-Cooled Power Reactors", and !!UREG-0017, " Calculation of Releases of Radio-active 1iaterials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs)". Gaseous effluents were calculate scurces as offgases from the main condenser evacuation' system; leak-age to containment, the reactor auxiliary building, and the turbine, building; noble gases stripped. from the primary coolant during nomal b.. / MuM
\\ ~ a. operation and at shutdown; and cover and vent gases from tanks and J-11.1 equipment containing radioactive material. Liquid effluents were calculated from such sources as shim bleed, leakage collected in equipment and floor drains such as found in as the reactor auxiliary building, fuel' handling, waste processing, and turbine buildings, contaminated liquids from anticipated plant operat' ions such as resin sluices, filter backwash, decontaminatio.n solutions, sample station drains, and detergent wastes. The staff has perfomed an independent calculation of the primary 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, cnd the methodology presented Table 11.1-1 presents the principal parameters which ( in ilUREG-0017. These were used in-this independent calculation _of the source terms. source terms were utilized in Sections 11.2 and 11.3 to calculate individual doses in accordance with the mathematica1' models and. guidance contained in Regulatory Guide 1.109, " Calculation of Annual Average Doses to 14an From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1." Liquid effluents occur from the waste monitoring tanks, the treated ,.,a laundry and the. hot shower storage tanks and the secondah was The sources of wastes to these tanks are discussed in. sample tanks. e ~ %w m 'g i.@M xd,w.3i irrir.E *:} &r= _ i~_~I_~ ~ l _^' ~ ~ .w
j 1 ' f-L ~ p( 11.1 Section 11.2 of this SER. One~ source of vraste to the waste monitor tanks which is not' discussed in Section 11.2 is that originating ' from the boron recycle system (BRS). Distillate fran 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 infonnation presented in Tables 11.1-1 and 11.1-2. The applicant assumed that floor drain wastes would be treated by the reverse osmosis (RO) unit of the floor drain treatment subsystem. The staff calculated liquid effluents assuming that the floor drains would be treated by the RO unit. However, the results indicated that over 5 curies per year per unit would be released based upon the staff ,.(. Since this ( projected inputs to the floor drain treatment subsystem. 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 treat: rent subsystem. The applicant ,v had indicated in the FSAR that these evaporators would be availtble 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 from the SHHPP (' ' could satisfy the criterion of Section A.2 of the Annex to Appendix I.'
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l i, In its evaluation, the staff determined that adequate holdup and 11.1 processing time were available for the treatment of the floor drain wastes and the equipment drain wastes. ~ -The applicant assumed in his analysis that the wastes collected by ~ the secondary waste low conductivity holding tank would be processed The by an evaporator in addition to a mixed bed deriineralizer. staff's review of the applicant's descriptinn of this system in-dicated that these wastes would usually be treated only by a de- ,7 mineralizer. Therefore, in their analysis, the staff assumed the latter mode of treatment. The holdup time calculated by the staff for the treatment of the regenerative solutions from the condensate polishing system (input + to secondary waste high conductivity holding tank) was calculated to be less than 2 days. Since the secondary waste evaporator, which r 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 beccmes inoperable; no alternative treatment scheme ^ had to be considered in lieu of the evaporator even though less than 2 days holdup was available for treatment of the regenerants. h. ~ The staff assumed that chemical drain wastes from the chenical dra tank of Units 1 and 2 and the concentrate from the laundry and hot 'O9 t g
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E...-_.J _ __ j r --.- :- --- -. l i .lr 3 Q. shower RO unit wotfid be sent to the'R0 concentrates tank and treated l, 11~.1 The applicant by the RO concentrates evaporator prior to discharge. did not include this source in their evaluation of effluent release 2. ~ All detergents wastes were considered by the staff to be collected and treated by the laundry and hot shower RO unit and then discharged. Airborne effluents occur from. he building ventilation systems, from t the continuous and pre-entry containment purges, from the gaseous J ~ ~ wa'ste processing system (GUPS), the main condenser evacuation system, and the turbine gland steam condenser. All airborne effluehts except those released from the turbine gland steam condenser, the main con-denser mechanical vacuum pump, and the GWPS are passed through a HEPA ~ filter and' charcoal adsorber prior to discharge. 'The continuous con-taindent purge is filtered by a HEPA filter and charcoal adsorber in the airborne radioactivity removal system.(ARRS) inside the containment Additional information utilized by the staff in its estimate of air-Addi tional borne releases is provided in Tables 11.1-1 and 11.152. details on the liquid and gaseous radwaste systems are contained in Sections 11.2 and 11.3 of this SER. 5 The applicant is installing a fluidized bed dryer to process evap-orator concentrates (bottoms), and filter sludges for'the purpose 9
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= = m - The opera-c. of reducing the voluoe of solid radwaste shipped offsite. 11.1 tion of this volume reduction (VR) equipment will result in additional liquid and airborne effluents. Airborne effluents will result fera the VR system's offgas and will be discharged on a continuous basis while the s'ystem is operating. There are no liquid effluents which will be discharged directly off-site from the VR equipment operation. However,' based upon FSAR Figure 11.4.2-2, decontamination solutions, condensate frdm the scrubbers and leakage from ptrups, pipes, etc. v'.'ill 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 some will again be treated in the VR system. [' . N.,. Evaluation and Findings 11.1.2 stem In s not presented any detail on t VR sy\\ The appl n N I the volu'me o waste. ) parti lar, the a plicant has not addressedntity'of airbo\\. rne di o-to e handled by t VR system; (2) the q \\ tem; (3) the additiona ac ive effluents vel ased from the VR s t.. y lume of wastes to b treated by the iquid waste processing sy tem ,- i a s a result of operatie of the'VR ystem; and (4) the additional uliing from operation of the VR adioactive liquid effluents, 'O .7 Mystem. The staff has estimated the quantity of wastes to be treated by the The VR system and the ' radioactivity associated with these wastes. Jw
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l .j 11.1.2 staff has estimated the additional amount'of radiacetivity released as f. airborne effluents from the VR system and as liquid effluents from the liquid radwaste system. These releases were included with the releases ts
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presented in' Section 5 of the SHHPP E{4 eft Environmental Statemen ~ ' Tables 11.1-1 and 11.1.2 of this SER present assumptions.which werf l}n f O ptn. f m o utilized i,n the calculation of effluents resulting frem L., ... at. g s The applicant as not filed with the mmissio details on the VR / / sy m design an its interface wi various pla t systems such as C piecess and. efflue t montoring. uch infomation w 11 be required p11or to approval o the plant' radwaste VR system in i to .tye infomatio.n outli x ~ m O ..? g 'Q: .Ik.krij ,;;:Mu [4 TEN sueL. l a x,..,.-
l.. ( Principal parameters and conditions used in Table 11.1-1 releares of radioactive material in liauid and gaseous effluents from Shearon Harris Huclear ~ Power Plant 2S00 Reactor power level (tult) O.80 " Plant capacity factor _ 0.12% Failed fuel 5 Prinary system 6b 3 L o n'ra ga / n) 1.44 x 10 Shim bleed rate (gal / day) 100 Leakage to secondary system (1b/ day) 'b Leakage to containment building (1b/ day) 160 {eakage to auxiliary building (1b/ day) 2 Frequency of degassing for cold shutdowns (times /yr) 6.0 Letdown cation'.demineralizer flow (gal / min) 7 Secondary system 1.2 x 10 5 Steam flow rate (1b/hr) 1.01 x 103 Mass of liquid / steam generator (1b) 9.00 x 10 6 Mass of steam / steam generator (1b) 1.53xIQ Secondary coolant mass (1b) 1.7 x 10-Rate of steam leak:ca to turbige area (1b/hr) 6 x 2.3 x 10 ume (ft ) Containtient buildinc 4 Frecuency of contain?.-~ purges (time 5/yr) A 1730 Containment low voluTiT.: urge rate (ft*/ min) 10* Me~r cate (f t*/ min) Ccntainment ab.~ G re 16 Pre-purge cleanup time duration thr) Iodine partition factors (gas / liquid) 0.0075 Leakage to auxiliary builcing 1.0 Leakage to turbine area 0.15 Main condenser / air ejector (volatile species) Liouid radwaste system decontamination factors Boron Recycle Equipment Drain Secondary Easte Treatment High Conductivity System Sub-system System Material 10 5 10 5 Iodine 10 4 10 3 10
- Cesium, 2x10 5
4 Rubidium 4 10 10 Other 10 "This value is constant and corresponds to 0.12% of the operating power pr.oduct source term as given in HUREG-0017 ( April 1976). r.1 1%/ day of the primary coolant noble ga's inventory and 0.001%/ day of the prima b k '( 3 coolant iodine inventory. a .I ^ - ' - ~ ~ ~ u-w _,n_
~. Table 11.1-1 (continued) ~ q:~ Secondary Maste Low Laundry and Hot Shower Conductivity R.0. Concentrate Subsystem Subsystem Material 2 3 lodine 10 104 Cesium, rubidium 2 10 2 4 l Other 10 10 Liquid Waste Inouts Proce Flow Rate Fraction Fraction Collection Time Stream _ (gal / day) of PCA Discharged time (days) (days Shimsleed Rate (BR5) 1440 1.0 0.1 Z3.3 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 Bloudoun 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 (.. Low Conductivity Holding Tank 19000 8.7x10~6 1.0 0.47 0.13 Source of Volume Reduction System Wastes Volume / Yeas / Unit 1. Evaporator Bottoms 3 (a) Recycle Evaporator 1,025 f (b) Waste Evaporator 960 f (c) Secondary Waste Evaporator 4,675 ft 3 l (d). R0 Concentrate 876 ft 4. Tii1.er 5iuose iY Gaseous !!aste Inputs There is continuous low volume purge of volume control tank l Holdup time for xenon (days) 70 Holdup time for Krypton (days) 70 L Fill time of decay tanks (days) 35 t G:C ~ i ras i imin
22 - \\[ 11.2 Liquid Radwaste Sistem ~ 11.2.1 Summary Decription The liquid waste processing system (LWPS) at the SH!.'PP consists of process equipment and in.strumentation necessary to collect, process, monitor, an'd 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 liquid waste is processed on a batch basis to pemit optimum control of releases. Before liquid waste is released, samples are a 11yzed to detemine the types and amounts of radioactivity present. Based on the results of the analysis and the waste treatment " system V[', utilized, the waste may be recycled for eventual reuse in the plant, retained for further processing, or released to the envirottient under controlled conditions. A radiation monitor in the discitarge.line from the various discharge tanks will automatically ter.:linate liquid waste discharges if radiation measurements exceed a predetemined level. An alarm will be simultaneously actuated in Units 1 and 2's control room, in the WPB control room and the Health Physics control to o". ). The LWPS at the SHHPP is composed of the following subsystems: (1) the equipment drain treatment; (2) the floor drain treatment; (3) the laundry and hot shower treatment; and }. ( (4) the secondary waste treatent. 9 h~^- ~. F'JD" N,P - M .. Ge* **
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C. ( 11.2.1 The SHh?P% 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 r,eactor grade stream consists of tritiated waste collected in the eciuipment drains. This streah is treated by the equipment drain treatment subsystem. The nonrecyclable equipment stream cEnsists of nonreactor grade water sources and is collected and processed through either the floor drain treatment subsystem or -the' laundry and hot shower treatment subsystem. The secondary waste ~ stream consists of regenerant solutions from the condensate polishing 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 between the two units at the SHL7P. There are two floor drain treatment subsystems and two secondary waste treatment subsystens shared between the two units. All other shared systens are single subsystems. All releases are inonitored before discharge to the cooling tower blowdown. The discharge valve is interlocked with a process radiation monitor and will close automatically if the radioactivity in the liquid should exceed a predetemined limit or if the"Ililution flow afforded by the cooling tower blowdown falls below a preset value., Additional details on the liquid,radwaste treatment system folicy. N O ~'
C,. ~ ^ 11.2.1 The equipnent drai-n traatnent subsy5 tem colle'ets reactor grade water from eouipment leaks and drains, valve leakoffs, pump seal le'akoffs, tritiated water sources and tank overflows. These wastes are collected in the waste ' holdup tank and then processed via filtration D and evaporation. After processing, these wastes,are either sent to the reactor makeup water storage tanks or to the waste monitor tank l for discharge or to the waste holdap tank for additional treatment. The floor drain treatment subsystem collect's and processes water from I-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 the hot shop. The waste is collected in the floor drain tank and 't processed by filtration and treatment in,,t,he floor drain treatment subsystem reverse osmosis (RO) unit and then collected in 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 equipment drain treatment subsystem, or pumped directly to the waste processing system (WPS) waste evaporator for treatment. The latter rcute will be utilized when radioactivity levels are such that filtration and reverse osmosis are insufficient to reduce the radioactivity to .. r acceptable levels. ^ -N - = h--
y._.{' _. ~ 11.2.1 The laundry and hot shower treatment subsystem collects, in the laundr hot shower tank, detergent waste from the WPB, the FHB and the hot s The applicant expects this waste to be of a quality such that treatmente for removal of radioactivity will not normally be required.
- However, if analysis indicates that treatment is required it will be routed to
.the laundry and hot shower RO unit. The permette frm the RO unit will be passed through a demineralizer and then routed to the treated laundry and hot shower tank. The contents of this tank can be recycled for further treatment or discharged via cooling tower blowdown or pumped to the condensate storage tank. The secondary waste treatment subsystem is designed to treat wastes generated from secondary systems. This water wil.1 contain radio-activity only if primary to secondary leakage occurs in,the steam generators. The secondary waste treatment subsystem consists of one subsystem to treat high conductivity wastes and one to, treat low conductivity wastes. Low conductivity was'tes such as the backflush from the electrmagnetic i filters of the steam generator blowdosn 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 ~ .. r through a demineralizer and then collected in the secondary waste sample tanks. From the secondary waste sample tanks the' water is *
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either recycled to the condensate stoiage tank, discharged to the k, 11.2.1 cooling tower blowdown or to the neutralization basin or recycled back to the low conductivity holding tanks. The main. sourbe of high co.nductivity was.tes is the re.generant ~ Tnis waste is solutions from the condrnsate polishing system. ~ collected in the high conductivity holding tank, processed by an evaporator and the evaporator distillate discharged to the low. i From the conductivity system upstream of 1;he demineralizer. t demineralizer, treatment is the same as for the low conductivity subsystem. Turbine building equipment drains and curbed area oil equ'ipme floor drains below the operating deck are collected in the industr '~/ Drains below grcund elevation ~ '~ waste sumps of the turbine building. s ~ areicilected in a condensate pump area. sump. This sump and th ~ The dustrial was'te sumps discharge through a radiation monitor. contents of these sumps will normally go to a yard cil separato If the monitor detects hsetr ,? *' then to th( cooling tower blowdown. g k'; s.adisadan in the discharge from one of these pumps, the discharge "c ec., p,'v will be directed to the low conductivi.ty holding tsnk for treatment. .4. The secondary waste subsystem also collects 1) the wgites from
- s a-chemical drain tank which are not sent to the solid waste proce d wastes from he
, system for solidification, and 2) the concentrate
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waste evsporator, the reverse osmosis units, and the secondary waste 11.2.1 These wastes are collected in the RO concentrate tank ~ ~ evaporator. ~~ The distillate from are p'rocessed in the RO concentrate evaporator. ~ this evaporator goes to the treated laundry and hot shower storage The evaporatcr concentrate goes to the waste 1 tark for discharge. evaporato'r concentrate tank for solidification or for treatment in The liquid waste system consists of a the volume reduction system. number of cross-ties which allows alternative treatment schemes '~ ~ ~ those discussed above. Further detail on the liquid waste system and these treatment schemes is provided in Section 11.2 of the SHt!PP FSAR. 11.2.2 Evaluation and Findings (, The LWPS system was reviewed with respect to the Acceptance Criteria - The staff's r'eview con-of Standard Review Plan 11.2, NUREG-0800. sidered the capability of the proposed LWPS to meet the anticipated demands of the plant due to anticipated operational oc'currences. The potential consequences resulting from reactor operation have also been considered and the staff has determined the concentrati radioactive materials in liquid effluents in unrestricted areas to be h small fraction of the limits in Table II, Column 2 of Appendix B to 10 CFR Part-20. .~' O ~ i. ee y - '.,g T h 3;;.A ga.n WL - x~
28 - ~ .c. g. ,m. 11.2.2 The staff has also considered the pot'ential ~ consequences resulting b from reactor operation with 17. of the cperating fission product in-ventory in,the core being released to the primari coolant and has detemined that the concentrations of radioactive materials in liquid ~ effluents in unrestricted' areas will be a small fract' ion of the limits of Table 2, Column 2 of Appendix B to 10 CFR Part 20. As diccussed in Section 11.1 of this SER, the staff calculated liquid effluents [ using the GALE computer program based upon the treatment systems for liquid effluents described above. These source tems were presented fn Appendix D of the SHNPP DES. 1 The staff calculated the doses to offsite individuals uti.lizing the methodology of. Regulatory Guide 1.109 and the liquid dispersion f parameters calculated in accordance with. Regulatory Guide 1.113, s_ " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I",. The staff has detern.ined that the proposed liquid radwaste' treatment systems are capable of maintaining releases of radioactive materials in liquid ef fluents such that the calculated individual doses in an unrestricted area from all pathways of exposure are less than 3 mrem c.- to the total body and 10 mrem to any organ. The staff has calculated, as noted in Section 11.1, t'he 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 reactoE x 5 - e b?M Wi.w e i Yebb-
11.5.2 and the annual dose to any organ of an individual in an unrestricted ars.:: to be less than 5 millirem per year total from both reactors. Therefore, in accordance with the option to Section II.D of Appendix ! 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 SHHPP DES presents a comparison of the RM 50-2 and Appendix I design objective doses with the doses calculated for the liquid scurce tems and a comparison of the RM 50-2 curie limitation with the projected releases,for the SHHPP. The design of the liquid radwaste system presented in Oe FSAR is ~ different from that which was proposed at the Construction Pemit ~ (CP) stage. At the CP stage the steam generator blowdown liquid vias to be discharged. Although no process treatment 'sys. tem was proposed, [.' the applicant made 5 commitment to install equipment capable of re-k ducing the level of activity in the blowdown stream by a fac, tor of 3000 or greater. The applicant has since decided to install an i.,:. L electromagnetic filter to remove magnetite and other spinel type. ~.. r oxides which are magnetic and to remove a portion of the nonmagnetic particulates. The filter is flushed and the water is collected in ~ the settling tank. The flush water is then pumped to the second'ary .Qf -9 s -l d
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30 - ~ ' ' ~ (, r. waste low conductivity holding tank's7 The steam, generator blowdown '11.2.2 The con-passes from the electromagnetic filter to the condenser. densate polishing system provides some removal capability for radionuclides.. The staff has assessed the overall capability of the radwaste systems to process waste in the event of a single major equipment failure by a comparison of the design flows to the potentia 1' process routes and equipment capacities. Based upon this review, the staff has determined ~ I that the radwaste system will be adequate to process wastes. The staff has considerad the capabilities of the proposed, liquid rad-waste treatment system to meet the anticipated demands of the plant due to anticipated operational occurrences and have concluded that the system capacity and design flexibility are adequate to meet the anti-cipated needs of the plant. The staff has reviewed the applicant's quality assurance provisions for the li id radwaste systems, the quality group classifications uset 2 for system components, ard the seismic design applied to structures f' The design of the systems and structures housi-hovsing these systems. these systems meet the criteria as set forth in Regulatory Guide 1.143 j- .. r 1-8 (, L L 2j: f. L.a Wn g,.ri, -m_ ______________________-_y__. q -____g___.___ ~
j ~ 11.2.2 The staff has reviewed the provisions in:orporated in the applicant's design to control the release of radioactive materials in liquids due. to inadvertent tank overflows and conclude that the measu'res proposed ~ by the applicant are consistent with the criteria as set forth in Regulatory Guide 1.143. Hota noted i Sections 11.1 and 11.4 of this SER, appi cant has et provided ufficient detail on the VR syst to allow he staff f to assess the e ability of the liquid radw te system to ocess 1 the additional li uid waste generated by ' e VR system or t ~ effluents resulting from this processing Lntil such'infoma ion / is presented, the SHN cannot be judg as +.o : : ~.ampliance 'th Appendix I. This sectio of the SE as been'de .d as,suming t the plant will meet Appendix 9 ~ e ,, 7 (. ~ $; Ji .n. ~ qv.:.;... r.
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l .,(.,.. ,e. ; Table 11.2-1 Design parameters of principal components considered in the calculation of liquid effluents from SHNPP, Units 152 Component Capaci ty Safety Number (each) Class Boron Recycle System Recycle Evaporator Feed Demineralizer 3 Recycle Evaporator Feed Filter 2 30 ft 3 Recycle Holdup Tank 2 150 gpm 3 Recycle Evaporator Feed Pump 2 84,000 gal 3 Regycle Package 2 30 gpm 3 ~~ Recycle Evaporator Concentrate Filter 2 15 gpm 3 & NN: Recycle Evapora'ar Condensate Demineralizer 2 35 gp NHS 20 ftg Recycle Evaporator Condensate Filtse 2 Recycle Monitor Tank 2 35 gpm Recycle Monitor Tank Pump 2 10,800 gal 2 30 gpm Equipment Drain Treatment System ? Reactor Coolant Drain Tank d
- Reactor Coolant Drain Tank Pump 2
350 gal P.eactor Coolant Drain Tank Pump Heat Exchanger 4 100 gpm Waste Holdup Tank 2 Waste Evaporator Feed Pump _1 25.000 gal Waste Evaporator Feed Filter 1 35 gpm Waste Evap:rator Package 1 35 gpm Waste Evaporator Condensate Deminera?.izer 2 15 gpm Waste Evaporator Coadensate Tank Filter 1 35 gpm Waste Evaporator Condensate Tank 1 35 gpm Waste Evaporator C:m.densate. Tank Pump 2 10,000 gal Waste Evaporator C mcentrate Tank 2 35 gpm Maste Evar:rator Concentrate Tank Pump 1 5,000 gal 2 35 gpm Floor Drain Treatment System Floor Drain Tank Floor Drain Tank Pump 4 25,000 gal Floor Drain Tank Filter 4 35 gpm Floor Drain Rever.ec> Osmosis Unit 4 35 gpm ~ Floor Drain Deverse Osmosis Feed Pump
- 2 30 gpm Waste Monitor Tanks 2
30 gpm Waste Monitor Tanks Demineralizer 2 25,0g0 gal Waste Monitor Tanks Pump 1 50 ft (30gpmf
- Chemical Drairi Tank 2
35 gpm !. Chemical Drain Tank Pump 2' 35 gpm 2 600 gal - e ,e $:-[ hb M-***
m ~. ~ C. Table 11.2-1 (Continued) Laundry and Hot Shower Treatment System ~ ~ Laundry and Hot shower Tank 2 25,000 gal Laundry and Hot Shower Tank Pump 2 35 gpm Laundry and Hot Shower Tank Filter 2 ,35 gpm ~- Laundry and Het Shower Reverse Osmosis Unit 1 30 gpm Laundry and Hot Shower Reverse Osmosis Feed Pump 1-j0 gpm (30gpm) Laundry and Hot Shower Demineralizer 1 50 ft Treated Laundry and Hot Shower Tank ?. 25,000 gal Treated Laundry and Hot Shower Tank Pump 2 100 gpm Reverse Osmosis Concentrate Tank 2 5,000 gal Reverse-Osmosis Concentrate Evaporator Feed Pump 2 35 gpm Reversi Osmosis Concentrate Package 2 10 gpm Reverse Osmosis Concentrate Evaporator 2 20 gpm Distillate Pump Secondary Waste Treatment System ~ Low conductivity Holding Tank 3 15,000 gal Low Conductivity Holding Ta,k Pump 2 100 gpm (-(,- Secondary Maste Filter 2, 100 gp-Secondary Waste Demineralizer 2 70 fr. 1 25,000 gal A Sec'ondary Waste Sample Tank ~ Secondary Vaste Sample Tank Pump 2 100 gpm High Conductivity Holding Tank i 15,000 gal High Conductivite Holding Tank Pump 2 35 gpm Secondary Waste Evaporator Package 2 15 gpm Secondary Waste Evaporator Concentrate Tank 2 4,000 gal Secondary Waste Evaporator Concentrate Tank Fump 2 35 spm + e
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.,e. -r ~ ) ~W~ 11.3 ~~ Gaseous Waste 14anagement System ~~' 11.3.1 Summan Description The gaseous waste management systems at the SHHPP' include systems which treat the normal ventilation exhausts; the exhaust from the main condenser mechanical iracuum pumps, and the gaseods wastes associated with degassing primary coolant, purging the volume control tank, dis' placing cover gases, purging of equipment, gas sampling analysis 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 with each system. Additional details are provided in Section 9.4 of the FSAR. If a generalization can be made of the normal ventilation exhaust ( treatment systems at the SHNPP, it is that the exhausts usually flow through a medium efficiency filter, a HEPA filter, and a charcoal adsorDer. i The RAB normal ventilation system (RABNVS) filters air from the con-tinuous con'ainment purge exhaust and areas from the RAB which contain equipment essential for the safe shutdovm of the reactors including . CYCS chiller area, 480 V auxiliary bus area, areas containing non-l l ' essential equipment etc. This system exhausts to the vent stack on the roof of the RAB. .e L. 1
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C,,~. ~ li.3.1 The waste processing arsas filtered exhaust system exhausts ir frc the contaminated areas of the WPB and discharges to a vent s ack or the roof of the WPB. The WPB laboratory areas fume hood ex5 usts a e filtered except for the perchloric acid exhaust. This exhat t is discharged ilnfiltered to the vent stack on the roof of the i B. The air from the contaminated spaces of the condensate poli: dng demineralizer area is exhausted through the coc.densate poli: dng ~ ~ demineralizer area filtered exhaust system. The exhaust is lis-charged from the vent stack located on each unit's turbine ' aildin. The condenser vacuum pump effluent treatment system was pre iously discussed in Section 10.4.2 of the SER. x The containment pre-entry purge is filtered by the containm nt pre entry purge system. The purge is discharged to the RAB ver stack Additional details of the nomal ventilation sy::tems are pr vided n Section 9.4 of the FSAR. The gaseous waste processing system (GWPS) processes gase-ollect d from the volume control tank and vent connections from the ecycle evaporator gas stripper, the reactor coolant drain tank, ti - prcssurizer relief tank and the recycle holdup tanks., The iWPS i shared between the two units and consists of two waste gas :ompre ; ors, .g a b %e g s.o - ~ - - _,n ~~ ._-__--___=_____.__e?-
36 - C.. .:.: ~. 11.3.1 two catalytic hydrogen recombiners and ten waste gas decay tanks to accumulate the fission product gases. Eight gas decay tanks are usec during normal operation and two are used for shutdown and startup. Nitrogen with entrained fission gases will be continuously circulated around the GWPS by one of the two waste gas compressors.' Fresh hydrogen gas is charged to the volume control tank wtiere it is mixed with fission gases which have been stripped frcm the reactor coolant. .into the volume control tank gas space. The contaminated hydrogen gas is continuously vented from the volume control 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 recombiner where de re-combiner converts the hydrogen to a water vapor by oxida' tion. After _ renoval of the. vapor-the resulting gas stream is circulated to a waste gas decay tank and then back to the compressor. Each gas decay tank is valved into the GWPS recirculation' loop for one.or a two days.
- k., ;
,1 Continued plant operation results in the buildup of pressure in the ) waste gas decay tank due to the accumlation of non-removable fission L.../. gases. When the pressure in the gas decay tanks reaches 25 psig the alignment of the GUPS must be changed due to the. design of the .S> \\ L. der n :, '3 ]'h;y :: t );gik.'.; whi r FgaAl, ~ ~ ~ .. = _ _ _
~ ~ 1 ]U The riew alignment has flow from the cmpressor to the 11.3.1 recombiner. 5 gas decay tanks to the recombiner and then back to the compressor. This alignment is suitable for operation up to 100 psig. The Gk'PS has analyzers tb monitor oxygen concentrations bet >reen the oxygen supply and the hydrogen recombiner package 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. 11.3.2 Evaluation Findings -s The gaseous waste manager.ent rystem was reviewed with respect to the Acceptance Critaria of SRP 11.3, HUREG-0800. At the construction pemit stage the off-gar from' the condenser air ejectors was untreated and the ventilations systens were only filtered by HEPA filters except for the exhaust from the WPB,which The staff stated in the was also filtered by a charcoal adsorber. SER for the CP that treatment of the main condenser December 22, 1972 t of f-gas would be required to reduce this potential source of iodine-131 to the atmosphere to bring the offsite doses into compliance w.ith e 9m s 34, ..;t. q j l .-qm
, - 38 .~ ~ '. The applicant has added the condenser effluent treatment 11.3.2 Appendix I. system, which can be utilized durin_g 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 additions decrease the quantity of iodine' released from areas. the SHNPP and are 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 ~ ~ 7 condenser effluent because the condenser effluent treatment system wi' not be d ized on a routine basis. t. The staff has calculated the doses to offsite individuals utilizing i the methodology of Regulatory Guido 1.109 and the atmospheric dis- "7 ( persion parameters calculated in accordance with Regulatory g Guide 1.111, " Methods for Estinating Atmospheric Transport and Dispersian of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors". The staff has detemined that the proposed gaseou radwaste t-c.atment systems are capable of maintaining releases of w.. radioactive-materials in gaseous effluents such that the calculated ind.ividual doses in an unrestricted area from all pathways of expo-v. sure are less than 5 mrem to.the total body and 15 mrem to any orgar w-from noble gases and that releases of radioiodine and radioactive material in particulate fem result in doses which are less than
- 15 mrem to any organ.
~ fj ^ G. ,) .k h mim (*.Na$.*' t ' - ~~ .._......,.T
_ 39 = = ~ ~. j -p The staff has also considered the potential effectiveness of aug-v' 11.3.2 menting the proposed gaseous radwaste treatment systems using item The applicant has chosen
- f.
of reasonably demonstrated technology. to show compliance with Section II.D of Appendix I to 10 CFR Part 5 by complying with the Annex to Appendix I (PM 50-2). Th,e SHNP -41Rr presents a comparison of the doses and releases calculat FES The SHHPP with the design objectives of Appendix 1 and PJ4 50-2. i bjectives , applicant's proposed design complies with the des gn o Therefors, we have detemined that no further effluent - of RM 50-2. treatment equipment will reduce the cumulative population doses within a 50 =tle radius in a cost effective manner. The staff has also considered the potential consequences resulting ? 3, -[ from reactor operation with 1". of the operating fission, product inventory in the core beingJeleased to the primary coolant.and ~ has detemined that the concen'trations of radioactive m in gaseous effluents in unrestricted araas will be a small fraction I 4 or the limits of Table 2, Column 1 of 10 CFR Part 26. l n: i (. +,.,' The capability of the proposed gaseous radwaste treatment 'sy, ste s + meet the anticipated demands of the plant due to operational occur-r [ rences was also considered and it was concluded that the system .. t C'! capacity and design flexibility is adequate to m,et the anticipat e l .needs of the station. i. 4 I .s*~ m.Q ?. 4 hG h.;,2..,~~*%*p $ ' ' w
~ -,. = Y 11.3.2 The applicant's q'ality assurance privisions for the gaseous radwaste u systems, the quality group classifications used for system components, the seismic design applied to the system and the structures housing the radwaste systems were also reviewed. The design of the systems and the structures housing these systems meet the criteria set forth 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- . pressors and the gas decay tanks. Such an analyzer is required in accordance with the Acceptance Criteria of SRP 11.3. Dual analyzers are required. ( The staff has reviewed the nomal ventilatior system's desigr., testing V 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. The'Ip ic-kthasnotindicated hether Sere are ruptu e di s in 4 iPS itself an\\d if there are iquid seals wnstream o the ru ture V \\ 0-)p(f discs, and whethe,r they arg designed such tha an ex osion will t cause the pemanent'ioss / \\ of the seals. V .. r The above infomation is required, along with a,ccmmitment to install dual analyzers, before the GWPS can be judged to be acceptab7e. ~ Q. m - we w w w
\\ - ~ _ 41 ~ _. (- li V, note As noted Sections 11.1 a d 11.4 of this SER, the applic . has not provide sufficient detail on the VR system to allow tha aff to \\ dete ne the effluents whichi 11 result from the ope ion of the VR s stem. ijntil such infoma n is presented, the IP,P cannot be udged as to its compliance w Appendix I. Th s section of the SE,has been drafted assuming that he infomation be provided w< 1 not negate the conclusion expre ed in this ction that the ' S'NPP will meet the design ob,iectives Append I. 11.4 Solid Waste Management Systems 11.4.1
System Description
The solid waste processing system (SWPS) is designed to process two general types of solid wastes: " wet" solid wastes and "d7" solid n wastes. Wet solid wastes consist mainly of spent filter cartridges, demineralizer resins, filter sludges, chemical drain solutions and evaporator bottoms which contain radioactive materials removed from liquid streams during processing. Dry solid wastes consist mainly of ventilation air filtering media (HEPA, charcoal), contaminated ( clothing, paper, rags, laboratnry glassware, and tools. )^_' -{ The spent filters associated with the various ventilation systems will be removed from the filter housing, wrapped, and packaged for disposal using a hydraulic compactor. The filter sludges from the liquid rad- }- -(Q W ,n.m; E"d - --r
- .L X
\\ t [ '~~.' T~ ~ Table 11.3-1 ; Normal ventilation system components at the i Shearon Harris Nuclear Power Plant Medium e Demister Heater Filter HEPA Charcoal HEPA RAB Normal Ventilation System ~ X X" X WP Areas Filtered Exhaust X X X System WPG Laboratory Fume Hood X X Exhaust (except perchlorite) - Condensate Polishing Demineral-X X X irer Area Filtered Exhaust System Condenser Vacuum Ef fluent X X X X X X Treatment System * ,( Continuous Containment Purge X X X (Passes through RAB Normal Ventilation System and Air-borne Radioactivity Removal System) Containment Pre-entry Purge X X X System " System will.not be used to filter releases on a routiune basis. Credit was not given in the Appendix I evaluation. ? ( x. i: b ~~ i ~~ ~ ~ ~ ~ -
- A3 ~
7
- . -(
11.4.1 waste systems will be backwashed to a WPB filter backwash storage tank t l: and to the WPB particulate ccncentrate tank. These sludges may then I ', be solidified or sent to the volume reduction system. Spent resins 'will be dewatered and then solidified by cement. In lieu ~ 'of solidification, the resins may be shipped dewatered in high integri containers. Evaporator bottoms will be processed in the volume reduc-tion system. Ch'emical drain solutions will be solidified. Ccmpressible low-activity solid waste will be cunpacted in SS-gallon drums. The conpactor is equipped with a hood, ventilation fan and HEPA filter. The displaced air will be vented through the HEPA filter The applicant has indicated that the SWPS has a storage area capable ' ~ .f of storing 1020 drums. The applicant has also' indicated,that the SWP! v I teets the criteria of ETSB 11-1 Rev. I which is the equivalent to Regulatory Guide 1.143. l The applicant 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 4'9 CFR 173. ~ Additional infomation, with respect to the solid radwaste system, is I .. r contained in Section 11.4 of the FSAR. L y - d A + #ya" 6 1 : L 4 gas s "Pf - (% ns ~
- [f 1% J L5, m. vh~ ^ fff"4
$;...,hh Sp&- f e ;LM.~Rs',.'h j D 'd~)d~ ' 2" 32 1
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Q$yr,e:h,,'._.$ 11/,l u tJ e-f 6 4, f's '. c = e -- - - = -. - -. -
44 y. x. 11.4.2 Evaluation and Findings ~i'. ( The staff has reviewed the SWPS in accordance with the acceptance - e' criteria of SP.P 11.4, NUREG-0800. The scope of thi 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 rev.iewed. The capability of the proposed system to process.the types and volumes of wastes expected during ~ nomal operation and anticipated operational occurrencer in' accord-ance with General Design Criterion 60, and provisions for the handling of wastes relativa to the requirements of 10 CFR Parts 20 and 71 and applicable DC .gulations have also been reviewed. The staff will not approve the design of the solid radwaste system until the apolicant provides infomation detailing the manner in which various waste ccmponents are treated. Infomation which is m. missing includes' (G i d fireu us.w. ; dwn vi e vuiuae repuction 5 j hd+ M .k., ' N, .syt t
- i. ouui...u.
- (a) ho the s tem operates; (b) expect input stream thei volumes, and as3ociated ac vi ties. (c) iquid and gas s effluents resul ng from system operation s ,.7 x ;f, ; r. ..,e.. ~ =+ imm .. _ - -., -. _.,. _,.,., _ _.,. ~.. _.. -.... ". " _.,
s ~ 11.4.2 (d) volume reducti factors achpec; (e) activity sociated wi he disposable ash; and ~ (.f) confo iance with Regu atory Guides 8.8,1.140, and 1.143, - ~ t/ e..... and BTP CMEB 9.5-f of SRP 9.5.1; '2) a rawing (CAR-E ) which d h'e i ce header and ' e was'e concentrate i itment to a p gr whereby the prese e of ree water i the L was contain is verifi and commi.ent to reprog the p contain w en free water is ered; Y fsI-)'Mr S Yb*. j ,?, A eser ption of the &l" :9 t 3Am; lP ^ ~ ' C/hfreme tv sRt II4 5 I t! pd g s details on the manner in which the filter sludge from t[ ~ following filters will be handled /rud Assis t rM #"*"'N I (a) reactor coolant;[ (b) seal water injection (c) seal water return; M (d) boric acid; BRS recycle evaporator feed; fu. x (e) 2 (f) BRS recycle evaporator conhentrate; [d ~ ~' ~ ,r,,,___ ey eas fn.a a wC y ,ae t ) recycle eV!porater Condensate; wr g 5 e g a? cOnwwM1;.;t C nd j
- n..xy. -
w am a~ ]'fI' 1 l + e d' ' ;._ -i --I ..... s 0,% ; '.. m.+.. _____m
~ N Ipfmuhn , det "; :hwir.g.that the vent exhaust from the spent' resin' T'.' [ ~ 11.4.2 storage tanks and the decanting tanks are filtered by a HEPA filter in accordance utth BTP ETSB 11-3 of SRP 11.4. ates cated that heat tracing from the,conce J The applican as n line of t e recycle evap rator to the boric acid tank is,at required acid solution will not cry tallize at the 4% weight bori becaus a 12% weight solution s required before r
- j ambie t temperatures and tha e staff's position s that a 4% by 11iration will occur.
~' ~
- . cry 0
56-57 F. Therefore, we ght solution of boric acid m 1 crystallize a the conce trates line of the h at tracing should be included fr mycle evaporator to the boric acid ta r ( Until the above infomation is provided the SWPS will be conside , i,. i (. unacceptable. The applicant has not provided the Process Control Program (P The PCP is not required until 6 months prior to the issuance of the The PCP will be judged as to its acceptability Operating License. when it is submitted. ' 7-Process and Effluent Radiological tionitoring and Sacpling Systens [~ 11.5 11.5.1 Summary Description The process and effluent radiciogical monitoring and sampling c systens are designed to provide infomation concerning radi I y. 4 9 k 9 n .. $sni M. 4m..: a e.Uwe qs 3.,
~ ~ INSERT 3 rr K The applicant has indicated that portions of the reactor auxiliary building, with piping systems which could contain stagnant boric acid solutions are arc equipped with space heaters orfp4 heat traced to maintain temperatures E 70 F during operating modes 1-5. The applicant did~not specify.what means are being utilized for the concentrates line of the recycle evaporator to the boric acid tank. It is the staff's position that boric acid solutions should be maintainet Crystalization at 2 70 F for all modes of operation not just modes 1-5. ~ In addition, the applicant would not be a function of the operating mode. did not specify what means were utilized to etsure that the piping systems are maintained at 2 70 F for those portions of the reactor auxiliary building Some automatic means should be available to which utilize space heaters. Therefore, it is start the heaters when the temperature approaches 70 F. the staff's position that the applicant should specify what parameters are monitored to result in autome. tic initiation of these heaters. e i 9 9 o- .; - R. ,,..E,.., ', 1.
- g.n
. z u..i ---n 47 3 levels in systems throughout the plant,-indicate radioactive leakage r [- 11.5.1 I. between systems, monitor equipment and performance, and monitor and centrol radioactivity levels in plant discharges to the environs. At the SHNPP, the airborne effluent sampling and monitoring systems For .are (ocated in the plant vents located on the RAB and the.WPB. liquid eff}uents, the effluent monitor locations are downstream of ~ the pumps of the LWPS waste monitor tanks, the treated laundry and Effluent ' ~ - }-hot. shower tanks, and the secondary waste sample ~ tanks. r monitors are also located to monitor the industrial waste sumps of the turbine buildings, the discharge from the tank area drain transfer pumps and the service water system. Table 11.5-1 contains a listing of both the process and ef. fluent This 1601 oiw includes monitors for airborne and liquid sources. Eirborne effluents, the type the type of radioactiytty moniwred u. ~ 1 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 monitoring system. ,p' 11.5.2 Evaluation and Findings The staff has reviewed the process and effluen't nonitoring system with c respect to the Acceptance Criteria of SRP 11.5, NUREG-0800.As a f result of this review, the following evaluation and findings have been made. e ne I y~ g, a.w 5,bdh 4 N55N g ,b
.~ , ~ Acceptance Criteria II.C.1.a of SRP 11.5 states that the gaseous o l'. 11.5.2 and liquid process streams and effluent release points should be monitored and sampled according to Tables 1 and 2 'of SRP 11.5. Information provided in Section 11.5 of the FSAR indicated that the SHNPP did not meet these criteria in the following' areas: The turbine gland seal condenser exhaust and the mec'hanical (1) vacuum pump exhaust are not monitored and sampled in accord-ance with Table 1. The condenser vacuum pump effluent is not sampled in accord-(2) ance with Table 1. There is no effluent monitor for the turbine building vents (3) (release points 3A and 3B) as required by Table 1 and' sampling provisions are not provided. m A [; V n im a..
- m. th:-
- 44) -Ttitrapplican has provided contracic ry i m r
continuou containment inment pr -entry purge and th con p [ge monitorin features of the HHPP. The s aff's positi n that both line 'shall be mo tored on a coat us ba s and fh IShat be 5 nonitors Q1, o high radiation signal, isolate e .;) purge operation in an automatic fashion. ' ^ . (5 he servi wa r syste does not pas ss th capab i.g g & ,~a ob ain continuo ample as re., red by Tabi The applicant has indicated, in response to a staff question, that process and effluent monitoring ~ program will meet the gui hY-N* lu ~.3 a L[ g k " T "y V; n n 3 pw n pJ.a hi-yTr fj'k-f'~f~ ~ Lu,2.wex~ 6M Qt; .md i ~- i__ - _ _ rn.n 7 r.._., _. _ _,, _ ]
... =-.= - ' j', y ~ ~ '^ ~ e eption. This e ep-(.: Position C of Regulatory Guide 4.15p4 .m ~ 11.5.2 tion is that e SHNPP will ke use of "n ionally reccgni d stand-S traceable s 4dsrds only. ards" and 111 not limi .hemselves to It is e staff's po tion-that any nationally re gnized standard" wil be ISS trac le. Therefo , the staff do s not accept this pro- / E osed de iat n to Positionf of RegulatoryAuide 4.15s 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 ^ o Regulatory Guide 1.97. e applicant has addressed items II.F.1, Attachments 1 and 2 of NUREG-0737 which covers similar criteria fo d uida 1.97.Vl.Nowever,4,u T 1 a effluent monitors to that proposed by Regulatory t " app icant has addr e uch of t ' foma. tion required by 1.F., ',' A tach ts 1 and 2. The applicant h not add ced the l fo11owing items f Attachment 1: (a monitoring lo tion or points of ampling; (t ) instrumentatio r main ste safety and pressure relief yalve /' pL !" discharge; h est4 t and (d (e) ca ilitf7f-perfo'rmi
- w fh3per_t 6TtucTment 2, the applicant has not addressed:
capabiljdprqidMempl%3, [ W .h. k m. p ,= y4.. en ___-_____________-:-~~. - _j
= -.. - _ - _ _ _ ~ ~ ~ D4 SERT A ) j& luddthattheh Based upon thegan" ~.h. 6 c-ps.MLL, lUb fun-pnnS. -^ the staff hasn W. h.c hwc4,ae. b a, idt~y effluent reiease points,3A and 3B should be the points.of monitoring and ~ j This change would (1) result nothfhecondenservacuumpumpeffluentalone. ~ in the moni.toring of'a. potential effluent release source (condensateib 9 te'M w g M n esclut.u b y polishing cubicles {, (2) allow isokinetic samples to be taken, and (3) minimize the potential damage of high humidity air on the rampler's b charcoal adsorber. T 46 g s g. The applicant has proposed a method for determining the release of radio-activity from the safety relief valves and the atmospheric steam dump The vales which is similar to that proposed for the Waterford Plant. Based upon the determination staff is assessing this method at this time. 7 (' made in the Waterford review, the acceptability of 'the method proposed fo:- Shearon Harris will be the same. o + }. 1 ;: n a .x b i* &rw,.9 ski
___2__
f } LL' &l. W.v
- ~
~ G- &. r j _ a W ,pLLr8 W _- h. ~. f2f G. n. capability of the on-site Tabor'atory to analyze or measure 11.5.2 (q,4, i these sampless and (d) isions for limi g occu tional dose * { analys s of sar. es._ ,r4 p 4),J)q The applicant can not assure representative samples framive. ;wn r:dic::ti!: pre ::: ;tc.m: :nd t:" tentent: because the capacity of the recirculation pumpg do not meet the criteria of II.2.a of SP.P 11.5. Th,e pisaps which do not comply are the owi ng: w (a waste holdup tank; s. (b) was evaporato ondensate tank; (c) waste mon r tanks; (d) rec e holdt p k; ( ( recycle monitor holdup ' nk. -IT.
- pe":" +^ * *** " q" :ti n, th a ;.'.i Ct Ctit?' t'"'t t: 'MVe y
pu.pa wou s o operate ar. i un out -ad *b"e naa+ arcaa- : :c .. i o ui i l'.7.s UT 5KY L1.3. It is Our pus i il^.;n tha-C.a pa.e.,
- ald.et he Tv. th: ;;ri:d J tic.; c:g!'-^d +n Operai.ed a1.
,..e run vaw uunuivivu
- r +a*4 a.
Furthernora. tha e+n## #4at 't 4 'meei Lid 3 a.vep$cnwa di ffitu t t to env ) s_to.n m-;4uu vpe i a u rs Usi ng woese pumps a t the _ i.. <fc ba 7 . ur-cut ::ndi-t4sn. gBe applicant should propose. an alternative .? means of ensuring that the contents of the various liquid waste may be sampled in a represantative manner. e e 6 WG e., e-ee.e...e en e e = ap.ew+w
- e-
- h es e em ene em' n
i,.:.:.;,.......-. b ,51 J" ^ . i; ' (; ^ ' p ^*'-- area) of the acceptance criteria of SRP 11.5 which the applicant 11.5.2 has not addressed or which deviate from the acceptance criteria i uunze dor T ability to r lac &sor de antami-n ^ e \\.v. ; w.. . (aI cap \\ g r losing,l1 / gase s effi nt withou openi the pro ss system 1l l ( the capab ity to isolate the effluent stre [(.5 > N.; 4:ain. .()
- he divers alves oc ed t
8'6 i mo do not fa in the closed position; / ( t confoman of n - ESF instru tat n to th desig uida of nd 11.5-A of S as not been a ressed; and f pff[inco'rporation of administrative controls and procedur inadvertent or accidental releases of radioactive liquidsf-- -a+ E y=~ -y. J. g ~ {_ The turbine building drain monitors and the tank area drain monitors q L. ', i Therefore, there appears to DQ do not provide a record of effluent flow. be no neans to determine the quantity of activity released nor the L }.%.. ' ' ' It is the f$ {.'[/g ' volume released in accordance with Regulatory GQide 1.21. L ' ("..'staff's position that the SHHPP possess the capability to determine [:'.,...y- : ' ' [' A' the quantity of effluents released from these two source g '6 The applicant h not provided sufficient nfomation in the FSAR to releases fr\\; the vents o i n~ all w the staff to detemine whether t on recycle system are routed in s ch a manner that a quate mo. tor b I a d sampling of these urces is p esent at the SHNPP. Su osmati ~ ~ A ^Dk r.
- ~
v i s required. $ ? l k- @n ~ - r %qM MbVdf[I h bh- [, ~ .a mmec m
p\\ ~ O' ~ 6f ' ' ~n l.., 11'.5.2 The ap licant has' provided cent adictory information on the operation of ~ the vent \\ valve on the WPB cooling water surge tank. Section 9.2.10.2.2 of the FS states that this valve loses automatically on a high radia-tion signal from the discharge of the WPB cooling water monitor (REM-3544)'. he appliceIt's response FSAR question 460.35 stated that upon reca t of an alam 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 th'e vent valve ~ ~ sh5uld' be isolated diately because failur of a seal in either the waste gas compres or or the catalytic reemb ner of the waste gas system could result in new and significant rele se path for effluents. [ As a result of their responses to staff questions on the FSAR, the ( applicant needs to revise varia"= antitiant af th. renq. n,; 2 .5 rr ':i::: i n;' ;;'; p l 1) igares 9 .2-Yan 10.1.0-6 show sam ing pin" -11, 12,- of the steam g tor blowdown; lc p\\ a Tabl.e 9'.3.2-2, Figure 9.3.2-2, and Section 9.3.2.2.2 to reflec '. -. rab sampling of the service water system; mens
- 33. Table
.E.2-ra o. rin .. nts ot m~,'hO HUR G-0737, Attachments 1 and 2. l ? e app ant has not add ssed the m itoring of th nue from the volume eduction stem. Thihmust addr sed. l p. l 'Ql l X
~ 55 - I e (:;' ~ 11.5.2 The staff's review 'of the process and effluent monitoring system has not addressed some items of SRP 11.5. Those items which have not been addressed will be reviewed at the time the Radiological EfMuent Technical Specifications. are reviewed. Those areas of the process and effluenti monitoring system which will be reviewed at that time incJude: J cq (1) sampling frequencies, required analyses, instrument alarm /.tga set points, calibration, and sensitivities; and, (2) frequency of routine instrument calibration, maintenance, and .nspections. The process and effluent monitoring systems cannot be judged as to the ~ adequacy until the above items are addressed. l e e a. 4
- ~
-*=e .m 5 4 0 H. : - .. t 4 = me
- .c.,
w
- ~;;.n:i
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t -_4 Table 11.5-1 1.iquid and airborne process and effluent. monitoring system at the Shearon Harris Nuclear Power Plant 4 Monitor Monitor Number Monitoring Type Monitor A. Airborne Process B sein 21 REM-3545 NG 1. Gas Decay Ta:*, ~ RE-1FL-3506 P.I NG B scin, Y sein, 2. Fuel Handling Building RE-1FL-3507 8 scin Homal Exhaust REM-1FL-3508BSB P. I, NG B scin, Y sein, l
- 3. -Tuel Handling Building 6 sein S sein, Y scin, Emergency Exhaust REM-1FL-3508ASA B sein RDi-1AY-3531 P. I, NG S sein, Y scin, 6 sein 4.
Reactor Auxiliary Building Homal REM-2AV-3531 P,1. NG S scin, Y scin, Exhaust S sein REM-1AV-3532A P. I, NG B tein,'T scin, B scin i 5. Reactor Auxiliarf Building Emergency REM-1AV-3532B P. I, H3 8 scin, y sein, Exhaust S scin REM-2AY-3532A P. I, NG S scin, Y scin, S scln P.04-2AV-3532B P I,NG B sein, Y scin, S scin ' REM-1TV-3534 NG B sein 6. Condenser Vacuum Pump REM-2TV-3534 NG B sein Ef fluent Treatnent y g. f System 7. Continuous Containment REM-1LT-3502ASA P, I, NG B sein, Y sein, B sein Purge REM-1LT-3502BSB P,1. NG S scin, Y scin, S scin / a.- REM-2LT-3502ASA F, I, NG S sein, Y scin, 8 scin RDt-2LT-3502BSB P I, NG B scin, Y scin, S scin e f Ik E m - a n E ~b"yG (E S L '' 3
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~... Table 11.5-1 (Continued) Monitor Monitor Monitor -Number Monitoring Type B B. Liquid Process Y sein 1 REM-3501A 1. Component Cooling Water Y sein 1 REM-3501B Y sein System. 2 REM-3501A Y sein 2 REM-3501B ; '2. I 'ux'iliary Steam Con, 21-REM-3525A. Y sein ~ Y scin A 21-REM-3525A densate Tank,, c Y sein 1 REM-3527 3.' Steam Generator Y scin 2 REM-3527 Blowdown Y sein 4 Auxiliary Steam 21 REM-3543 Condensate Waste Processing System ".l..i.;, Y sein ~ 5. Waste Processing 1 REM-3544 Building Cooling Vater ~ C. Airborne Effluent 1. Plant Vent (Release REM-1AV-35095A P, I, NG S sein, Y scin, S sein Point 1) REM-2AV-35095A P,1, NG B scin, Y sein, 8 sein 2. Waste Processing Building Exhaust Systems
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(a) Release Point 5 REM-1WV-3546 P, I, NG S sein, Y scin, B sein (b) Release Point SA REM-1WY-3547 P. I, NG B scin, Y scin, B sein 3. Turbine Building Vent Stack (a) Release Point 3A (b) Release Point iS n-t. hy :'!- :..,' 7, g :-y n ;., .g:& 7. ,4ds.. v.. ! 3".- ', g,,3. s.:; e.;. , g..,
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7' t: (~ Table 11.5-1 - r_. (Continued) ~ Monitor Monitor Monitor Number Monitoring Type Liquid Effluent D. 1. Service Water System REM-1SW-3500ASB Y sein REM-25W-3500ASB Y sein REM-1SW-3500BSA Y sein REM-25W-3500BSA Y sein REM-1SW-3500L3A Y scin ~ ~ REM-25W-3500CSA Y sein REM-1SW-3500DSB Y sein ~ , REM-2SW-35000SB Y sein Y sein 2. Vaste Monitor Tanks REM-21WL-3541 3. Turbine Building Drain REM-1MD-3528 Y sein REM-2MD-3528 Y scin.. [ G 4. Tank Area Drain REM-1MD-3530 Y sein : ~ i Transfer Pumps REM-2MD-3530 Y scia w 5. Treated Laundry and REM-1WL-3540 Y sein u t %ower Tank Pumps e =- 6. Secondary Waste Sample REM-21WS-3542 Y sein Tank Pumps P = Particulate I = Radiciodine NG = Noble Gases e 4 e a. e ..,['g. j,.. '3.c
c 57 - f 11.5.7.3 Licuid Tank Failure Accident The staff evaluated 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 Cr'iteria of 3RP 15.7.3, NUREG-0800. Considered in the evaluation are (1) the radionuclide inventory ir. 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) nitigating effects incor-porttad into the plant design, and (4) the effects of site geology and hydrology. (< The results of this analysis were prcsented in Section 2.4.6 of this N SER. e 4 0 e AW
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