LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 11.2, Liquid Waste System
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11.2 LIQUID WASTE SYSTEM The Liquid Waste System (LWS) provides controlled handling and disposal of liquid wastes generated during plant operation. The system is designed to minimize exposure to plant personnel and the general public, in accord with Nuclear Regulatory Commission (NRC) regulations. 11.2.1 Design Objectives The design objectives of the LWS are the following: 1. Maintain annual activity releases within the limits specified in 10CFR20 2. Protect the public health and safety by maintaining radioactive releases as low as practicable 3. Collect radioactive and potentially radioactive liquid wastes 4. Provide processing of liquid wastes such that operation and availability of the stations are not limited 5. Assure that exposures to the public are maintained below the design objectives set by Appendix I to 10CFR50 The design criteria for the LWS areas follows: The facility design shall include those means necessary to maintain control over the plant radioactive liquid effluents. Appropriate holdup capacity shall be provided for retention of liquid, can be release particularly where unfavorable environmental conditions expected to require operational limitations upon the of radioactive effluents to the environment. In all cases, the design for radioactivity control shall be justified 1) on the basis of 10CFR20 requirements, for both normal operations 11.2-1 SGS-UFSAR Revision 6 February 15, 1987 and for any transient situation that might reasonably be anticipated to occur and 2} on the basis of 10CFR50. 67 dosage level limits for potential reactor accidents of exceedingly low probability of occurrence. Liquid facilities are designed so that discharge of effluents and offsite shipments are in accordance with applicable governmental regulations. Radioactive fluids entering the LWS are collected in tanks until determination of subsequent treatment can be made. They are sampled and analyzed to determine the quantity of radioactivity, with an isotopic breakdown if necessary. Liquid wastes are processed as required and then released under controlled conditions following isotopic analysis. The system design and operation are directed toward minimizing releases to unrestricted areas. Discharge streams are appropriately monitored and safety features are incorporated to preclude releases in excess of the limits of 10CFR20. 11.2.2 System Description The bulk of the radioactive liquids discharged from the Reactor Coolant System ( RCS) is processed and retained inside the plant by the Chemical and Volume Control System {CVCS) recycle train. This minimizes liquid input to the LWS which processes relatively small quanti ties of generally low activity level wastes. The processed water from waste disposal, from which most of the radioactive material has been removed, is discharged through a monitored line to the service water discharge header and then to the circulating water discharge. During normal plant operation the LWS processes liquids from the following sources: 1. Equipment drains and leaks SGS-UFSAR 11.2-2 Revision 23 October 17, 2007 *
- 2. Radioactive chemical laboratory drains 3. Hot shower drains 4. Decontamination area drains 5. eves demineralizer regenerant solutions and spent resins 6. Sampling System In addition, piping has been installed to direct fluid valves in the following systems to the LWS: Residual Heat Removal (RHR), ection (SIS), Containment eves, Sampling This minimizes the event of of accidents. radioactive the continuous releases from steam generator blowdown from in the to below the of the steam blowdown radiation monitor are to the condenser or to the non-radioactive waste treatment system. The LWS also collects and transfers liquids from the to the eves, to the waste tanks, or back to the tank (depending on fluid content) for 1. Reactor coolant 2. Pressurizer relief tank 3. Reactor coolant pump seals 4. Excess letdown ( 5. Accumulators 6. Valve and reactor vessel leakoffs 7. canal drains 11.2-3 SGS-UFSAR sources water storage Revision 25 October 26, 2010 These liquids flow to the reactor coolant drain tank and are-discharged either directly to the eves holdup tanks or to the waste holdup tanks by the reactor coolant drain pumps which are operated automatically by a level controller in the tank. These pumps also return water from the refueling canal and cavity to the refueling water storage tank. There is one reactor coolant drain tank with two reactor coolant drain tank pumps located inside containment. Where possible, waste liquids drain to the waste holdup tanks by gravity flow. Other waste liquids drain to the Auxiliary Building sump tank and are discharged to the waste holdup tanks by pumps operated automatically by a level controller for the Auxiliary Building sump tank. With the exception of the shared pumps and tanks of the Laundry and Hot Shower Drains, the Chemical Drains, Portable Filter and the Portable Demineralizer, each unit has its own Liquid Waste Disposal System. The Laundry and Hot Shower Drain Tanks and the Chemical Drain Tank are pumped to one of the Waste Hold-up Tanks or the Waste Monitor Hold-up Tank of either unit. When a Waste Hold-up or Waste Monitor Hold-up Tank is filled, it is isolated and sampled while another tank is in service. If analysis confirms that the activity level of the tankrs contents is suitable for discharge, the tank's contents may be pumped through a flow meter and a radiation monitor to the Service Water system. Tanks requiring processing before release are routed on a batch basis through a portable filter and portable de.mineralizer. The effluent of the portable system is returned either to the Waste Monitor Hold-up Tanks or the eves Monitor Tanks to be sampled, analyzed, and either reprocessed or pumped through a flow meter and a radiation monitor to the Service Water System. Although the Waste Monitor Hold-up or eves Monitor Tank analysis forms the basis for recording activity releases, the radiation monitor provides surveillance over the operation by closing the discharge valve if the liquid activity exceeds a preset value. 11.2-4 SGS-UFSAR Revision 17 October 16, 1998 ...._,..
The system is capable of processing all liquid wastes generated during continuous operation of the primary system assuming that fission products escape to the reactor coolant by diffusion through defects in the cladding on one percent of the fuel rods. At least two valves must be manually opened to permit discharge of liquid waste from the LWS. The control valve will trip closed on a high effluent radioactivity level signal. The system is controlled from a central panel in the Auxiliary Building. Malfunction of the system is alarmed in the Auxiliary Building, and annunciated in the Control Room. All system equipment is located in the Auxiliary Building, except for the reactor coolant drain tank and drain tank pumps which are located in the reactor containment, and a 2-inch line from the drain tank pumps to the refueling water storage tank (RWST). The LWS process flow diagram is shown on Plant Drawings 205239 and 205339. Performance data for the LWS is given in Table 11. 2-1. liquid discharged to the LWS is given in Table 11.2-2. 11.2.3 System Design The LWS code requirements are given in Table 11. 2-3. The estimated annual A summary of component system data is given in Table 11.2-4. Note that Table 11.2-3 also contains code data for the Gaseous and Solid Radwaste Systems. 11.2-5 SGS-UFSAR Revision 27 November 25, 2013 Hot Shower Tanks Two stainless steel tanks collect liquid wastes originating from the hot shower and local sinks. These tanks and their associated pumps are common to both Units' LWS. The intention is that one tank will be available for filling, while the contents of the other tank are being pumped to a waste holdup tank to await processing. A basket type strainer is provided downstream of this pump to prevent discharge of lint to other tanks.. The pump is started and stopped manually from a local control panel. Chemical Drain Tank The chemical drain tank is stainless steel and collects drainage from the chemistry laboratory. This potentially high activity waste is normally transferred to the waste holdup tanks to await processing. This tank and associated pump are common to both Units 1 and 2. The pump is started and stopped from a local control panel. The suction lines from the chemical drain tank and laundry tanks are interconnected to allow the laundry pump and chemical drain pump to substitute when necessary. Reactor Coolant Drain Tank The reactor coolant drain tank is a right circular cylinder with spherically dished heads. The tank is constructed of stainless steel with welded seams. The -___,. reactor coolant drain tank receives recyclable waste from the following sources: 1. Reactor coolant pump seal and head tank leakoffs 11.2-6 SGS-UFSAR Revision 14 December 29, 1995
- 2. Drains from each of the four primary coolant loops 3. Reactor vessel flange leakage 4. Accumulator drains 5. Excess letdown 6. Refueling canal drains During normal operation a nitrogen blanket1 maintained in the reactor coolant drain tank. at a pressure of 0. 5 psig, is *The tank is normally vented to the Gaseous Waste Disposal System vent header so that changes in liquid level will cause the tank to breathe to and from this header. This eliminates the of hydrogen and radioactive gases to the containment. The contents of the reactor coolant drain tank can be transferred to one of the following 1. eves holdup tanks 2. Emergency Core System (ECCS) RWST 3. LWS holdup tanks Normally all waste collected in the reactor coolant drain tank is transferred to the CVCS holdup tanks by the Nos. 111 21 and 12, 22 reactor coolant drain pumps. Operation of these pumps is automatically controlled by tank level instrumentation. Valves WL-12 and WL-13 are maintained in the in the reactor coolant drain tank pump discharge line shut following containment isolation until manually reset by the operator. 11.2-7 SGS-UFSAR Revision 26 May 21, 2012 Two waste holdup tanks are provided to accept liquid wastes from the eves, sump tank, chemical drain tank, reactor coolant drain tank, Steam Generator Blowdown System, floor and hot shower tanks. The tanks are of welded stainless steel construction. Individual air-operated valves in the common inlet manifold to these tanks are used to divert waste flow from one tank to the other. Two tanks are with the intention that one tank will be available to accept waste, while the contents of the other tank are being held to await processing. This an additional over and above that available from to allow shorter-lived radionuclides to An additional 25, waste monitor holdup tank is available to waste surges in the event of an emergency. The containment sump accumulates all floor drains, washdowns from refueling decontamination operations, drains and condensate from the fan coil units and miscellaneous equipment drains of a potentially radioactive but non-reactor coolant nature. The contents of this sump are pumped directly to the waste holdup tanks by two sump pumps that operate from sump level control instrumentation. Both pumps can also be started manually. All wetted parts of the pump are stainless steel. The tank is all welded stainless steel. The Unit 1 waste evaporator is abandoned in place. No. 2 waste evaporator has been cancelled. 11.2-8 SGS-UFSAR Installation of the Unit Revision 26 May 21, 2012 Piping and valves which are in, contact with liquid wastes are constructed of stainless steel. Piping con11ections are welded except where flanged connections are necessary to facilitate equipment maintenance. Isolation valves are provided to isolate each piece of equipment for maintenance, to direct the flow of waste through the system, and to isolate storage tanks for radioactive Relief valves are for tanks containing radioactive wastes if the tanks might be over component malfunction. The spent resin storage tank retains the zed by operation or resin discharged from the mixed bed, evaporator feed ion exchange, spent fuel , deborating vessel and cation demineralizers. A layer of water is maintained over the resin storage to prevent resin degradation due to heat from fission products. The contents can be removed any time by flushing with nitrogen. Resin sample connections are supplied and downstream of the spent resin storage tank isolation valve. The tank is all welded austenitic stainless steel. 11.2-9 SGS-UFSAR Revision 26 May 21, 2012 The Waste Monitor Tanks have been disabled and abandoned in place (West end of 84' elevation). These tanks are of welded stainless steel construction. The Waste Monitor Hold-up Tank, used as a steel tank and it serves a dual purpose. WHUT, is also a welded stainless Its normal function is as a third waste holdup tank to receive abnormally large quantities of waste discharged to the system, but it can also serve as a waste monitor tank. Portable Processing System Permanent provisions have been made to the 460 VAe supply, waste liquid piping, compressed air piping, and the demineralized water-restricted area to allow for the .installation and operation of a portable system to process liquid radwaste from either unit. The Unit 2 liquid waste may be processed at a higher rate due to a difference in piping configuration. The system is installed and operated in the 100' elevation of the truck bay of the The effluent of the is returned to either the Waste Monitor Holdup Tanks or the eves Monitor Tanks to be sampled, analyzed, and either reprocessed or disposed of. Exhausted ion media, or or both, is transferred to a burial site approved container after which it can be processed, classified, and shipped for The steam generator blowdown is described in section 10.4.8. 11.2.4 Procedures Verification is made to ensure that dilution flow sufficient to meet the of 10CFR20 is available whenever radioactive liquid wastes are released to the Plant Discharge System. 11.2-10 SGS-UFSAR Revision 26 May 21, 2012 Liquid waste releases are continuously monitored for gros*s activity during discharges to ensure that the activity limits specified in 10CFR20 for unrestricted areas are not exceeded. The maximum allowable release at the plant is specified in the Technical Specifications. Radioactive liquid batch wastes are sampled prior to releases to the Plant Discharge System and records of all releases are kept. Continuous releases from the steam generator blowdown system are monitored and controlled in accordance with the Salem Offsite Dose Calculation Manual. 11.2.5 Performance Tests Samples are taken on each batch of liquid waste released. Station records contain the quantity and concentration of radioactive isotopes, the volume of each batch and estimates of the water flow for dilution. Each sample is analyzed for principal gamma emitters. Composites are prepared from each batch released during a month and analyzed for the principal gamma emitting nuclides, fission and activation products, gross alpha, and tritium. A quarterly composite analysis is also performed for Sr-89, Sr-90, and Fe-55. The sensitivities and frequencies of analyses comply with the requirements of Salem Technical Specifications. Continuous releases from the steam generator blowdown system are sampled and analyzed to determine the quantity and concentration of isotopes present in the blowdown stream. Composites are prepared from the samples. The sensitivities and frequencies of analysis comply with the requirements of the Salem Technical Specifications. 11.2-lOa SGS-UFSAR Revision 18 April 26, 2000 I THIS PAGE INTENTIONALLY LEFT BLANK 11.2-lOb SGS-UFSAR Revision 13 June 12, 1994 11.2.6 Estimated Releases Liquid wastes are primarily by plant maintenance and service operations, and, consequently, the quantities and activity concentrations of influents to the system. Tables 11.2-5 and 11.2-6 are estimated values. Therefore, considerable operational margin has been assigned between the design capability and the estimated system load as indicated in Table 11.2-5. A conservative estimate of system ability activity released in the iiquid phase is to *limit dissolved and suspended summarized in Table 11.2-6: This tabulation is based on the following assumptions. 1. Fission product concentration in the reactor coolant is based on 1 defective fuel. 2. of reactor grade coolant which is and discharged from the is assumed to be a total of 2,102 gallons per day. 3. Non-reactor non-radioactive which is and discharged from the is assumed to be a total of 4,308 gallons per day. 4. It is assumed that the liquid wastes are accumulated in the waste SGS-UFSAR holdup tank and then cooling water. for 11.2-11 overboard with the raw Revision 26 May 21, 2012
- 5. A dilution factor is used in determining the discharge concentrations of liquids released from the waste rnoni tor holdup and waste holdup tanks. This is discussed in Section 11.2.8. 6. The tri tiurn that is formed in the fuel (the predominant source) diffuses through the zircaloy clad and eventually becomes available for dispersal to the environment. The expected release of ternary produced tritium is about 1 percent; the total annual tritium release expected is indicated in Table 11.2-6. All of the sources of tritium accumulating in the reactor coolant, shown in Section 11.1, are included in the annual release. The release estimates given in Table 11.2-6 are based on continuous operation with 1 percent fuel defects in both units. Based on experience with operating pressurized water reactors to date, 0.2 percent is a more realistic estimate of fuel defects averaged over a year of operation. Hence, in order to evaluate expected releases, all release values, except for H-3 and corrosion activation products given in Table 11.3-6, could be reduced by a factor of 5. The release estimates for continuous releases from the steam generator blowdown system are based on assumptions consistent with NUREG-001 7. Releases are monitored by the steam generator radiation monitors which provide a signal to close the isolation valves to maintain releases within the requirements of the ODCM. At higher primary system activity levels, steam generator blowdown would be isolated at lower primary to secondary leakage rates. 11.2.7 Release Points Release points are shown on the system flow diagram, Plant Drawings 205239 and 205339. 11.2.8 Dilution Factors Monitored waste released from the Liquid Waste Disposal System is normally pumped into the Circulating Water System discharge lines via the Service Water System. The maximum release rates are calculated based on how many circulators are available in the release path. The release rate is controlled by throttling the discharge valve to maintain the maximum release rate or less. Stearn generator blowdown is directed to the non radioactive waste basin either from the blowdown flashtank or from the condensate polishing system and then to the circulating water system. 11.2-12 SGS-UFSAR Revision 27 November 25, 2013 11.2.9 Estimated Doses (Potential) There are generally two main pathways by which the general population could receive radiation exposure from liquid releases. One would be by drinking the water from the river in the vicinity of the station, the other would be by the consumption of marine life (such as fish and shellfish) that inhabit the general river and bay area (marine life has a tendency to reconcentrate certain radioactive isotopes above background water levels). Less important pathways would be from swimming in the river, boating or fishing, standing on the shoreline, etc. Section 2 contains detailed information on public water supplies and known water wells in the Salem site vicinity. Because of the brackish condition of the river, no potable water supplies are drawn from it in the area. Ground water is the primary source of water supply in the vicinity with the exception of the city of Salem, New Jersey, which obtains about two-thirds of its water supply from Quinton, on Alloways Creek. This water supply is a dammed fresh water stream some 9 miles upstream from the Delaware River -Alloways Creek confluence. Hence, no radioactive releases would reach this public water supply from the Salem station as the flow is from Alloways Creek into the Delaware River. Consideration was given to the possibility of radioactivity reaching public and private water supplies that are present in the Salem area. The Delaware River is not recharging aquifers that are in use. The upper sand layers in the region are saline aquifers. The artesian aquifers, located at much greater depths than the saline aquifers, are separated from the upper sand layers by an impervious clay strata. Hence, no Hydraulic communication exists. It is concluded that no liquid radioactive releases could reach ground water drinking supplies in the Salem area (additional information on ground water hydrology is given in Section 2). 11.2-13 SGS-UFSAR Revision 14 December 29, 1995 Consideration was given to the radiation exposure that might be received through the fish food chain. The fundamental approach in evaluating this pathway is dependent on the radionuclide concentration provided by the fish in question. The concentration of the stable element {and the radionuclide) by the organism is related to the natural biological demand which the organism has for the element in question and the ratio of the concentration of the element to the elemental concentration in its water environment. Tables 11.2-7 and 11.2-8 relate the concentration factor (by the marine life), the radioactivity in the marine life and the resulting concentration to which the individual would be exposed upon consumption of fish and blue crabs, respectively. The following assumptions and data were used to develop the concentration factors, ingestion factors and fraction of MPC in Tables 11.2-7 and 11.2-8: 1. Concentration factors are based on a literature review of the stable element chemistry and the radionuclide concentration contained in "Concentration Factors of Chemical Elements in Edible Aquatic w. H. Chapman et al, UCRL-50564, December 30, 1968. 2. 100 percent of the effluent radionuclides are assumed to be ingested or absorbed by the marine life in question (the organisms are considered to remain in the vicinity of the discharge pipe 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 52 weeks per year). 3. Individual consumption will include approximately 4-5 meals per week (100 grams, or 140 grams per day, 52 weeks per year). The marine life in question are comprised of bullhead catfish, carp, weakfish, striped bass, American eel and blue crab. These organisms represent the major cross section of edible marine life caught in the area. 11.2-14 SGS-UFSAR Revision 6 February 15, 1987 -
- 4. The ingestion factor is calculated based on the following assumptions: a. Equivalent density for "fish flesh" and water b. Individual daily consumption of "fish flesh" is approximately 140 grams c. MPC values given in 10CFR20 are based on a total daily intake of 2.2 liters of water I t. F t 140 --6.36 X 10-2 nges 10n ac or = 2200 This approach to an analysis of radiation exposure through the food chain is extremely conservative. The assumption that the marine life in question will remain adjacent to the discharge pipe 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 52 weeks per year, is highly conservative. The reduction in radioactivity due to radioactive decay and biological turnover was not assumed. Based on Table 11.2-7 and 1 percent failed fuel, the potential exposure from eating 50,000 grams (110 lbs) per year of fish can -5 be calculated as 6.1 x 10 x 500 mrem = 0. 030 mrem per year. Similarly, from Table 11.2-8, the potential exposure from eating 50,000 grams per year of crabmeat (net weight) can be calculated -4 as 2.4 x 10 x 500 mrem = 0.12 mrem per year. Based on 0.2 percent fuel defects, the exposures from ingestion of fish and crabmeat would be 0.01 mrem/yr and 0.03 mrem/yr, respectively. Consideration was also given to individuals swimming, fishing, and boating on the river. Calculation of these doses is given below. 11.2-15 SGS-UFSAR Revision 6 February 15, 1987 The dose to an individual swimming near the discharge canal was calculated using the following basic equation for the dose in an "infinite" homogeneous source (1): R = 51 CE where! R = dose, rads/day C = concentration of radioactive material, uCi gm E = decay energy, Mev/dis. The release concentrations given in Table 11.2-6 (based on 1 percent fuel defects) would be adjusted to 2.0 x 10-ll uCi/cc, excluding H-3, and 4.5 x 10-7 uCi/cc for H-3 (based on 2 percent fuel defects). It is assumed that an individual swims near the discharge canal for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year. It is also assumed that the average decay energy is I Mev/dis for all isotopes except H-3. An average decay energy of 0.0057 Mev/dis is used for H-3. The calculations to a maximum individual follow: Dose due to all isotopes except H-3 D = 51(2.0xl0-ll !£) cc D -9 = 8.3xl0 yr 11.2-16 SGS-UFSAR (l Mev) dis (200 hrs) yr Revision 6 February 15, 1987 ..__,.
Dose due to H-3 D uCi cc Mev hrs 1 day s1 (4.5x 10-' --)--ri -> (o.oos7 --> {2oo --) c ) cc gm dis yr 24 hrs rads D 1. 1x 1 o-6 --yr The total dose is thus 1.1x10-6 rads per year. The dose to an individual fishing along the shore or on a boat on the river can be estimated in a manner similar to the one above. In this case, it is more appropriate to think in terms of a "semi-infinite" medium, since essentially no radioactivity from releases to the river is present in the air above the river (in the swimmdng case, it was assumed that the individual was "submerged" in the water; hence, the individual would be exposed to radiation from all directions}. The doses to an individual fishing 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year on shore or on a boat would thus be one-half of the doses previously calculated, or 4. 3x10-9 rads per year due to all isotopes except H-3 and 5.5xl0-1 rads per year due to H-3, for a total dose of S.Sxl0-7 rads per year. The dose pathways considered, and the resulting doses to the maximally exposed individual based on realistic liquid releases at 0.2 percent failed fuel defects, are summarized in Table 11.2-9. Doses and releases, including steam generator blowdown continuous releases are controlled in accordance with the Salem Offsite Dose Calculation Manual. 11.2.10 1. SGS-UFSAR Reference for Section 11.2 Evans, R. D. "The Atomic Nucleus," McGraw-Hill, 1955, p. 742. 11.2-17 Revision 18 April 26, 2000