BVY 09-037, Vermont Yankee - Off-Site Dose Calculation Manual, Revision 31

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Vermont Yankee - Off-Site Dose Calculation Manual, Revision 31
ML091460624
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 04/08/2008
From: Skibniowski S
Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
BVY 09-037
Download: ML091460624 (393)
v • d • e


Text

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hapter 5 contains the basis for plant procedures that the plant operator requires to meet ODCM Control 3.2.1 which limits the total fraction of combined effluent concentration in liquid pathways, excIuding noble gases, denoted here as, FF~ at the point of discharge at any time (see Figure 9-1). Ff"" is limited to less than or equal to ten, Le., The total concentration of all dissolved and entrained noble gases at the point of discharge from all station sources, denoted CING, is limited to 2E-04 pCi/ml, Le., cy 12E - 04 pCi /ml. Evaluation of ~y and crG is required concurrent with the sampling and analysis program in Control Table 4.2.1. 5.1 Method to Determine FfNG and CyG Determine the total fraction of combined effluent concentrations at the point of discharge in liquid pathways (excluding noble gases), denoted FYI and determine the total concentration at the point of discharge of all dissolved and entrained noble gases in liquid pathways from all station sources, denoted CING, as follows: and: I Revision29 Date 1/11/02 5-1 cf"" = cFG 12E-04 i where: pENG = Total sum of the fractions of each radionuclide concentration in liquid effluents (excluding noble gases) at the point of discharge to an unrestricted area, divided by each rahonuclide's ECL value. I cpi = Concentration at point of discharge to an unrestricted area of radionuclide "i", except for dssolved and entrained noble gases, from any tank or other significant source, p, from which a discharge may be made (including the floor drain sample tank, the waste sample tanks, the detergent waste tank and any other significant source from which a discharge can be made) (pCi/ml).

This concentration can be calculated from: Cpi = CTKI x FTK/~DIL + FTK) where: CTKI equals the concentration of radionuclide i in the tank to be discharged (pCi/ml); FDL is equal to the dilution flow provided by the liquid radioactive waste ddution pumps (20,000 gpm); FTK equals the liquid waste discharge pump flow rate which regulates the rate at which liquid horn a waste collection tank is discharged (gpm). ECL, = Annual average effluent concentration limits of radlonuclide Y', except for &solved and entrained noble gases, from 1OCFR20.1001-20.2402, Appendix B, Table 2, Column 2 (pCi/ml). I CY = Total concentration at point of discharge to an unrestricted area of all dissolved and entrained noble gases in liquid pathways from all station sources (pCi/mlj. cFG = Concentration at point of discharge to an unrestricted area of dissolved and entrained noble gas "i" in liquid pathways from all station sources (pCi/ml). I Revision 2 Date 1/11/02 5-2 5.2 Method to Determine Radionuclide Concentration for Each Liquid Effluent Pathway 5.2.1 Sample Tanks Pathways Cpi is determined for each radionuclide above LLD from the activity in a representative grab sample of any of the sample tanks and the predicted flow at the point of discharge to an unrestricted area. Most periodic batch releases are made from the two 10,000-gallon capacity waste sample tanks. These tanks serve to hold all the high purity liquid wastes after they have been filtered through the waste collector and processed by ion exchange in the fuel pool and waste demineralizers. Other periodic batch releases may also come from the detergent waste tank or the floor drain sample tank. The tanks are sampled from the radwaste sample sink and the contents analyzed for water quality and radioactivity. If the sample meets all the high purity requirements, the contents of the tank may be re-used in the nuclear system. If the sample does not meet all the high purity requirements, the contents are recycled through the radwaste system or discharged. Prior to discharge each sample tank is analyzed for tntium, dissolved noble gases and dissolved and suspended gamma emitters. 5.2.2 Service Water Pathway The service water pathway shown on Figure 9-1, flows from the intake structure through the heat exchangers and the discharge structure. Under normal operating conditions, the water in this line is not radioactive. For this reason, the service water line is not sampled routinely but it is continuously monitored with the service water discharge monitor (No. 17/351). The alarm setpoint on the service water discharge monitor is set at a level which is three times the background of the instrument. The service water is sampled if the monitor is out of service or if the alann sounds. I Revision 29 Date 1/11/02 5-3 .. Under expected or anticipated operating conditions, the concentration at any time of I area will not exceed ten times the effluent concentration values of lOCFR20.1001-20.2402, radionuclides at the point of discharge from the service water effluent pathway to an unrestricted Appenchx B, Table 2, Column 2, 5.2.3 Circulating Water Pathway The circulating water pathway shown on Figure 9-1, flows from the intake structure through the condenser and the discharge structure. Under normal operating conditions, the water in this line is not radioactive. For this reason, the circulating water line is not sampled routinely but it is monitored continuously by the discharge process monitor {No. 17/359) located in the discharge structure. The alarm setpoint on the discharge process monitor is set at a level which is three times the background of the instrument. The circulating water is sampled if the monitor is out of service or if the aIarm sounds. Under normal operating conditions, the average concentration of radionuclides at the point of discharge from the circulating water pathway to an unrestricted area will not exceed the I annual effluent concentration limits in 1OCFR20.1001-20.2402, Appendlx B, Table 2, Column 2. I Revision29 Date 1/11/02 5-4 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SUMMARY

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`SB'NX"'!'%R5O'II a 8 2C;37MGYKU[YJOYINGXMKLRU]!II'YKI"/&*&*&*4GYOYLUXZNKC;37?UHRK9GY3IZO\OZ_>UTOZUXCKZVUOTZDNKC;37TUHRKMGYGIZO\OZ_SUTOZUXYKZVUOTZS[YZKTY[XKZNGZDKINTOIGRCVKIOLOIGZOUT+&/&<&)OYTUZK^IKKJKJ&DNKJKXO\GZOUTUL7W[GZOUT/%*)OYYZXGOMNZLUX]GXJ&COSVR_ZGQOTM7W[GZOUT/%)-GTJY[HYZOZ[ZOTMZNKROSOZOTMXKRKGYKXGZKGZZNKC;37LUX $_OKRJY7W[GZOUT/%*)$ZNKYKZVUOTZKW[GZOUTLUXZNKC;37TUHRKMGYGIZO\OZ_SUTOZUX&EKXSUTZFGTQKK?[IRKGXAU]KXCZGZOUT@LL%COZK6UYK5GRI[RGZOUT>GT[GRCKIZOUT/BK\&+(AGMK**UL** I 9.0 LIOUID AND GASEOUS EFFLUENT STREAMS. RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS Figure 9-1 shows the normal (design) radioactive liquid effluent streams, radiation monitors, and the appropriate Liquid Radwaste Treatment System. Figure 9-2 shows the normal (design) gaseous effluent systems, radiation monitors, and the appropriate Gaseous Radwaste Treatment System. I 9.1 In-Plant Radioactive Liauid Effluent Pathways The Liquid Radwaste System collects, processes, stores, and disposes of all radioactive liquid wastes. Except for the cleanup phase separator equipment, the condensate backwash receiving tank and pump and waste sample tanks, floor drain sample tank and waste surge tank, the entire Radwaste System is located in the Radwaste Building. The Radwaste System is controlled from a panel in the Radwaste Building Control Room. The Liquid Radwaste System consists of the following components:

1. Floor and equipment drain system for handling potentially radioactive wastes. 2. Tanks, piping, pumps, process equipment, instrumentation and auxiliaries necessary to collect, process, store, and dispose of potentially radioactive wastes. The liquid radwastes are classified, collected, and treated as either high purity, low purity, chemical or detergent wastes. "High" purity and "low" purity mean that the wastes have low conductivity and high conductivity, respectively.

The purity designation is not a measure of the amount of radioactivity in the wastes. High purity liquid wastes are collected in the 25,000-gallon waste collector tank. They originate from the following sources:

1. Drywell equipment drains.
2. Reactor Building equipment drains.
3. Radwaste Building equipment drains. 4. Turbine Building equipment drains. 5. 6, 7. Resin rinse. Decanted liquids from cleanup phase separators. Decanted liquids from condensate phase separators, Revision 27 Date 10/09/00 9- 1 Low purity liquid wastes are collected in the 25,000-gallon floor drain collector tank. They originate from the following sources: 1. Drywell floor drains.
2. Reactor Building floor drains. 3. Radwaste Building floor drains. 4. Turbine Building foor drains. 5. Other floor drains in RCA (e.g., AOG and Service Building, stack, etc.). Chemical wastes are collected in the 4,000-gallon chemical waste tank and then pumped to the floor drain collector tank. Chemical wastes arise from the chemical laboratory sinks, the laboratory drains and sample sinks. Radioactive decontamination solutions are classified as detergent waste and collected in the 1,000-gallon detergent waste tank. Once the wastes are collected in their respective waste tanks, they are processed in the most efficient manner and discharged or reused in the nuclear system. From the waste collector tank, the high purity wastes are processed in one of three alternative filter demineralizers and then, if needed, in one "polishing" demineralizer.

After processing, the liquid is pumped to a waste sample tank for testing and then recycled for additional processing, transferred to the condensate storage tank for reuse in the nuclear system or discharged. The low purity liquid wastes are normally processed through the floor drain filter demineralizer and collected in the floor drain sample tank for discharge or they are combined with high purity wastes and processed as high purity wastes. Chemical wastes are neutralized and combined with low purity wastes for processing as low purity wastes. Although there is only one discharge pathway from the Radwaste System to the river, there are three locations within the Radwaste System from which releases can be made. They are: the detergent waste tank (detergent wastes), the floor drain sample tank (chemical and low purity wastes), and waste sample tank (high purity wastes). The contents of any of these tanks can be released directly to the river. The liquid wastes collected in the tanks are handled on a batch basis. The tanks are sampIed from the radwaste sample sink and the contents analyzed for radioactivity and water purity. A release is allowed once it is determined that the activity in the liquid wastes will not exceed Control release limits. I Revision 27 Date 10/09/00 9-2 A discharge from any of the tanks is accomplished by first starting the sample pumps, opening the necessary valves, and positioning the flow controller. The release rate in the discharge line is set between 0 and 50 gpm. The dilution pumps which supply 20,000 gpm of dilution water are then started. An interlock does not allow discharge to the river when dilution water is unavailable. The effluent monitor (No. 171350) in the discharge line provides an additional check during the release. The alarm or trip setpoint on the monitor is set according to the effluent Control limits and an analysis of the contents of the tank. The monitor warns the operator if the activity of the liquid waste approaches regulatory limits. In response to a warning signal from the monitor, the operator may reduce the flow rate or stop the discharge. Revision 27 Date 10/09/00 9-3 9.2 In-Plant Radioactive Gaseous Effluent Pathwavs The gaseous radwaste system includes subsystems that dispose of gases from the main condenser air ejectors, the startup vacuum pump, the gland seal condenser, the standby gas treatment system and station ventilation exhausts. The processed gases are routed to the plant stack for dilution and elevated release to the atmosphere. The plant stack provides an elevated release point for the release of waste gases. Stack drainage is routed to the liquid radwaste collection system through loop seals. The air ejector Advanced Off-Gas Subsystem (AOG) reduces the ejector radioactive gaseous release rates to the atmosphere. The AOG System consists of a hydrogen dilution and recombiner subsystem, a dual moisture removalldryer subsystem, a single charcoal absorber subsystem, and dual vacuum pumps. Equipment is located in shielded compartments to minimize the exposure of maintenance personnel. Radioactive releases from the air ejector off-gas system consist of fission product noble gases, activation product gases, halogens, and particulate daughter products from the noble gases. The particulates and halogens are effectively removed by the charcoal beds and high efficiency particulate filters in the AOG System. The activation product gases that are generated in significant quantities have very short half-lives and will decay to low levels in the holdup pipe, as well as in the absorber beds. The noble gases, therefore, are expected to provide the only significant contribution to off-site dose. The charcoal off-gas system is designed to provide holdup of 24 hours for krypton and 16.6 days for xenon at a condenser air inleakage rate of 30 scfm. Steam dilution, process control, and instrumentation systems are designed to prevent an explosive mixture of hydrogen from propagating beyond the air ejector stages. An explosive mixture of hydrogen should never exist in the recombiner subsystem, "30-minute" delay pipe, condenser/dryer, or charcoal absorber beds. To prevent a hydrogen explosion in the recombinerlpreheater and upstream lines during shutdown, the residual off-gas steam mixture containing hydrogen is purged with steam or air. Starting procedures insure sufficient steam is introduced upstream of the preheater to dilute any hydrogen entering the AOG System as the air Revision 27 Date l0/09/00 9-4 ejector line is prepared for operation. To prevent operating unsafely, instrumentation is used to detect an explosive mixture. Hydrogen control is accomplished by providing redundant hydrogen analyzers on the outlet from the Recornbiner System. These analyzers initiate recombiner system shutdown and switchover if the hydrogen concentration at the system outlet exceeds 2% by volume. During an automatic shutdown, two main air process valves close to isolate the recombiner system. Additionally, the recombiner bed temperatures and recombiner outlet temperature provide information about recombiner performance to insure that inflammable hydrogen mixtures do not go beyond the recombiner. Should a number of unlikely events occur, it would be hypothetically possible for a hydrogen explosion to occur in the off-gas system. Such an explosion within the recombiner system could propagate into the large "30-minute" delay pipe, through the condenserldryer subsystem, and into the charcoal absorber tanks. However, the recombinerladsorber subsystems, piping, and vessels are designed to withstand hydrogen detonation pressures of 500 psi at a minimum so that no loss of integrity would result. Furthermore, the seven tanks of charcoal would significantly attenuate a detonation shock wave and prevent darnage to the downstream equipment. During normal operation, the dryerladsorber subsystem may be bypassed if it becomes unavailable provided the releases are within effluent Control limits. With the dryerladsorber subsystem bypassed, the air ejector off-gas exhausts through the recombinerlcondenser subsystems, and the 30-minute delay pipe. I The off-gas mixture combines with steam at the air ejector stage to prevent an inflammable hydrogen mixture of 4% by volume from entering the downstream hydrogen recombiners. Approximately 6,400 lbhr of steam introduced at the second stage air ejector reduces the concentration of hydrogen to less than 3% by volume. The recombiner subsystem consists of a single path leading from the hydrogen dilution steam jet ejectors to two parallel flow paths for hydrogen recombination. Each recombination subsystem is capable of operating independently of the other and each is capable of handling the condenser off-gas at a startup design flow of 1,600 lblhr air and the normal off-gas design flow rate of 370 lblhr. The major components of each recombiner flow path are a preheater, a h ydrogen-oxygen recombiner, and a desuperheating condenser. Revision 27 Date 10l09l00 9-5 The preheater assures that the vapor entering the hydrogen-oxygen recombiner is heated to approximately 300OF. At this temperature, the water vapor in the stream becomes superheated steam, thereby, protecting the recombiner catalyst. During passages through the recombiner, the recombination of H2 and 0, in an exothermic reaction increases the stream temperature to approximately 52OOF. This recombination results in a maximum effluent H2 concentration of 0.1 % by volume. The desuperheating condenser is designed to remove the heat of recombination and condense the steam from the remaining off-gas. The condensers discharge the off-gas through moisture separators into the initial portion of an underground 24-inch diameter delay pipe which allows for 40% of the total system holdup volume. The pipe slopes away from the off-gas particulate (HEPA) filters in both directions for drainage purposes. Loop seals prevent gas escaping through drainage connections. Shorter lived radionuclides undergo a substantial decrease in activity in this section of the system. The preheatersh-ecombiners operate at pressures slightly above atmospheric; the condenser and the subsystems that follow operate at subatmospheric pressures. Particulate (mPA) filters with flame suppressant prefilters are located at the exit side of the delay pipe ahead of the moisture removal subsystem to remove radioactive particulates generated in the delay pipe. In the moisture removalidryer subsystem, the moisture of the gas is reduced to incfease the effectiveness of the charcoal absorber beds downstream. The subsystem consists of two parallel cooling condensers and gas dryer units. Each condenser is cooled by a mechanical glycollwater refrigeration system that cools the off-gas to -40OF as it removes bulk moisture. The dryer is designed to remove the remaining moisture by a molecular sieve desiccant to a dew point of less than -40°F (1% RH). One of the dryers absorbs moisture from the off-gas; the other desorbs moisture by circulating heated air through the bed in closed cycle. The mixed refrigerantldryer concept improves the reliability of the system. If the refrigerant system fails, the two dryer beds operate in parallel to remove the moisture and maintain the off-gas near the design dew point (-4OOF). If the dryer fails, the -40°F dew point air leaving the mechanical system can enter the guard bed for over 6 hours without affecting the performance of the charcoal beds downstream. Revision 27 Date 10/09/00 9-6 The charcoal absorber subsystem consists of seven tanks of charcoal preceded by a smaller charcoal guard bed upstream. The guard bed protects the seven main tanks from excessive radioactivity levels or moisture in the event of a malfunction upstream in the moisture removal subsystem. The guard bed also removes compounds which might hinder noble gas delay, The seven tanks hold a minimum of approximately 90,OOO pounds of charcoal. The first two main tanks can be bypassed and used for storing a "batch of high activity" gas for static decay. The remaining five are all in series with no bypassing features so that the off-gas to the stack must be delayed. Redundant particulate (HEPA) after-filters are used to remove charcoal fines prior to the vacuum pumps. A water-sealed vacuum pump boosts the gas stream pressure to slightly over-atmospheric pressure before it is vented through the stack. To assure maintaining constant operating pressures in the system, a modulating bypass valve will recirculate process gas around the pump as required. During periods of high flow rates, both pumps can be operated in parallel. Discharge of the vacuum pump then passes through the remaining 60% of the delay pipe prior to being vented through the station stack. The gland seal off-gas subsystem collects gases from the gland seal condenser and the mechanical vacuum pump and passes them through a charcoal filter (if required) and then through holdup piping prior to release to the stack. The gases from the gland seal condenser system are discharged to the atmosphere via the ventilation stack after passing through the filter for iodine removal (if required) and then through the same 1-314 minute holdup piping that is used for the startup vacuum pump system. One automatic valve on the discharge side of each steam packing exhauster closes upon the receipt of high level radiation signal from the main steam line radiation monitoring subsystem to prevent the release of excessive radioactive material to the atmosphere. The exhausters are shut down at the same time the valves close. In addition, the mechanical vacuum pump is automatically isolated and stopped by a main steam line high radiation signal. The filter assembly is located in the air ejector room. The release of significant quantities of gaseous and particulate radioactive material is prevented by the combination of the design of the air ejector AOG system and automatic isolation of the system from the stack. Gas flow from the main condenser stops when the air Revision 27 Date 10/09/00 9-7 ejectors are automatically isolated from the main condenser by either a high radiation signal in the main steam line or by high temperature and/or pressure signals from the AOG System. The gland seal off-gas system is automatically isolated and stopped by a main steam line high radiation signal. In addition, monitoring the stack release provides a backup warning of abnormal conditions. 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D, C 20555 August 30, 1989 Docket No. 50-271 Mr. L. A. Tremblay Licensing Engi neeri ng Vermont Yankee Nuclear Power Corporation Engi neeri ng Off i ce 580 Main Street Bolton, Massachusetts 01740-1398

Dear Mr. Tremblay:

SUBJECT:

APPROVAL UNDER 10 CFR 20.302(a) OF PROCEDURES FOR DISPOSAL OF SLIGHTLY CONTAMINATED SEPTIC WASTE ON SITE AT VERMONT YANKEE fTAC NO. 73776)

REFERENCE:

(a) June 28, 1989 letter from R. Ld. Capstick to US NRC Document Control Desk, including Attachment I and Attachment
11. Vermont Yankee Nuclear Power Station, dated July 1972. (b) Final Environmental Statement related to the operation of In reference (a) Vermont Yankee Nuclear Power Corporation (Vermont Yankee, or the licensee) submitted an application for disposal of licensed material on site. This disposal was not previously considered by the staff in the Vermont Yankee Final Environmental Statement (FES), reference fb). This extensive application, prepared in accordance with 10 CFR 20.302(a), contains a detailed description of the licensed material, thoroughly analyzes and evaluates the information pertinent to the effects on the environment of the proposed disposal of the licensed material, and commits the licensee to follow specific procedures to minimize the risk of unexpected or hazardous exposures.

In the FES, the NRC staff considered the potential effects on the environment of licensed material from operation of the plant and, in the assessment of the total radiological impact of the Vermont Yankee Station concluded that: "...operation of the Station will contribute only an extremely small increment to the radiation dose that area residents receive from natural background. Since fluctuations of the background dose may be expected to exceed the increment contributed by the plant, the dose will be immeasurable in itself and will constitute no meaningful risk to be balanced against the benefits of the plant." Revision Date 3/2/90 B-2 Mr. L. August 30, 1989 LA1 855 4 Since the disposal proposed by the licensee involves licensed material containing less than 0.1 percent of the radioactive materials, primarily cobalt-60 and cesium-137, already considered acceptable in the FES, and involves exposure pathways much less significant than those considered in the FES, we consider the site-specific application (Reference (a)) for Vermont Yankee Nuclear Power Station to have insignificant radiological impact. We accept the commitments and evaluations of the licensee, documented in reference (a), as further assurance that the proposed disposal procedures will have a negligible effect on the environment and the general population in comparison to normal background radiation. In conclusion, we find the licensee's procedures with commitments as documented in reference (a) to be acceptable, provided that reference (a) is permanently incorporated into the licensee's Offsite Dose Calculation Manual (ODCM) as an Appendix, and future modifications of reference (a) be re~orted to NRC in accordance with licensee commitments reqardinq ODCM chanqes. Pursuant to 10 CFR 51.22(~)(9), no environmental assessment is required. This completes our -review under TAC No. 73776. Sincerely , Morton 8. Fairtile, Project Manager Project Directorate 1-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation cc: See next page I Revision 9 Date 3/2/90 8-3 Mr. L. A. Tremblay d cc : Mr. J. Gary Weigand President & Chief Executive Officer Vermont Yankee Nuclear Power Corp. R.D. 5, Box 169 Ferry Road Brattleboro. Vermont 05301 Mr. John DeVi ncenti s, Vice President Yankee Atomic Electric Company 580 Main Street Bolton. Massachusetts 01740-1398 New England Coalition on Nuclear Hill and Dale Farm R.D. 2, Box 223 Putney, Vermont 05346 Pol 1 uti on Vermont Publ i c Interest Research Group, Inc. 43 State Street Montpelier, Vermont 05602 Regional Admi ni strator, Regi on I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussi a, Pennsyl vani a 19406 - R. K. Gad, I11 Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 Mr. W. P. Murphy, Vice President, Vermont Yankee Nuclear Power Corporation R.D. 5, Box 169 Ferry Road Brattl eboro, Vermont 05301 and Manager of Operations G. Dean Weyman Chairman, Board of Selectman Post Office Box 116 Vernon, Vermont 05354 Mr. Raymond N. McCandless Vermont Division of Occupational and Radiological Health Admi ni st rat i on Bui 1 di ng Montpel i er, Vermont 05602 Mr. George Sterzinger, Commissioner Vermont Department of Publ i c Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 Publ ic Service Board State of Vermont 120 State Street Montpelier, Vermont 05602 Honorable John J. Easton Attorney General State of Vermont 109 State Street Montpel ier, Vermont 05602 Conner & Wetterhahn, P.C. Suite 1050 1747 Pennsylvania Avenue, N.W. Washington, D.C. 20006 Diane Curran, Esq. Harmon. Curran & Tousley 2001 S Street. N.W., Suite 430 Washington, D.C. 20009 David J. Mullett, Esq. Special Assistant Attorney General Vermont Department of Publ i c Service 120 State Street Montpel ier, Vermont 05602 Jay Gutierrez Regional Counsel U.S. Nuclear Regulatory Commission 475 All.endale Road King of Prussi a, Pennsyl vani a 19406 G. Dana Eisbee, Esq. Office of the Attorney General Envi ronmental Protection Bureau State House Annex 25 Capitol Street Concord, New Hampshire 03301-6397 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commi ssi on Washington, D.C. 20555 .. , Revision 9 Date 3/2/90 8-4 Mr. L. cc : Mr. Gustave A. Li nenberger, Jr. Admini strati ve Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Resident Inspector Vermont Yankee Nuclear Power Station U. S. Nuclear Regul atory Commi ssi on P.O. Box 176 Vernon, Vermont 05354 John Traficonte, Esq. Chief Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, Massachusetts 02108 Geoffrey M. Huntington, Esquire Office of the Attorney General Envi ronmental Protection Bureau State House Annex 25 Capitol Street Concord, New Hampshire 03301-6397 Charles Bechhoefer, Esq. Administrative Judge Atomic Safety and Licensing Board U. S. Nucl ear Regul atory Commi ssi on Washington, D.C. 20555 - Or. James H. Carpenter Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Adjudicatory File (2) Atomic Safety and Licensing Board Panel Docket U.S. Nuclear Regulatory Commission Washington, D.C. 20555 / Revision Date 3/2/90 'VERMONT YANKEE NUCLEAR POWER CURF'OELATION Ferry Road. Brattlebom. VT 05301-7002 June 28, 1989 BVY 89-59 KCL. IO ENGINEERING OFFICE $80 LWN STREET BOLTON. MA 01 ?# T706711 United States Nuclear Regulatory Commi ssion Washington, DC 20555 Attention: Document Control Desk

Reference:

License No. DPR-28 (Docket No. 50-271).

Subject:

Request to Routinely Dispose of Slightly Contaminated Septic Waste in Accordance with 10 CFR 20.302(a)

Dear Sir:

In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.302(a) (10CFR20.302(a)), enclosed please find the subject application for the disposal of very low level radioactive waste materials. Vermont Yankee Nuclear Power Corporation (Vermont Yankee) hereby requests NRC approval of the proposed procedures for the disposal of slightly contaminated septic waste generated at the Vermont Yankee Nuclear Power Plant in Vernon, Vermont. This appl i cati on specifically requests approval to dispose of septic tank waste, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed method of disposal is for the on-site land spreading in designated areas in compliance with State of Vermont health code requirements for septic waste. Disposal of this waste in the manner proposed, rather than at a 10 CFR Part 61 licensed facility would save Vermont Yankee not only substantial cost, but also valuable disposal site space which would then be avai 1 ab1 e for wastes of higher radioactivity 1 eve1 s. Disposal as radioactive waste would require treatment of the biological aspects of the septage and solidification to a stable waste form, thereby increasing the volume substanti a1 ly . A radiological assessment and proposed operational controls, based upon the continued on-site disposal of septic waste as presently contained in the plant's septic tanks, are detailed in Attachments 1 and 2. Based upon this analysis, Vermont Yankee requests approval to dispose of septic tank waste on-site by land spreading in such a manner that the radioactivity concentration limit in any batch of septage to be spread does not exceed one-tenth of the MPC values listed in 10 CFR 20, Appendix B. Table 11; and the combined radi ol ogi cal impact for a1 1 disposal operations shall be 1 imi ted to a total body or organ dose of a maximally exposed member of the public of less than one mremlyear (less than 5 mrem/year to an inadvertent intruder). Revision Date 3/2/90 B-6 United States Nuclear Regulatory Commi ssi on June 28, 1989 c Page 2 Due to our expected need to utilize the proposed methodology of land application of septic waste on-site during the spring of 1990, we request your review and approval of this proposed disposal method by the end of the first quarter of 1990. We trust that the information contained in the submittal is sufficient; however, should you have any questions or require further information concerning this matter, please contact this office Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION Robert W. Capstick, Jr. ti censi ng Engineer / MSSlemd Enclosures cc: USNRC - Region I USNRC - Resident Inspector, VTNPS Revision Date 3/2/90 8-7 ATTACHMENT 1 VERMONT YANKEE NUCLEAR POWER PLANT APPLICATION FOR APPROVAL TO ROUTINELY DISPOSE OF SEPTIC WASTE WITH M~NIMAL LEVELS OF RADIOACTIVITY - Revision Date 3/2/90 B-8 ATTACHMENT 1 VERMONT YANKEE NUCLEAR POWER PLANT Application for Approval to Routinely Dispose of Septic Waste With Minimal Levels of Radioactivity 1 .O INTRODUCTION Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requests approval, pursuant to 10CFR20.302(a). of a method proposed herein for the routine disposal of slightly contaminated septic tank waste. Vermont Yankee proposes to dispose of this waste by spreading it on designated areas within the plant's site boundary fence. This application addresses specific information requested in 10CFR20.302(a). 2 .O HASTE STREAM DESCRIPTION The waste involved in this application consists of residual solids and water associated with the sewage collection system at Vermont Yankee. The plant's sewage systems are of the septic tank and disposal field type. The two systems servicing the majority of the plant's sanitary waste are identified as (1) main septic system and (2) the south sewage disposal system. - The main septic system (design flow capacity 4,950 gallonsfday) consists of a wastewater lift station, septic tank, and dual alternating disposal fields located on the north side of the plant. This system services the main complex of buildings central to the plant and processes approximately 3,500 gallons of wastewater per day. The septic tank, shown in Figure (l), will typically contain 9,250 gallons of septage. The south sewage disposal system is a newly-installed (January 1989) pressurized mound system, which is used in lieu of the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. The new system is composed of a septic tank (5,700 gallon capacity, see Figure 2). pumping station, and pressurized mound disposal field. When dosing the field. a force main pressurizes the disposal field's piping system with the septic tank effluent, which distributes throughout the field. The south sewage disposal system has - Revision 9 Date 3/2/90 the design flow capacity to process 4,607 gallons of wastewater per day. The system is typically loaded at approximately 2,500 gallons per day during normal plant operations. Figure (3) indicates diagrammatically the flow of both potable and wastewater throughout Vermont Yankee. 4 Both the main septic system and the south sewage disposal system's septic tanks collect waste from the plant's lavatories, showers, kitchens, and janitorial facilities outside the Radiological Control Area (RCA). No radioactivity is intentionally discharged to either of the septic systems. However, pl ant i nvesti gati ons into the source of 1 ow 1 eve1 s of contami nati on found in septic waste have identified that very small quantities of radi'oacti ve materi a1 s, which are bel ow detection 1 imi ts for radioactivity releases from the RCA, are carried out of the control area on individuals and accumulate in the septic waste collection tanks by way of floor wash water, showers, and hand washing. As a means of minimizing the transport of radioactive materials into the septic collection tanks, the primary source of ter bag a the radioactivity ( to remove suspended janitorial sink. .e., floor wash water) is now poured through a fi solids and dirt before the water is released into The majority of the radioactivity found in waste sludge has been associated with the main septic tank. Grab samples of sludge from the bottom of the COB and main septic tank were analyzed by gamma spectroscopy with the foll owing results of pl ant - re1 ated radi onucl ides : d COB Sludge (June 8, 1988) Main Tank Sludge (June 8, 1988) IsotoDe CS-137 Co - 60 Mn - 54 Zn - 65 Co-60 CS - 134 CS - 137 Activity Concentration fl Siqma (DCi/kq Met) 10.3 rt 1.8 45.4 k 3.1 39.3 f 4.3 853.0 f 12.0 52.7 f 8.2 13.0 j, 2.2 120.7 f 5.2 Revision Date 3/2/90 B-10 The principle radionuclide is Cobalt-60, which accounts for 79% of the plant related activity in the septage samples. smear samples taken for 10CFR61 waste characterizations, the septage sample from the main tank correlates very close with the distribution of radionuclides identified in-plant as shown below: In comparison to in-plant 4 Re1 ati ve I sotoDi c Di st ri buti ons IsotoPe In-P1 ant Smears Main lank Sludge Mn - 54 Zn - 65 co-60 CS - 134 CS - 137 3.6% 81.5 3.3 0.4 10.3 3.6% 79.1 4.9 1.2 11.2 Additional analyses of the main tank septage showed that the liquid portion of the collected sample did not contain any plant-related activation or fission products, and that essentially all of the activity i.n the waste was associated with the solid sludge fraction. The average density of the collected sludge was found to be approximately equal to that of water, with a wet to dry ratio of 25.4 to 1. "4 Both the liquid and solid fractions of the main tank septic waste were also analyzed for strontium with no detectable activity found. The liquid portion of the waste sample was also analyzed for tritium with no activity above the minimum detectable levels found. Appendix A to Attachment 2 contains the laboratory analysis reports of the samples taken from the COB and main septic tanks. Prior to identification of the plant-related radioactivity in septage waste, the COB holding tank was being pumped on the average of twice per week, with the sludge and waste liquid transported off-site primarily to the Brattfeboro, Vermont, sewage treatment facility. Waste from the main septic tank was being pumped and transported off-site for disposal on the average of twice per year. Revision Date 3/2/90 B-11 With the replacement of the COB holding tank by the new south sewage disposal system, and the requested implementation of on-site land disposal of accumulated septic waste, the frequency of collection tank pump-outs with land application of the waste is expected to be once per year. With the past pump- out frequency of the main tank being every six months, the accumulation of sludge at the bottom of the tank was well below its design capacity. During the 1988 sample collections, it was estimated that the sludge thickness was less than 1 foot of its 6-foot depth. However, for conservatism in the radiological evaluations, it is assumed that the sludge layer in the main septic tank and south disposal tank occupies 30% of their combined design volume, and that the frequency of pump-outs is semiannual as opposed to the expected annual cycle. Also, as noted above from laboratory analyses of the sludge layer taken from the bottom of the main tank, the average density of the tank contents is approximately equal to that of water, with a wet-to-dry ratio of 25.4 to 1. Hence, the weight of solids (W,,,) being disposed of is estimated, for purposes of this bounding dose assessment, to be approximately: 4 Wso, = 14.950 [gall x 3,785.4 Eccfgall x Ekg/ccl x 0.30 [solids fraction] x (1125.41 Cdrylwet ratio] - 700 Ekgl per pump-out of both tanks or, 1,400 kg of dry solids per year. 3.0 DISPOSAL METHOD Approval of this application will allow Vermont Yankee to dispose of septage by utilization of a technique of land spreading or surface injection in a manner consistent with all applicable state of Vermont health regulations regarding disposal of septic waste. Details of the chemical and biological controls necessary to satisfy state health code requirements are provided in Reference

5. The septage will be spread or surface injected on land areas owned by Vermont Yankee and situated within the plant's site boundary.

Transportation of the septage waste to the disposal areas will involve pumping from one of the septic waste collection tanks (i.e., main septic tank, COB holding tank, Revision Date 3/2/90 B-12 new replacement COB septic tank, or from any other on-site septic waste collection point) into an enclosed truck-mounted tank. The enclosed tank truck is used to prevent spillage while in transit to the disposal areas. The septage will be transported to one of the two disposal sites designated for -.c ankee, and applied at a fixed rate state of Vermont for heavy metals radioactivity content such that exceed established dose land application for septage from Vermont based on either limitations imposed by the or organic content of the waste, or on the projected maximum individual doses wi 11 no objectives. 3.1 Seutic Haste Disposal Procedure Gamma isotopic analysis of septic waste shall be made prior to each disposal by obtaining a representative sample from each tank prior to pump- out. At least two septic waste samples will be collected from each tank to be pumped by taking a volumetric column of sludge and waste water which allows for analysis of the solid's distribution and content from top to bottom of each tank. The weight percent of solid content of the collected waste will be determined and applied to the gamma isotopic analysis in order to estimate the total radioactivity content of each tank to be pumped and spread on designated disposal fields. - These gamma isotopic analyses of the representative samples will be performed at the environmental Technical Specification lower limit of detection (LLD) requirements for liquids (see Technical Specification Table 4.9.31 in order to document the estimation of radiological impact from septage disposal . The radionuclide concentrations and total radioactivity identified in the septage will be compared to the concentration and total curie limits established herein prior to disposal. The methodology and limits associated with determining compl i ance with the disposal dose and activity criteria are described in Attachment

2. If the concentration and total activity limits are met, compliance with the dose assessment criteria will have been demonstrated since the radiological analysis (Section 4.5 and Attachment
2) was based on evaluating the exposure to a maximally exposed individual and inadvertent intruder after the accumul ati on of twenty years of periodic semi annual d Revision Date 3/2/90 8-13 spreading of the septic waste on a single (2 acre) plot within one of the designated disposal areas. If the activity limit per disposal area is projected to be exceeded, the appropriate exposure pathways as described in Section 4.5 will be evaluated prior to each additional application, or a separate plot within the designated disposal area will be utilized.

--cl Annually, for years in which disposal occurs, the potential dose impact from disposal operations conducted during the year, including the impact from previous years, will be performed and results reported in the plant's Semi annual Radioactive Effl uent Re1 ease Report which i s f 1' 1 ed after January 1 A1 1 exposures wi 11 be assessed uti 1 i zi ng the methodot ogy described in Attachment

2. The established dose criteria requires that all applications of septage within the approved designated disposal areas shall be limited to ensure the dose to a maximally-exposed individual be maintained less than 1 mremlyear to the whole body and any organ, and the dose to the inadvertent intruder be maintained less than 5 mrem/year.

The total activity based on the measured radionuclide distribution for any single disposal plot is not expected to exceed the following: Maximum Accumul ated Per Acre Isotope -1 ~.lim wCi 3 Radi oacti vi ty A1 1 owed Mn - 54 Zn - 65 Co-60 CS - 134 CS-137 1.4 120.0 1.4 0.7 46.5 If any of the above radionuclides are projected to exceed the indicated activity val ues , then dose cal cul ati ons wi 11 be performed prior to spreading, in accordance with the methods detailed in Section 4.2.2 of Attachment 2, to make the determination that the dose limit criteria will not be exceeded. Revision Date 3/2/90 8-14 The concentration of radionuclides in any tank of septic waste to be disposed of will also be limited to a combined Maximum Permissible Concentration of Water (MPC) (as listed in 10CFR. Part 20, Appendix B, Table 11, Column 21 ratio of less than or equal to 0.1. 1_ For radi ol ogi cal control , each appl i cati on of septage wi 11 be appl i ed on the designated land area by approved plant procedure which adheres to the following assumptions which were used in developing the dose impact: 0 During surface spreading or injection, the septage. and any precipitation falling onto or flowing onto the disposal field, shall not overflow the perimeter of the designated area. 0 Septage shall not be surface spread or injected into the top 6-inch soil layer within 300 feet from any drinking water well SUPPl Y . 0 Septage shall not be surface spread closer than 300 feet nearest dwelling or public building (or within 100 feet injected into the top 6-inch surface layer). from the f 0 Septage shall not be surface spread closer than 50 feet or within 25 feet if injected into the top 6-inch surface layer) from any roads or site boundary adjacent to land areas. 0 Septage shall not be surface spread within 100 feet (or within 50 feet if injected into the top 6-inch surface layer) of any surface water (rivers, streams, drainage ditches). 0 Low areas of the approved fields, subject to seasonally high groundwater levels, are excluded from the septage application In addition to the radiological controls to limit the total accumulation of radioactive materials released by septic waste spreading, state of Vermont health code requirements will be followed to ensure the protecti on of the pub1 i c and envi ronment f rom chemi cal and bi ol ogi cal hazards. The application rate and acreage will be determined prior to each J Revision Date 3/2/90 B-15 disposal operation. This will vary with the chemical composition of the septage, the percent solids, and the radioactive concentrations. --.- 3.2 Administrative Procedures Complete records of each disposal will be maintained. These records will include the concentration of radionuclides in the septage, the total volume of septic waste disposed, the total activity in each batch as well as total accumulated on the disposal plot at time of spreading, the plot on which the septage was applied, and the results of any dose calculations required. The annual disposal of septage on each of the approved plot areas will be limited to within the established dose, activity, and concentration criteria noted above, in addition to limitations dictated by chemical and bi ol ogi cal condi ti ons. Dose guide1 i nes, and concentration and acti vi ty limits, will be maintained within the appropriate values as detailed in Attachment

2. Any farmer using land which has been used for the disposal of septic waste will be notified of any applicable restrictions placed on the site due to the land spreading or injection of waste. d 4.0 EVALUATION OF ENVIRONMENTAL IMPACT 4.1 Site Characteristics 4.1.1 Site Toposracihv The proposed disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site, which is located on the west bank of the Connecticut River in southwestern Vermont at 1 ati tude 42 degrees, 47 minutes north and longitude 72 degrees 31 minutes west. Both fields are on plant property within the site boundary and surrounded by a chain link fence. i Revision Date 3/2/90 B-16 Site A contains an approximate eight-acre parcel of usable land centered approximately 2,200 feet northwest of the Reactor Building.

Site B contains about two acres and is centered approximately 1,700 feet south of the Reactor Building. The usable acreage of both the north and south disposal fields is restricted to those areas which have no slopes greater than five percent to limit surface runoff. A radiological assessment based on the 1988 measured radioactivity concentrations in sludge has determined that a single two-acre plot would be sufficient for the routine disposal of septage for twenty years without exceeding the dose criteria to maximum exposed individual or inadvertent intruder. As a result, the eight-acre field to the northwest could be divided into four disposal plots, with the two-acre site at the south end of the plant site, providing a fifth plot. A portion of the United States Geological Survey topographic map (Brattl eboro quadrangle), showing the plant site. is presented in the Final Safety Analysis Report (FSAR) as Figure 2.5-1. A plan map showing the plant site and the disposal sites is given on Figure 4. - The sites are located along a glacial terrace on the west side of the Connecticut River. This terrace extends about 3,000 feet west rising gently and then more abruptly to a higher terrace and then to dissected uplands. Distance to the east from the disposal sites to the river is at least 100 feet if septage is disposed of by surface spreading within the designated areas, or 50 feet if septage is injected directly into the soil. - Relief of the proposed disposal sites is low, with elevation ranging between 250 feet and 265 feet (msl). Mean water surface elevation of the adjacent river is about 220 feet. The topographic character of the s with this use. The spreading of septage effect on the topography of the area. te and surrounding area is compat at these locations will have no bl e Revision Date 3/2/90 B-17 4.1.2 Site Geo1oq.y 1 Profiles of site exploratory borings are shown in the FSAR in Figures 2.5-8 through 2.5-11. Current site characteristics as determined from a recent detailed site investigation can be found in Reference

5. Composition of surfacial materials is compatible with the proposed use of the site for septic waste disposal.

4.2 Area Characteristics 4.2.1 Meteorol oqy The site area experiences a continental-type climate with some modification due to the marine climate which prevails at the Atlantic seacoast to the east. Annual precipitation averages 43 inches and is fairly evenly distributed in each month of the year. Potential impacts on septic waste disposal include occasional harsh weather: ice storms, severe thunderstorms, heavy rains due to hurricanes, the possibility of a tornado, and annual snowfall of from 30 to 118 inches per year. In addition, frozen ground can occur for up to 4 months of the year. - Septage spreading will be managed by written procedure such that material which is spread or a mix of that material with precipitation will not overflow the perimeter of the disposal site. Additional information on meteorology of the site can be found in Section 2.3 of the Final Safety Analysis Report. 4.2.2 Hvdrol 0q.y Hydrology of the site and local area is tied closely to flow in the adjacent Connecticut River. River flow is controlled by a series of hydroelectric and flood-control dams including the Vernon Dam which is about 3,500 feet downstream of the site. I Revision 9 Date 3/2/90 B- 18 All local streams drain to the Connecticut River and the site is in the direct path of natural groundwater flow from the local watershed easterly toward the river . Site groundwater 1 eve1 is i nfl uenced by both precipitation and changes in the level of ponding of the Connecticut River behind the Vernon Dam due to natural flow or dam operation. I' ed by numerous dams inc year flood is about 228 Flood flows on the Connecticut are control Elevation of the 100 five upstream of the site. udi ng ft (msl); and, thus, well below the elevation of the proposed site which ranges from about 250 to 265 feet (mslf. The 100-year flood level is based on information presented in References (1) and (2). Septage disposal by means of land spreading on the proposed site will have no adverse impact on area hydrology. Further information about site hydrology is in Section 2.4 of the FSAR. 4.3 Water Usase 4.3.1 Surface Water The adjacent Connecticut River is used for hydroelectric power, for cooling water for the Vermont Yankee plant, as well as for a variety of recreational purposes such as fishing and boating. The Connecticut River is not used as a potable water supply within 50 miles downstream of the plant. Locally, water from natural springs are used for domestic and farm purposes. FSAR Table 2.4.5 and Figure 2.4-2 show springs used within a 1-mile radius of the site. FSAR Table 2.4.4 and Figure 2.4-1 show water supplies with surface water sources which are within a ten-mile radius of the site. There will be no impact on surface water usage or quality as a result of septage disposal due to the required separation distances between surface waters and the disposal plots. - Revision Date 3/2/90 B-19 4.3.2 Groundwater - Based on a review of groundwater measurements in various site borings presented in the FSAR and References 3 and 5, an upper estimate of groundwater levels at the plant is about 240 feet. Considering the proximity of the Connecticut River and Vernon Pond, with a mean water surface elevation of 220 feet, this estimate for the groundwater level appears to be reasonable. Given the topography of the proposed disposal sites, it is highly unlikely that the groundwater level will be within 3 feet of the disposal area surface elevation. Prior to each application of septic waste to a disposal plot, the groundwater level in nearby test wells will be determined and no application will be allowed if the groundwater level in the vicinity of the disposal plot is found to be less than 3 feet. Groundwater provides potable water for public wells as shown in FSAR Table 2.4.5 and Figure 2.4-1. Groundwater flow in the vicinity of the proposed disposal sites is towards the Connecticut River. There are no drinking-water wells located between the site and the river. Therefore, it is highly unlikely that any drinking water wells could be affected by septage disposal. FSAR Figure 2.4-2 and Table 2.4-5 present information on private wells near the plant. 2 The Vermont Yankee on-site wells provide water for plant use. This supply is routinely monitored for radioactive contamination. To quantify the impact of septage disposal on the Connecticut River, a conservative groundwater/radionucl ide travel time analysis was performed. For an assumed average travel distance of 200 feet from the disposal site to the river. a groundwater travel time of 408 days was estimated from Oarcy's Law. This estimate is based on a permeability for the glacial till of 10 gpdift', a hydraulic gradient of 0.11 ftlft, and a soil porosity of 0.3. This analysis conservat'ively assumed that the septage placed on the ground was immediately available to the groundwater. In practice, a minimum of 3 feet separation between groundwater and the surface will be required at time of application of the septic waste. I Revision Date 3/2/90 9-20 Due to ionic adsorption of the radionuclides on solid particles in the groundwater flow regime, most radionuclides travel at only a small fraction of the groundwater velocity. For the radionuclides present in the sludge, retardation coefficients were developed from NUREWCR-3130 (Reference 4). Retardation coefficients for Co-60, Cs-137, and Cs-134 were directly obtained from NUREGICR-3130. The coefficients for Zn-65 and Mn-54 were conservatively estimated using NUREGICR-3130 as a guide. The radionuclides, their half- lives, retardation coefficients, and their travel time to the river are summarized in Table 1. d TABLE 1 Radionuclide Travel Times Retardation Travel Time Radi onucl i de Hal f ti fe Coefficient to River Co-60 5.3 years 860 961 years CS-137 30.2 years 173 193 years CS - 134 2.1 years 173 193 years Zn - 65 244 days 3 1,224 days Mn - 54 312 days 3 1,224 days The radiological impact on the river for the radionuclides reaching the river under this conservative analysis is discussed in Attachment

2. Water usage of the Connecticut River downstream from the disposal area is limited to drinking water for dairy cows, irrigation of vegetable crops, and irrigation of cow and cattle fodder. Based on the assessments noted above, it is concluded that groundwater sources will not be adversely impacted as a result of septage disposal on the proposed site. 4.4 Land Use Both the eight-acre and two-acre sites are currently part of the Vermont Yankee Nuc plant's site boundary which is enclosed by a proposed for the disposa ear Power Plant Site ins chain link fence. It is areas de the Revision Date 3/2/90 E-21 undeveloped except for transmission line structures which traverse a portion of the northern disposal area. Development potential is under the control of Vermont Yankee.

At present, the eight-acre site on the north end of the plant property is used by a local farmer for the growing of feed hay for use with his dairy herd. No curtailment of this activity as a result of the low levels of radioactivity in septage will be necessary. Utilization of the proposed sites for septic waste disposal will result in no impact on adjacent land or properties because of the separation of the disposal plots from off-site properties, the general movement of groundwater toward the river and away from adjacent land areas, and the very low levels of radioactive materials contained in the waste. Administrative controls on spreading and the monitoring of disposal area conditions will provide added assurance that this proposed practice will not impact adjacent properties. 4.5 Radiolosical ImDact In addition to state of Vermont limits imposed on septage spreading, based on nutrient and heavy metal content, the amount of septage applied on each of the proposed disposal plots will also be procedurally controlled to insure doses are maintained within the stated limits. These limits are based on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIFINESP-037, August 1986). The proposed dose criteria require that the maximally exposed member of the general public receive a dose less than 1 mrem/year to the whole body or any organ due to the disposal material, and less than 5 mrem/year to an inadvertent intruder. "_ To assess the doses received by the maximally-exposed individual and the inadvertent intruder, six potential pathways have been identified. These i ncl ude: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, _, Revision Date 3/2/90 8-22 (c) Ingestion of leafy vegetables, ._- (d) Ingestion of stored vegetables, I I I I 4. (f) Ingestion of meat, and (9) Ingestion of milk. The liquid pathway was also evaluated and determined to be insignificant. Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with difference between the two related to the occupancy time. analyses include: The basic assumptions used in the radiological (a) Exposure to the ground contamination and to resuspended radioactivity is for a period of 104 hours per year during Vermont Yankee active control of the disposal sites, and continuous thereafter. The 104-hour interval being representative of a farmer's time on a plot of land (4 hours per week for 6 months). (b) The septic tanks are emptied every two to three years. (The assumed practice is to pump septic tanks once per year. The actual practice may be to pump septic tanks every two to three years. 1 (c) The tank radioactivity remains constant at the currently determined level. To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed in Section 2 were increased by 3 sigmas. That is, the activity concentrations employed in dose assessment and the total radioactivity content per pump-out (at 700 kg of solids per batch) are as follows: -I' [ Revision 23 Date 05/12/99 B-23 Upper-Bound Activity Upper-Bound Activity I sot ope Concentration EpCilks drvl Content [Ci /tankful ) fln - 54 Zn - 65 Co - 60 CS-134 CS - 137 1,348 23,060 1,620 322 4,100 9.436E-07 1.614E-05 1.134E-06 2.254E-07 2.870E-06 (d) The radiation source corresponds to the accumulation of radioactive material on a single plot (two-acre) within the proposed disposal sites over a period of 20 years (40 applications at 6-month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used with an application frequency of once per year.) (e) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, a1 1 dispersed radioactive material remains on the surface and forms a source of unshielded radiation. (In practice, the septic waste will be either surface spread or directly injected within the top 6 inches of the disposal plot, in which case, the radioactive material will be mixed with the soil. This, in effect, would reduce the ground plane source of exposure by a factor of about four due to self-shielding.) (f) No radioactive material is dispersed directly on crops for human or y through root uptake. animal consumption, crop contamination being on (g) The deposition on crops of resuspended radioact smal 1 . vity is insignificantly Revision Date 3/2/90 8-24 (h) Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases,with the exception that the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for direct human consumption are grown on any of the proposed disposal plots). (i It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder). (j) For the analysis of the impact after Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil: but, nonetheless, undergoes resuspension at the same rate as surface contamination. From radio1 ogi cal impact assessments associated with the di sposa septage on different plot sizes (Attachment 21, it was determined that single two-acre plot within the disposal sites would accommodate the 1 mrem/year prescribed dose to the critical organ of the maximally exp individual for a period of up to 20 years, as well as the 5 mrem/year of a sed 1 prescribed dose to the inadvertent intruder after control is assumed to be relinquished. The calculated potential radiation exposures following the spreading of 40 combined (main septic system and south disposal system) tankfuls (at six-month intervals) on a single two-acre plot are as follows: Control of Disoosal Sites Radiation Exposure Individual /Orqan Controlled by VYNPS 0.1 mremfyr Chi 1 d/Whol e Body (Maximum Exposed Individual 1 0.2 mrem/yr Maximum ChildlCiver Uncontroll ed 1.3 mremlyr Adul t/Whol e Body (Inadvertent Intruder) 3.9 mrem/yr Maximum Teenager/Lung - Revision Date 3/2/90 8-25 The individual pathway contributions to the total dose at the end of the 20-year accumulation of waste deposited on a single two-acre plot are as listed below: - Pathway-Dependent Critical Orqan Doses Pathway Ground Irradiation Inhalation Stored Vegetables Leafy Vegetable Milk Ingestion Meat Ingestion Maxi mal 1 y Exposed Inadvertent Intruder Indi vi dual /Organ Cri ti caf Individual /Organ (Chi ld/ Li verf (TeenagerlLung) (mremlyear) (mremiuear) 0.0576 0.00122 0.0913 0.00467 0.0421 0.00249 1.16 2.74 0.00601 0.00040 Of00229 0.00012 TOTAL 0.1994 3.909 In addition, an isoto'pic breakdown of the critical organ dose results listed above is shown in the following table: Isotopic Breakdown of Maximum Radiation Exposures Radioactivity Exposure Description Isotope [uCi /2 Acres] [ m r em/y r 3 During Vermont Yankee Mn - 54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites. Zn - 65 2.801 0.0230 Maxi mal 1 y Exposed CS - 134 1.457 0.00231 Individual/Organ: CS-137 92.59 0.118 Chi 1 d/Li ver TOTAL 0.199 After Vermont Yankee Mn - 54 2.831 0.0144 control of sites is Co- 60 235.3 3.76 ref i nqui shed. Zn - 65 2.801 0.00983 Inadvertent Intruder CS - 134 1.457 0.000505 Critical Individual / CS - 137 92.59 0.1247 Organ: Teenager/Lung TOTAL 3.91 Revision Date 3/2/90 B-26 Of interest are also derived dose conversion factors which provide a means of ensuring septage disposal operations within the prescribed radiological guidelines. The critical -organ (worst-case) all-pathway values per acre are as follows: I A1 1 -Pathwau Critical -0rqan Dose Conversion Factors Durinq Vermont Yankee Control of Disposal Sites Exposure I sotope Individual /Orqan ~ Imrem/vr-uCi /acre1 Mn - 54 Adul t/GE-LLI GO-60 Teenager/ Lung Zn-65 Chi 1 d/Li ver CS-134 Child/Liver CS-137 Chi 1 d/Bone 3.74E-4 7.14E-4 1.64E-2 3.18E-3 2.66E-3 The calculational methodology and details of the radiological assessment and proposed operational controls on total activity and concentration of waste to be disposed are presented in Attachment

2. .- 5.0 RADIATION PROTECTION The disposal operation will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specified dose and re1 ease concentration criteria.

c Revision Date 3/2/90 B-27 REFERENCES .d 1. Flood Insurance Study, Vernon, Vermont, Windham County, FEMA, Community No. 500137. July 25, 1980. 2. Flood Insurance Study, Town of Hinsdale, New Hampshire, Cheshire County, FEMA, Community No. 330022, October 15. 1980. 3. Vermont Yankee Well Development Evaluation by Wagner, Heindel, and Noyes, Inc. July 10, 1986. 4. NUREGfCR-3130, Influence of Leach Rate and Other Parameters on Groundwater Migration, by Dames & Moore, February 1983. 5. Vermont Yankee Nuclear Power Corporation On-Site Septage Disposal Plan, by Wagner, Heindel, and Noyes, Incorporated, June 1989. Revision 9 DAte 3/2/90 8-28 FIGURE 1 MAIN SEPTIC TANK Revision 9 Date 3/2/90 6-29 FIGURE 2 SOUTH DISPOSAL SYSTEM SEPTIC TANK B Y Revision 9 Date 3/2/90 B-30 I I I I I I 1 I 1 1 I 1 I I I I 1 I FIGURE 3 POTABLE AND WASTE WATER FLOW Revision Date 3/2/90 8-31 FIGURE 4 SEPTIC WASTE DISPOSAL AREAS Revision Date 3/2/90 B-32 (This attachment to Appendix B is incorporated into the ODCM by reference due to size. part of Correspondence Letter BVY 89-59.) A complete copy is on file with Vermont Yankee Document Control as 4 ATTACHMENT 2 VERMONT YANKEE NUCLEAR POWER PLANT RADIO LOGI CAL ASSESSMENT OF ON-SITE DISPOSAL OF SEPTIC WASTE and PROPOSED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RAD1 0 LOGI CAL LIMITS Revision Date 3/2/90 B-33 APPENDIX D ASSESSMENT OF SURVEILLANCE CRITERIA FOR GAS RELEASES FROM WASTE OIL INCINERATION -J Revision 16 Date 10/28/93 D-1 APPENDIX D INTRODUCTION: ASSESSMENT OF SURVEILLANCE CRITERIA FOR GAS RELEASES FROM WASTE OIL INCINERATION The Nuclear Regulatory Commission amended its regulations (10CFR20) in a Federal Register Notice (Vol. 57, No. 235; page 57649 / Monday, December 7, 1992) that permitted the on-site incineration of contaminated waste oil generated at licensed nuclear power plants without the need to ,<mend existing operating licenses. This action will help to ensure that the limited capacity of licensed low level waste disposal facilities is used efficiently while maintaining releases from operating nuclear power plants at levels which are "as low as reasonably achievable." Incineration of this class of waste must be in full compliance with the Commission's current regulations that restrict the re1 ease of radioactive materi a1 s to the envi ronment . Any other appl i cab1 e Federal , State, or 1 oca1 requi rements that re1 ate to the toxic or hazardous characteristics of the waste oil would also have to be sati sf i ed. Incineration of waste oil is to be carried out under existing effluent limits, recordkeeping and reporting requirements. Specifically, licensees must comply with the effluent release limitations of lOCFR Part 20, and Part 50; Appendix I. This Technical Specifications (Section 3.8). The dose contribution to members of the public resulting from the on-site incineration of contaminated waste oil must not cause the total dose or dose rate from all effluent sources to exceed the dose or concentration limits imposed by lOCFR20, 10CFR50; Appendix I, and the Radiological Effluent Technical Specifications (RETS). It is expected that the actual contribution to public exposures caused by waste oil burning will be a small fraction of the site's effluent limits, as well as a small portion of the total releases from the site. d, includes the site gaseous pathway dose and dose rate limits contained in the plant's SOURCE DESCRIPTION Contaminated waste oil suitable for on-site incineration can be burned in the Waste Oil Burner located in the North Warehouse. The burner has its own exhaust stack situated on the roof of the warehouse. However, due to the short height of the exhaust stack above the roof line, this release point is considered to be a ground level point source for modeling discharges to the environment. In addition, the building wake effects from the North Warehouse are assumed to be independent of the larger Turbine HalllReactor Building complex due to its distance from these main structures. Consequently, the re1 atively smal 1 size of the North Warehouse 1 eads to -..... Revision _16 Date 10/28/93 0-2 meteorological dispersion factors that are conservative with respect to the dispersion factors for the main plant structures. c The waste oil burner is rated to process oil at a 2 gal ./hour from a 500 gallon day tank. The offgas flow rate for the burner is rated as 199 cfm. This provides an air to oil dilution during the incineration of 44,800. WASTE OIL SAMPLINGI'SURVEILLANCE REQUIREMENTS The oil burner stack is not equipped with continuous air monitoring or sampling capability for the direct determination of radiolog'ical effluent releases during the incineration process. As a consequence, sampling and analysis of the waste oil prior to its incineration is necessary to project the dose and dose rate consequences of burning contaminated oil. Calculations of projected dose from the incineration of total quantity of oil to be added to the Waste Oil Burn Day Tank for each series of burns will be performed in accordance with the methods in the ODCM and compared to the accumulated site total dose for that period before initiation of incineration. Dose rate determinations will be determined by averaging the projected dose for the quantity of radioactivity determined to be present in the oil over the expected duration of the burn necessary to incinerate the total volume to be added to the Day Tank. Inherent in this determination is the assumption that all radioactivity found to be present in each batch of oil will be released to the chamber is assumed in calculating the offsite radiological impact. .- atmosphere during the incineration. No retention of activity in the combustion Normal sampling and analysis methods for gaseous release streams cannot be applied directly to liquids (waste oil 1. Therefore, the sampling and analysis requirements for liquids as identified in Technical Specification Table 4.8.1 shall be used to determine the level of contamination in waste oil. The stated Lower Limits of Detection (LLD) given on Table 4.8.1 provide assurance that undetectable levels of contamination up to the LLD values will not result in a significant dose impact to the maximum offsite receptor. If waste oil was burned continuously for an entire calendar quarter, and the radionuclides listed in the ODCM Dose Conversion Factor Table 1.1-12 were assumed to be present in the oil at the LLD values specified in Technical Specification Table 4.8.1, the resultant maximum organ dose would amount to only 0.28% of the ALARA quarterly limit of 7.5 mrem. The principle limitation in the incineration of waste oil is that the site release limits contained in RETS, and implemented by the ODCM methodology, shall not be exceeded. sufficient sensitivity to ensure that site dose limits will not be exceeded as a consequence of burning slightly contaminated oil. The use of the liquid LLDs on waste oil sample analyses provide Revision 16 Date 10/28/93 D-3 APPENDIX F APPROVAL PURSUANT TO 10CFR20.2002 FOR ONSITE DISPOSAL OF COOLING TOWER SILT d Revision 21 Date 08/14/97 F-1 UNWED STATES NUCLEAR REGULATORY COMMISSION WASISWINOTON. D.C. po565OM)l June 18, 1997 Nn 97-85 LA I 1130 Mr. Donald A. Reid Vice President, Operations Vermont Yankee Nuclear Power Corporation Ferry Road Brattl eboro, VT 05301 The NRC staff's approval of VYNPC's silt disposal request is granted provided the enclosed replacement SE is permanently incorporated into Vermont Yankee's Offsite Dose Calculation Manual as an appendix. Any modification to the proposed action that may be considered in the future must have prior NRC staff approval

SUBJECT:

REVISED SAFETY EVALUATION - APPROVAL PURSUANT TO 10 CFR 20.2002 FOR ONSITE DISPOSAL OF COOLING TOWER SILT - VERMONT YANKEE NUCLEAR POWER STATION (PAC NO. M96371)

Dear Mr. Reid:

By letter dated August 30, 1995, Vermont Yankee Nuclear Power Corporation (VYNPC) requested approval, pursuant to 10 CFR 20.2002, for the onsite disposal of slightly contaminated silt material removed from Vermont Yankee Nuclear Power Station's (Vermont Yankee's) cooling towers. In a safety evaluation (SEI dated March 4, 1996, the NRC staff approved the proposed silt disposal. However, because of discrepancies VYNPC identified between the safety evaluation and VYNPC's letter of August 30, 1995, VYNPC postponed implementation of the silt disposal until resolution of the discrepancies. By letter dated August 2, 1996, VYNPC informed the NRC staff of the discrepancies and requested that the SE be revised accordingly. Recognizing the discrepancies, the NRC staff has prepared the enclosed SE to resolve the discrepancies and to replace the SE of March 4, 1996. Pursuant to the provisions of 10 CFR Part 51, the Commission has published in the Federal Reqister an Environmental Assessment and Finding of No Significant Impact (61 FR 6662). Revision 21 Date 08/14/97 F-2 If you have any further questions regarding this matter, please contact Mr. Kahtan Jabbour at (301) 415-1496. 4 Sincerely , Patrick D. Milano, Acting Director Project Di rectorate 1-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosure:

Safety Eva1 uati on cc w/encl: See next page _. Revision 21 Date 08/14/97 F-3 Vermont Yankee Nuclear Power Corporati on Vermont Yankee Nuclear Power Station cc : e' Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 R. K. Gad, I11 Ropes & Gray One International Pi ace Boston, MA 02110-2624 Mr. Richard P. Sedano, Commissioner Vermont Department of Public Service 120 State Street, 3rd Floor Montpel i er, VT 05602 Pub1 i c Service Board State of Vermont 120 State Street Montpel i er, VT 05602 Chai rman, Board of Sel ectman Town of Vernon P.O. Box 116 w Vernon, VT 05354-0116 Mr. Richard E. McCullough Operating Experience Coordinator Vermont Yankee Nuclear Power Station P.O. Box 157 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq. Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937 Resident Inspector Vermont Yankee Nuclear Power Station U.S. Regulatory Commission P.O. Box 176 Vernon, VT 05354 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Mr. Peter LaPorte, Director ATTN: James Muckerheide Massachusetts Emergency Management 400 Worcester Rd. P.O. Box 1496 Framingham, MA 01701-0317 Agency Mr. Raymond N. McCandless Vermont Di vi si on of Occupati onal and Radi ol ogi cal Heal th Administration Building Montpel i er, VT 05602 Mr. J. J. Duffy Li censi ng Engi neer Vermont Yankee Nuclear Power Corpo'rati on 580 Main Street Bolton, MA 01740-1398 Mr. Robert J. Wanczyk Di rector of Safety and Regulatory Affairs Vermont Yankee Nuclear Power Corp. Ferry Road Brattleboro. VT 05301 Mr. Ross B. Barkhurst, President Vermont Yankee Nuclear Power Ferry Road Brattl eboro, VT 05301 Corporation Mr. Gregory A. Maret. Plant Manager Vermont Yankee Nuclear Power Station P.O. Box 157 Governor Hunt Road Vernon, VT 05354 4 Revision 21 Date 08/14/97 F-4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASlikNOTON, 0.C. zOSdSQOol SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ONSITE DISPOSAL OF SLIGHTLY CONTAMINATED COOLING TOWER SILT VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 1 .O INTRODUCTION By letter dated August 30, 1995, Vermont Yankee Nuclear Power Corporation (VYNPC) requested approval for the onsite disposal of slightly contaminated si 1 t materi a1 removed from Vermont Yankee Nuclear Power Station's (Vermont Yankee's) cooling towers. In a safety evaluation (SEI dated March 4, 1996, the NRC staff approved the proposed silt disposal. However, because of discrepancies between the SE and VYNPC's letter of August 30, 1995, VYNPC postponed implementation of the silt disposal until resolution of the discrepancies. By letter dated August 2, 1996, VYNPC informed the NRC staff of the discrepancies and requested that the SE be revised accordingly. Recognizing the discrepancies, the NRC staff has prepared this SE to resolve the discrepancies and to replace the SE of March 4, 1996. 2.0 BACKGROUND VYNPC has previously obtained NRC staff approval of the onsite disposal of very-low-level radioactive material similar to the proposed silt disposal. By letter dated June 28, 1989, VYNPC proposed the onsite disposal of slightly contaminated septic waste material by land application at Vermont Yankee. By letter dated August 30, 1989, the NRC staff approved this request pursuant to 10 CFR 20.302 (now 10 CFR 20.2002). The NRC staff considered this site-specific application for Vermont Yankee to have insignificant radi ol ogi cal impact because the proposed septic waste materi a1 di sposal invol ved 1 i censed materi a1 containing 1 ess than 0.1 percent of the radioactive material, primarily cobalt-60 and cesium-137, already considered acceptable in the Final Environmental Statement (FES) of July 1972, and involved exposure pathways much less significant than those in the FES. In addition, the proposed septic waste materi a1 di sposal satisfied the foll owing appl i cab1 e boundary conditions for the disposal of licensed material:

a. The whole body dose to the hypothetical maximally exposed individual must be less than 1.0 mremiyear.

Revision 21 Date 08/14/97 F-5 -.-- b. Doses to the whole body and any organ of an inadvertent intruder from the probable pathways of exposure are less than 5 mremlyear

c. The disposal must be at the same site. Following the NRC staff's approval on August 30, 1989, VYNPC implemented the disposal of the contaminated septic waste material as proposed.

By letter dated August 30, 1995, VYNPC requested that the previous authorization for the onsite disposal of very-low-level radioactive material be amended to permit the onsite disposal of slightly contaminated silt septic material, within the boundary conditions of the-previously approved waste material disposal . 3.0 EVALUATION In its fetter of August 30, 1995, VYNPC stated that the proposed si method is the same as the previously approved septic waste disposal and utilizes land spreading in the same onsite areas approved for s disposal. The volume of silt proposed for onsite disposal consists t disposal method, pti c waste of 14,000 cubic feet 1396 cubic meters) accumulated through August 1335 plus approximately 4,000 cubic feet 1113 cubic meters) to be removed from the cool i ng towers during each 18-month operating cycl e. in the currently accumulated silt, based on samples taken by VYNPC in June 1995, is 0.193 millicuries, principally from 0.034 millicuries of cobalt-60 and 0.159 millicuries of cesium-137. The activity contained in the 1_ additional silt to be removed from the cooling towers each 18-month operating cycle is anticipated to be 0.059 millicuries, principally from 0.012 millicuries of cobalt-60 and 0.047 millicuries of cesium-137. The acti vi ty contained LA I 1193 1130 VYNPG's radiological assessment enclosed with its August 30, 1395, letter demonstrates that the combined radiological impact for all onsite disposal operations, the proposed disposal of silt and the previously approved disposal of septic waste material, will continue to meet the applicable boundary conditions (given above) for the disposal of licensed material. Therefore, the proposed onsite disposal of slightly contaminated silt is acceptable. As discussed in VYNPC's letter of August 2, 1966, if the onsite disposal of cooling tower silt or septic waste material would result in exceeding the applicable boundary conditions (given above). then VYNPC must obtain prior NRC staff approval of the disposal. In addition, VYNPC made the following commi tments: a. VYNPC will report in the Annual Radiological Effluent Release Report a list of the radionuclides present and the total radioactivity associated with the onsite disposal activities at Vermont Yankee. "-0 Revision 21 Date 08/14/97 F-6 c AI 1130 4 LA I 1130 b. VYNPC will maintain records of radionuclide concentrations and total activity associated with onsi te disposal activities at Vermont Yankee in accordance with 10 CFR 50.75(g).

4.0 CONCLUSION

The NRC staff finds that the radiological conditions at the Vermont Yankee site (see attachment) that would result from the onsite disposal of slightly contaminated silt material, as proposed by VYNPC pursuant to 10 CFR 20.2002, and the previously approved onsi te disposal of slightly contaminated septic waste material, are within the applicable boundary conditions (given above) for the disposal of licensed material. Therefore, the proposed onsite disposal of slightly contaminated silt removed from Vermont Yankee's cooling towers is acceptable. VYNPC is required to permanently incorporate this SE into the Vermont Yankee Offsite Dose Calculation Manual as an Appendix to document the the radioactive material onsite disposal activities approved for Vermont Yankee, and VYNPC's re1 ated commitments regarding reporting and record keeping. Any additional modification of VYNPC's disposal activities which go beyond those proposed in the August 30, 1995, submittal, and are not addressed above must have prior NRC staff approval. In addition, any onsite disposal of cooling tower silt or septic waste material that would result in exceeding the applicable boundary conditions (given above), must also have prior NRC staff approval. I Principal Contributors: J. Mi nns D. Dorman 6. Harbuck Date: June 18, 1997

Attachment:

Vermont Yankee Site Area Map Revision 21 Date 08/14/97 F-7 FIGURE 4 SEPTIC WASTE DISPOSAL AREAS Revision 21 Date 8/14/97 F-8 VERMONT YANKEE NUCLEAR POWER CORPORATION n RESPONSIBILITY am7 TO ENGINEERINGOFF(CE 58oM(rfff STREET BOLTON. MA 01740 (soel 719-671 I August 30, 1995 BVY 95-97 United States Nuclear Regulatory Commission Washington, DC 20555 ATTN: Document Control Desk

References:

(1) License No. DPR-28 (Docket No. 50-271) (2) Letter from R. W. Capstick. Vermont Yankee, to USNRC, "Request to Routinely Dispose of Slightly Contaminated waste in Accordance with 10CFR20.302(a)", BVY 89-59, June 18, 1989. (3) Letter from M. B. Fairtile, USNRC, to L. A. Tremblay, Vermont Yankee, "Approval Under 10 CFR 20.3021a) of Procedures for Disposal of Slightly Contaminated Septic Waste on Site at Vermont Yankee (TAC No. 73776)". dated August 30, 1989.

Subject:

Request to Amend Previous Approval Granted Under 10 CFR 20.302(a) for Disposal of Contaminated Septic Waste In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.2002 (previously cited 10CFR20.302(a)), enclosed please find the subject application to amend the previously granted approval (Reference

3) to dispose of slightly contaminated septic waste on site at Vermont Yankee by expanding the allowable waste stream to include slightly contaminated Cooling Tower silt material.

This application specifically requests approval to dispose of Cooling Tower silt deposits, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed silt disposal method is the same as the septic waste disposal method requested in Reference 2 and approved in Reference

3. The disposal method utilizes on site land spreading in the same designated areas used for septic waste. Disposal of this waste in the manner proposed, rather than holding it for future disposal at a lOCFR Part 61 licensed facility when access to one becomes available, will save substantial casts and valuable disposal site space for waste of higher radioactivity levels. A radiological assessment and proposed operational controls based on continued on site disposal of accumulated river silt removed from the basins of the plant's mechanical draft cooling towers is contained in Enclosure A. The assessment demonstrates that the dose impact expected from the disposal of silt removed from the cooling towers during normal maintenance will not exceed the dose limits already imposed for septic waste disposal.

The combined radiological impact for all on site disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one rnrerniyear during the period of active Vermont Yankee control of the site, or less than five mremlyear to an inadvertent intruder after termination of active site control. Enclosure B contains a copy of the original assessment and disposal procedures for Revision 21 Date 08/14/97 F-9 VERMONT YANKEE NUCLEAR POWER CORPORATION septic waste (References 2 and 31 for your use and reference in evaluating the proposed amendment. -r Upon receipt of your approval, Enclosure A will be incorporated into the Vermont Yankee ODCM. We trust that the information contained in the submittal is sufficient, however, should contact this office. you have any questions or require further information concerning this matter, please Sincerely. VERMONT YANKEE NUCLEAR POWER CORPORATION James J. Duffy Licensing Engineer Enclosures A & B c: USNRC Region I Administrator (Letter and Enclosure A) USNRC Resident Inspector - VYNPS (tetter and Enclosure A) USNRC Project Manager - VYNPS (Letter and Enclosure A) Revision 21 Date 08/14/97 F-10 ENCLOSURE A VERMONT YANKEE NUCLEAR POWER PLANT ASSESSMENT OF ROUTINE DISPOSAL OF COOLING TOWER SILT IN AREAS ON SITE PREVIOUSLY DESIGNATED FOR SEPTIC WASTE DISPOSAL - Revision 21 Date 08/14/97 F-11 Table of Contents Page 1.0 ~NTRO~UC~IO~ ........................... 3 2.0 WASTE STREAM DESCRIPTION ..................... 4 3.0 DISPOSALMETHOD .......................... 9 3 . I Si 1 t Disposal Procedure Requi rements ............ 9 3.2 Administrative Procedure Requirements ............ 12 4.0 EVALUATION OF ENVIRONMENTAL IMPACTS ................ 13 4.1 Site Characteristics .................... 13 4.2 Radiological Impact ..................... 13 5.0 RADIATION PROTECTION ....................... 23

6.0 CONCLUSION

S ............................ 23

7.0 REFERENCES

............................ 24 . 2 c Revision 21 Date 08/14/97 F-12 VERMONT YANKEE NUCLEAR POWER PLANT Assessment of Routine DiSDOSaf of Coolinq Tower Silt in Areas On-Si te Previous1 Y Designated for Septic Waste Disposal 1 .O INTRODUCTION: Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requested from the NRC in 1989 permission to routinely dispose of slightly contaminated septic waste in designated on-site areas in accordance with 10CFR20.302(a). The NRC responded to this request on August 30, 1989 by granting approval of the proposed procedures for on-site disposal of septic waste concluding that the commitments, as documented in our request, were acceptable provided that our request and analysis be permanently incorporated into the plant's Offsite Dose Calculation Manual (ODCM). Revision 9 to the ODCM (Appendix Bf incorporated the assessment and approval of the methods utilized for on-site disposal of slightly contaminated sewage sludge. In addition to the previously identified solids content of septic waste as a source of envi ronmental , 1 ow 1 eve1 radi oacti ve contaminated materi a1 , cool i ng tower silt deposits resulting from the settling of solids from river water passing through the mechanical draft cooling tower system have been identified - to also contain low levels of plant-specific radionuclides. Periodic removal of the silt from the cooling tower basins is a necessary maintenance practice to insure operability of the cooling system. However, due to the presence of by-product materi a1 s in the si 1 t, proper disposal requi rements must be appl ied to insure that the potential radiological impact is within acceptable limits. This assessment of silt disposal expands the original septic waste disposal assessment to include earthen type materials (cooling tower silt deposits) whi 1 e maintaining the original radi ol ogi cal assessment model i ng and dose 1 imi t criteria that have been approved for septic waste spreading on site. This assessment demonstrates that cooling tower silt can be disposed of in the same manner and under the same dose limit criteria as previously approved for septic waste in Appendix B to the Vermont Yankee ODCM. Implementation of the following commitments as an amendment to the original 10 CFR .d Revision 21 Date 08/14/97 3 F-13 Part 20.302(a) approval for septic waste shall be incorporated into the Vermont Yankee ODCM upon approval by the PJRC. 4 2.0 WASTE STREAM DESCRIPTION: The waste involved in this assessment is residual solids (silt) collected in the basins of the plant's mechanical draft cooling tower system. The silt consists of organic and inorganic sediments and earthen type materials that have settled from the cooling water flow taken from the Connecticut River as it passes through the towers. As a result of de-sludging the tower basins in 1993, an estimated 14,000 cubic feet of silt was accumulated on site. Clean-out operations will also occur periodically to ensure continued system operability. Sample analysis performed to the plant's environmental lower 1 imits of detection requirements, as contained in Technical Specification Table 4.9.3., has identified Cobalt-60 and Cesium-137 in low concentrations as being present in silt collected in 1993. The cooling towers are located at the southern end of the plant facility complex but are not directly connected to any system in the plant that contains radioactivity. The postulated mechanism of how plant-related radionuclides have been introduced into the cooling system silt assumes that past routine effluents discharged from nearby plant gaseous release points through the towers as a heat exchange medium. The cooling water flow provides a scrubbing action as it is breaks up into fine water droplets due to the splash pans of the towers. This scrubbing action washes any airborne particulates out of the. air. Over long periods of operation, any radioactivity removed from the air flow could buildup to measurable levels in silt that settles out in the basins at the bottom of the towers. 1 were entrained in the large mechanically-induced air flow that is pulled Table 1 lists the analyses of twenty-one samples collected from the silt pile removed from the cool i ng tower basins. Radi oacti vi ty measurements, averaged over all the samples, indicate that the silt material can be characterized as containing approximately 50 pCi/kg (dry wt.) of Cobalt-60 and 198 pCifkg (dry wt.) of Cesium-137. Eight of the samples indicated no positive Cobalt-60 above a minimum detectable level achieved for the analysis. Revision 21 Date 08/14/97 4 F-14 Table 1 Sample # Cool i nq Tower Si 1 t Radi oacti vi ty ( 1993 sampl es*) co - 60 (pCi/kg dry) CS - 137 (pCi/kg dry) G12759 G12758 G12757 G12756 G12755 G12754 G12753 G12752 G12751 G12750 G12749 G12748 G12747 G12746 G12745 G12744 G12743 612742 -.- 612724 G12723 G13940 53 72 (14 (17 73 (16 (27 79 (29 35 59 <19 <38 <7 50 40 68 45 71 104 126 144 172 201 245 206 165 240 181 180 107 171 205 209 218 241 220 2 64 195 115 264 218 Average: Max. Min. Standard deviation: 50 126 (7 30

  • Average wet to dry sample weight ratio equal to 1.6 density equal to 1.3 gm/cc. 5 198 264 107 42 Dry weight silt - Revision 21 Date 08/14/97 F-15 For the purpose of estimating the total activity in the silt pile, the less than values in Table 1 are included as positives in the calculation of the average radioactivity concentration. - Cobalt-60, due to its relatively short half life, is typically associated with plant operations when measured in the near environment.

However, Cesium-137 when measured in the environment may have a background component that is not related to power plant operations. Past weapons testing fallout has imposed a man made background level of Cesium-137 in New England soils and sediments that can vary over several hundred pCi/kg. The plant's Environmental Monitoring Program has shown that Connecticut River sediment in the vicinity of Vermont Yankee averages about 123 pCi/kg (dry wt.) of Cesium-137 (Table 2) with no plant related detectable level of Cobalt-60. The value of 123 pCi/kg may represent an estimate of background level of Cesium-137 in sediment that would be subject to entrainment in cooling water flow that enters the plant. In comparing the measured levels of Cesium-137 on Table 1 with the past river sediment level, the average concentration in the cooling tower silt is higher than that of the river sediment data but does fall within the observed range of recorded sediment Cs-137. The river sediment Cesium-137 concentration averages about 62% of the concentration value detected in the tower silt. For purposes of this assessment of plant-related dose impact from the on-site disposal of si1 t material, it is conservatively assumed that all detectable 1 Cs-137 in cooling tower silt is directly related to plant operations. No background component is subtracted from the measured values for this case study since only a single sampling location (down stream) is included in the Environmental Monitoring Program which may not fully describe the true background levels in the region. The total radioactivity for the current 14,000 cubic feet of silt collected on site can be estimated by multiplying this volume by its "as is" density of 2.1 gm/cc (i.e. 1.3 gm/cc dry weight density x 1.6 wetldry weight ratio) and then conservatively assume that the measured average dry weight radioactivity concentrations for Cobalt and Cesium would be the same as in the collected silt. Multiplying the average Cobalt-60 and Cesium-137 concentration in silt by the mass of the collected material produces estimates (Table

3) of total radioactivity that was removed from the cooling tower basin in September 1993. - Revision 21 Date 08/14/97 6 F-16 Table 2 Date Cesium-137 in Connecticut River Sediments*

CS - 137 fpCilkg dry) 61 60 137 176 178 230 62 (174 179 115 62 a5 a4 Average: Max. Min. Standard deviation: 132 230 60 56

  • Sampl es coll ected as part of the Vermont Yankee Radio1 ogical Envi ronmental Monitoring Program (REMPI for river sediment sample location SE-11. Revision 21 Date 08/14/97 7 F-17 Table 3 Estimated Total Radioactive Material for 1993 Tower Clean-Out Volume of Mass Average Total Act. Decayed Act. Silt Concentration (as of 11/93) (as of 6/95) (ft3) fkg) ( pCi / kg 1 (uCi 1 (uCi 1 CO- 60 14.000 8.32E+5 50 42 34 CS - 137 14,000 8.32 E+5 198 165 159 In addition to 14,000 cubic feet of silt already accumulated, it is anticipated that periodic maintenance work in cleaning out the cooling tower basins will generate approximately 4,000 cubic feet of new silt material over each successive 18 month operating cycle. Assuming the same level of plant-related radioactivity concentration that was originally observed, the vity that will require on site disposal can also be estimated.

Table 4 lists an vity that might be present at each 18 month addi ti onal amounts of radi oact foll owing each refuel ing cycl e estimate of the total radioact cl ean - out cycl e. - Table 4 Estimated Total Radioactive Material for Each 18 Month Maintenance Cycle Volume of Mass Average Total Silt Concentration Activity (ft3) (kg) (pCi /kg) (uCi 1 .. ........ ..... .~.,., .............................. ~,." ..__.___.._.._~____._.,..

  • CO-60 4,000 2.38E+5 50 12 CS-137 4.000 2.38E+5 198 57 - Revision 21 Date 08/14/97 8 F-18 3.0 DISPOSAL METHOD: ci The method of silt disposal shall utilize a technique of land spreading in a manner consistent with the current commitments for the on-site disposal of septic waste as approved by the NRC and implemented as Appendix B of the Vermont Yankee ODCM (Reference I). The same land areas designated and approved for septic waste disposal shall be used for the placement of silt removed from the cool i ng tower basins. Determination of the radi ol ogi cal dose impact shall also be made based on the same models and pathway assumptions as indicated in Appendix B of the ODCM. 3.1 Si 1 t Disposal Procedure Reaui rements : Gamma isotopic analysis of silt samples shall be made prior to each disposal by obtaining representative composite samples in sufficient numbers to characterize the material removed from the cooling tower basins. Each gamma isotopic analysis shall be required to achieve the environmental lower limits of detection as indicated for sediment on Table 4.9.3 of the Vermont Yankee Technical Specifications.

The estimation of total radioactivity to be disposed of shall be made based on the average of all composite sample analyses. The estimation of total collected silt on the designated disposal plots. The dose impact from each disposal operation shall be included with all past septic waste and silt spreading operations to ensure that the appropriate dose limits are not exceeded on any waste disposal area for the combination of all past operations. I radioactivity and projected dose impact shall be made prior to placing the The established dose criteria requires that all applications of earthen type materials within the approved designated disposal areas shall be limited to ensure that dose to a maximally exposed individual (during the Vermont Yankee control period) be maintained less than 1 mremlyear to the whole body and any organ, and the dose to an inadvertent intruder following termination of site control be maintained less than 5 mrem/year to the whole body and any organ. Revision 21 Date 08/14/97 9 F-19 The limits on concentrations of radionuclides as addressed in Appendix B to the ODCM for septic waste (i.e., each tank of septic sludge to be disposed are limited to a combined MPC ratio of less than 0.1) were included to ensure proper control was in place to address the situation of small quantities of re1 ati vel y high Concentration mater1 a1 . This 1 imitation does not di rectly apply to silt deposits since the silt is handled as dewatered sediments as opposed to liquid slurries of septic waste. d For dry, earthen type material such as silt, a specific radionuclide concentration limit shall be applied in place of the septic waste liquid MPC ratio. No soil associated with a sample analysis that identifies a plant-related radionuclide in excess of the concentration limits of Table 5 will be permitted regardless of the total pathway dose assessment determined for the quantity material under consideration. For the case where more than one radionuclide is detected, the sum of the ratio rule will be applied. The measured concentration of each radionuclide divided by its limiting concentration value shall be added with the sum of all fractions equal to or less than 1. This limiting condition will prevent small volumes of relatively high specific radioactivity from being spread on the disposal plots, and therefore reduce the potential for creating unexpected hot spots of concentrated material. Table 5 lists, by radionuclide, soil concentration values that would generate an annual external effective dose equivalent of 25 mremlyear if it were assumed that an individual continuously stood on an infinite plane of soil contaminated to a depth of 15 cm. The assumptions of an infinite plane and continuous occupancy are conservative for situations where the amount of contaminated soil identified would not provide for a 15 cm soil depth over an extended surface area and where disposal site access is limited. Twenty-five mremlyear was selected as a reference value based on the fact that it was a suitable fraction of the NRC annual dose limit (100 mrem/year per 10 CFR Part 20.1301) applied to members of the public from all station sources. The 25 mrem/year also equals the EPA dose limit from 40 CFR Part 190 which would apply to real members of the public offsite and allow for credit to be taken in accounting for actual usage patterns such as occupancy time. The external dose factors provided on Table 5 were derived from Table E-2 of NUREWCR-5512 (Reference 3). - Revision 21_ Date 08/14/97 10 F-20 Table 5 Radi onucl i de Dry Soil Maximum Concentration Values Soi 1 Concentration pCi / kg (equal to 25 mremfyr) Cr-51 Mn-54 Fe-59 CO-58 Co-60 Zn - 65 Zr-95 Ag-llOm Sb-124 CS - 134 CS-137 Ce-141 Ce-144 1.51 E+05 5.50E+03 3.83E+03 4.70E+03 1.82E+03 7.85*+03 6.18E-f-03 1.66E-t-03 2.51 *+03 2.95*+03 8.13E+03 7.85E+04 8.75E+04 Assumptions include infinite planar distribution. uniform depth distribution to 15 cm, soil density at 1.625E+06 gm/m3 and external direct dose pathway only with a 100% occupancy factor. I Revision 2 Date 08/14/97 11 F-21 3.2 Administrative Procedure Requirements: .4 Dry silt material shall be dispersed using typical agricultural dry bulk surface spreading practices only in approved disposal areas on site. Complete records of each disposal will be maintained. These records will include the concentration of radionuclides detected in the silt, an estimate of the total volume of silt disposed of, the total radioactivity in each disposal operation as well as the total accumulated on each disposal plot at the time of the spreading, the plot on which the silt was applied, and the results of any dose calculations or maximum allowable accumulated activity determinations required to demonst ate that the dose limits imposed on these land spreading operations have not been exceeded. The determination of the total radioactivity and dose calcu ations shall also include all past septic waste and silt disposal operations that placed low level radioactive material on the designated disposal plots. The periodic disposal of silt on each of the approved land spreading areas will be limited to within the same established dose and radioactivity criteria that have been approved for septic waste disposal. Concentration limits that are applied to the disposal of earthen type that have relatively high concentrations of radioactivity such that direct exposure could not exceed a small proportion (25%) of the annual dose limits to members of the public that is contained in 10 CFR Part 20.1301, .-- materials (dry soil) shall restrict the placement of small volumes of material Any farmer leasing land used for the disposal of silt deposits will be notified of the applicable restrictions placed on the site due to the land spreading of low level contaminated material. These restrictions are the same as detailed for septic waste spreading as given in Reference

1. Revision 21 Date 08/14/97 12 F-22 4.0 EVALUATION OF ENVIRONMENTAL IMPACTS: 'd 4.1 Site Characteri sti cs The designated disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site. Both fields are on the plant property within the site boundary security fence. Site A contains an approximate ten-acre parcel of land centered approximately 2,000 feet northwest of the Reactor Building.

Site B consist of approximately two acres and is centered approximately 1,500 feet south of the Reactor Building. These are the same land parcels approved by the NRC for the land disposal of septic waste and are described in detail in Reference 1 along with the boundary restrictions for the placement of contaminated materi a1 . Radi ol ogi cal assessments of septic waste disposal have determi ned that a single two-acre plot would be sufficient for the routine disposal of that waste stream over a 20-year period without exceeding the dose criteria to a maximum exposed individual or inadvertent intruder. As a result, the ten-acre field to the northwest can be divided into five disposal plots, with the two-acre site at the south end of the plant site providing a sixth plot. It i s therefore concluded that there is sufficient space within the a? ready approved di sposal pl ots to accommodate additional materi a1 f rom the cool i ng the approved dose limit criteria. - tower basins along with the septic waste without the likelihood of exceeding Since the residual organic and inorganic solids associated with river sediment (silt) are similar to the sand and residual organic material remaining after decomposition of septic waste that is removed from the plant's septic tanks, the conclusions of no significant environmental (non-radiological) impact associated with the disposal of septic waste are not changed by the addition of another earthen type material, namely silt. 4.2 Radioloqical ImDact: The amount of cooling tower silt, in combinat di sposal s, wi 11 be procedural 1 y control 1 ed to within the prior approved limits (Reference 1 Revision 21. Date 08/14/97 13 F- 23 on with any septic waste insure doses are maintained . These limits are based on past NRC proposed guidance (described in AIF/NESP-O37), August 1986). The dose criteria require that the maximally exposed member of the general public receive a dose less than 1 mrem/year to the whole body or any organ due to the disposed material and less than 5 mrem/year to the whole body or any organ of an inadvertent intruder. d To assess the doses received by the maximally exposed individual and inadvertent intruder resulting from silt spreading, the same pathway modeling, assumptions and dose calculation methods as approved for septic disposal are used. These dose models implement the methodologies and dose conversion factors as provided in Regulatory Guide 1.109 (Reference 2). Six potential pathways have been identified and include: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, (cf Ingestion of leafy vegetables, (d) Ingestion of stored vegetables. (f) Ingestion of meat, and (g) Ingestion of cow's milk Based on the septic waste evaluations, the liquid pathway was determined to be insignificant. Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with the difference between them related to occupancy time. The basic assumptions used in the radiological analyses include: / (a) Exposure to ground contamination and resuspended radioactivity is for a period of 104 hours per year during the Vermont Yankee active control of the disposal sites and continuous thereafter. The 104-hour interval is representative of a farmer's time spent on a plot of land (4 hours per week for 6 months). (b) For the purpose of projecting and illustrating the magnitude of dose impacts over the remaining life of the plant, it is assumed that the current concentration levels of activity detected in sift remain Revision 21 Date 08/14/97 14 F-24 constant. Table 1 indicates the measured radioactivity levels for Cobalt-60 and Cesium-137 first noted in silt material. (c) The maximum radiation source corresponds to the accumulation of radioactive material on a single plot (two acre> within the approved disposal sites over a period of 13 operating cycles. the next 18 years until after the operating license expires in 2012. The initial application (referenced to June 1995) consists of 14,000 cubic feet of silt collected in 1993 along with the first periodic clean out of the tower basins that adds an additional 4,000 cubic feet. All subsequent applications of 4,000 cubic feet occur at 18-month interval s. This extends over (d) For the analysis of the radiolog Yankee active control of the disposal take place and all dispersed radioact forming a source of unshielded direct cal impact during the Vermont sites, no plowing is assumed to ve material remains on the surface radiation. (e) No radioactive material is dispersed directly on crops for human or animal consumption. Crop contamination is only through root uptake. (f) The deposition on crops of suspended radioactivity is insignificantly small. (g) Pathway data and usage factors used in the analysis are the same as those used in the plant's OOCM assessment of off-site radiological impact from routine releases with the exception that the fraction of stored vegetables grown on the contaminated land was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for human consumption are grown on any of the approved disposal plots). (h) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the operating license expires in 2012 (i.e., the source term accumulated on a single, 2-acre disposal plot applies also for the inadvertent intruder). - Revision 21 Date 08/14/97 15 F-25 (i) For the analysis of the impact after Vermont Yankee control of the site is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil: but nonetheless, undergoes resuspension in air at the same rate as the unplowed surface contarninati on. to the six-inch plow layer reduces the surface dose rate by about a factor of four. For di rect ground pl ane exposure the sel f shi el ding due The dose models and methods used to generate deposition values and accumulated activity over the operating life of the plant are documented in Attachment 2 to Reference

1. Based on the measured concentrations and silt volumes noted in Section 2.0 above, the total radioactivity that remains on the disposal plots after the operating license expires is estimated on Table 6. Table 6 Projected Radi oacti vi tv Bui 1 duD Due to Si 1 t SDreadi nq Nucl i de Contribution Accumulation from Total Remaining from initial 13 cycles at in year 2013 14,000 ft3 (uCi) 4,000 ft3/ea. (uCif (uCi 1 Cobal t - 60 3.2 Cesi urn- 137 104.9 61.9 500.5 65.1 605.4 The calculated potenti a1 radiation exposure fo7 1 owing the spreading of a1 7 silt material anticipated to be generated through the remainder of the operating license on a single, two-acre plot is provided on Table 7. v Revision 21 Date 08/14/97 16 F-26 Table 7 Dose Impact Due to Continued Spreadinq to End of License Disposal Site Access Radi ati on Exposure Individual

/Organ Control 1 ed by VYNPS (rnax. exposed individual 1 Uncontrolled by VYNPS (inadvertent intruder after license termination) The individual pathway contr spreading are shown on Table Pathway 0.228 mrem/yr adul tlwhol e body 0.820 mrem/yr max. childibone 1.46 mremlyr adul tfwhofe body 2.41 mremlyr max. childlbone butions to the total dose due to cont 8. Table 8 Pathway-Dependent Critical Orsan Doses nued silt Maximally exposed Inadvertent Intruder Individuaf/Organ Critical Individual /Organ (ChildIBone) (Chi 1 d/Bone (mrem/year) (mremfyear 1 Ground Irradiation Inhalation Stored Vegetables Leafy Vegetables Milk Ingestion Meat Ingestion Total : - Revision 21 Date 08/14/97 0.0474 0.00814 0.528 0.0265 0.201 0.00833 0.82 17 F-27 0.957 0.685 0.528 0.0265 0.201 0.00833 2.41 In addition, the isotopic breakdown of the critical organ doses listed above (Table 8) for the two detected radionuclides is seen to be: - Table 9 Isotopic Breakdown of Maximum Radiation Exoosures Radioactivity Dose Percent of Description I sotope f uCi 12 acres 1 (mrem/yr 1 total During CS - 137 605.4 0.805 98.2 control of Co-60 65.1 Of 0144 1.8 disposal 0.82 sites Max. organ : chi 1 d/bone Termination CS-137 of disposal Co-60 site Max. organ : chi 1 d/bone 605.4 65.1 2.12 2.41 - 0.29 88.0 12.0 For comparison to the total dose calculated assuming the continued disposal of silt removed from the tower basins through the end of the operating license, the dose from just the original 14.000 cubic feet collected is shown on Table 10. Revision 21 Date 08/14/97 18 F- 28 Table 10 c Dose Impact Due to Sinqle 114,000 ft3) Silt SDreadinq Disposal Site Access Radiation Exposure Individual /Organ Controlled by VYNPS (max. exposed i ndi vi dual in 1995 1 Uncontroll ed by VYNPS (inadvertent intruder after license termination) Tab (14 e 10 shows that the applicat 000 cubic feet) accounts for 0.064 mrem/yr adul tlwhol e body 0.219 mrem/yr max.' chi 1 d/ bone 0.224 mremlyr adul tlwhol e body 0.393 mrem/yr max. childlbone on of the silt material initially collected about 27 percent of the maximum individual organ dose during the control period as compared to the scenario of continued periodic silt spreading over the balance of the operating license. This illustrates that dose impacts from the material currently collected are well below the acceptance criteria of limiting the dose from any two-acre plot to no more than 1 mrem/year during the control period and 5 mrem/year after termination of the license, and is expected to remain below the acceptance cri teri a throughout the pl ant 1 i fe. If unexpected bui 1 dup of radi oacti vi ty in future silt clean-out operations were to occur, the option for use of alternate disposal plots remains available to ensure that the impact from any single, two-acre plot stays within the acceptance criteria. - Also of interest are derived dose conversion factors which provide a means of ensuring that septic and si 1 t disposal operations remain within the prescribed radi ol ogi cal gui del i nes noted above. The critical organ (worst case) and whole body dose factors for all pathways on a per acre bases are Revision 21 Date 08/14/97 19 F-29 given on Table 11 for periods during Vermont Yankee control of the disposal site and on Table 12 for post control periods associated with the inadvertent intruder scenario. The dose conversion factors have been expanded to include other potential radionuclide beyond the original five that were addressed in Reference

1. This provides a means to assess other nuclides if future disposal operations i denti fy addi ti onal radi onucl ides not previ ously observed.

The devel opment of these additional nucl ide dose conversion factors uti 1 i ze the same modeling and pathway assumptions as used to derive the factors for the -original five radionuclides identified in septic waste. The models f-or these site and pathway-specific dose factors are those in Regulatory Guide 1.109 (Reference

2) and are described in detail in Attachment If to Reference
1. .4 + Revision 21 Date 08/14/97 20 F -30 Table 11 4 A1 1 -Pathway Critical Orqan / Who1 e Body Dose Conversion Factors Durinq Vermont Yankee Control of Disposal Sites Critical Organ Whole Body Dose Dose Factor Factor Nucl i de Individual

/Organ fmremlyr per uCi /acre) Cr-51 Mn - 54 Fe-55 Fe-59 CO-58 Co-60 Zn - 65 Zr-95 AgllOm Sb-124 CS - 134 CS-137 I Ce-141 Ce-144 Teen/Lung Chi 1 dfBone Teen/Lung Teen/ Lung Teen/Lung Childiliver Teen/ Lung Teen/GI-LLI Teen/ Lung ChitdlLiver Chi ld/Bone Teen/ Lung Teen/Lung Adul t/GI - LLI 21 1.14E-05 3.75E-04 6.45E-06 4.61 E- 04 3.27 E - 04 7.17E-04 1 A4E-02 4.47E-04 1.32E-02 8.34E- 04 3.18E-03 2.66E-03 1.54E-04 6. OOE- 04 5.76E-06 1.93E-04 1.06E-06 2.13E-04 2.OlE-04 5.31E-04 1.03E-02 1.34E - 04 5.24E-04 3.54E-04 1.28E-03 7.02E-04 1.5OE-05 2.44E Revision 21 Date 08/14/97 F-31 Table 12 All -Pathway Critical Orqan / Whole Bodv Rose Conversion Factors Post Vermont Yankee Control of RisRosal Sites (Inadvertent Intruder) Critical Organ Whole Body Rose Rose Factor Factor Nucl i de Indi vi dual /Organ (mrernlyr per uCi/acre) Cr-51 Mn - 54 Fe - 55 Fe-59 CO-58 Co-60 Zn-65 Zr-95 AgllOm Sb-124 CS - 134 CS - 137 - Ce-141 Ce-144 TeenlLung Teen/ Lung TeenILung Teen/ Lung TeenILung Teen/ Lung ChildILiver TeenILung TeenILung Teen/ Lung Chi 1 d/Li ver Chi ldf8one TeenILung Teen/ Lung 22 5.89E-04 1.02E-02 3.50E-04 2.55E-02 1.59E-02 3.19E-02 1.89E-02 2.93E-02 3.59E-02 4.73E-02 1.21E-02 6.98E-03 1.21E-02 5.00E-02 1.19E-04 3.12E-03 2.27E -05 4.43E-03 3.72E-03 9.09E- 03 1 AE-02 2.99E-03 9.53E-03 7.04E-03 9.36E-03 3.85E-03 3.44E -04 1.52E Revision 21 Date 08/14/97 F-32 5.0 RADIATION PROTECTION: i The disposal operation of silt material from the cooling tower basins will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specific dose criteria as previously approved for septic waste disposal (Reference 1).

6.0 CONCLUSION

S: Silt collected from the cooling tower basins is an earthen type material that is similar in characteristics to septic waste residual solids with respect to the radiological pathway behavior and modeling and can be disposed of through on-site land spreading on the same disposal plots as previously evaluated and approved for septic waste disposal. The radiological assessment of low level contaminated silt shows that the projected dose from the on-site periodic spreading of this material will have no significant dose impact to members of the public and can be maintained below the approved dose limitations already in place for septic waste. - Revision 21 Date 08/14/97 23 F-33

7.0 REFERENCES

d (1) Vermont Yankee ODCM, Appendix 8; "Approval of Criteria for Disposal of Slightly Contaminated Septic Water On-Site at Vermont Yankee". approval letter dated August 30, 1989, VY request for approval dated June 28. 1989 with Attachments I and 11). (Included NRC (2) USNRC Regulatory Guide 1.109, Rev. 1; "Calculation of Annual Doses to Man from Routine Re1 eases of Reactor Effluents for the Purpose of Eva1 uati ng Compliance with 10 CFR Part 50, Appendix I", dated October 1977. (3) NUREGfCR-5512, Vole 1, "Residual Radioactive Contamination From Decommissioning" , Final Report, dated October 1992. file: vsilt.mss k Revision 21 Date 08114197 24 F-34 APPENDIX G MAXIMUM PERMISSIBLE CONCENTRATIONS (MPCs) IN AIR AND MATER ABOVE NATURAL BACKGROUND TAKEN FROM 10CFR20.1 TO 20.602. APPENDIX B 4 Revision 21 Date 08/14/97 G-1 APPENDIX G With the implementation of the revised Part 20 to Title 10 of the Code of Federal Regulations (10CFR20.1001-20.2401), the Maximum Permissible Concentrations (MPCs) that were part of the old 10CFR20 were replaced by a new Appendix B to lOCFR20 for the limits that apply to effluents released to unrestricted areas. However, MPC values were also used and accepted as licensing conditions for the control of radioactive materials in situations other than those directly covered by the requirements of the regulations. One example is the on-site disposal of septic waste which used the MPC values as one criteria of acceptability for land spreading. references 10CFR20.1-20.601 Appendix B MPCs as concentration criteria for this disposal option. Appendix B to the ODCM With the final publication of the revised 10CFR20.1001-20.2401, the original MPC tables of the old 10CFR20 are no longer in print. As such, this appendix to the ODCM is added to provide a reference source for the MPC values contained in the original Appendix B to 10CFR20.1-20.601 for those conditions that still refer to these requirements. Revision 21 Date 08/14/97 G-2 APPENDIX G ~ 5x10-: 1 2x10-i 1 2~10"~ 8x10a5 4x10- 2x10- 1~10-~ 1 8~10-~ MAXIMUM PERMISSIBLE CONCENTRATIONS (MPCs) (FROM 10CFR20.1 TO 20.602. APPENDIX B) APPENDIX B TO 1820.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND [See footnotes at e ~ Element (atomic number) I sotopel Actinium (89) ...... Ac 227 S I Ac 228 S I Americium (95) ..... Am 241 Am 242m Am 244 S I Antimony Sb 122 S I Argon (18) ....... Arsenfc (33) ...... A3 7 A4 1 As 73 As 74 As 76 As 77 Sub2 Sub S I S I S I S I n d of Appendix Bl Table I I Table I1 Col. 1 Col. 2 "":r ~ ::>-: Water I Air ~ Water (pCi /ml 1 (pCi /ml ) (pCi /ml 1 (pCi/ml) 3x1o-I1 9~10'~~ 3~10'~ 2x10-12 6~10-~ 8~10-l~ 2x10-6 5~10-~ 3~10-~ 2x104 1x10'~ 3~10~~ 3~10~~ 9x10-10 1~10-~ 6~10-~ ........ 1~10-~ ........ 2x10-6 ........ 4~10'~ ........ 2x10-6 1x10-z 7~10-~ 5~10'~ 4~10-~ 1x10-2 1x10-8 5~10'~ 3~10-~ 1~10-~ Revision 21 Date 08/14/97 G-3 APPENDIX B TO 8520.1

  • 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND Isotope' [See footnotes at end of Appenc I Tab Col. 1 Ai r (pCi /ml 1 ix 81 e1 e I1 Tab Col. 1 Air (pCi /ml 1 2x10-10 1x10-9 Col. 2 Water (pCi /ml 5~10-~ 2~10-~ Col. 2 Water (pCi /ml 1 2x10-6 7~10-~ Element (atomic number) Astatine (85) . . . . . . Barium (56) . . . . . .

Ba 131 1x10-6 I i I 4~10-~ 4~10-~ 1x10-8 Ba 140 Berkelium (97) . . . . . Bk 249 2x10-2 2x10-2 Bk 250 6x10e3 6~10-~ 5x10-' 5x10 1x10-6 Beryllium (4) . . . . . . Be 7 Bismuth (83) . . . . . . Bi 206 6x10*' 5xlO-l' Bi 207 Bi 210 6x10-' I I 6x10-' 2 x 10 -I0 2x10-10 lxlo-z 1x10-2 3x10-' 7x10 Bi 212 Bromine (35) . . . . . . 4x10" 6~10~' Cadmium (48) . . . . . . 2x10-9 3x10-' Cd 109 Cd 115m Cd 115 9x10-6 2~10-~ Ca 45 S 3~10-~ I 1~10-~ Ca 47 S ~~10'~ I 2x10'~ Calcium (20) . . . . . . 6x10e9 6x10 Revision 21 Date 08114197 G-4 APPENDIX B TO JIZO.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND El emen t ( at omi c number 1 Californium (98) . . . . Carbon (6) . . . . . . . Cerium (58) . . . , . . . Cesium (55) . . . , . , . [See footnotes at end of Appendix B1 Revision 21 Date 08/14/97 G-5 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND Element (atomic number) Chlorine (17) . . . . . . Table I Table I1 Col. 1 Col. 2 Col. 1 Col. 2 Ai r Water Ai r Water C1 36 S 4~10~~ 2~10-~ 1x10'8 8~10-~ I 2x10-8 2~10-~ ~xIo-~O 6~10-~ C1 38 S 3~10'~ 1x10-2 9x10'8 4x10m4 Isotope1 (pCi /ml f (pCi /ml 1 (pCi /ml 1 (pCi /ml 1 Revision 21 Date 08/14/97 I 2x10-6 1x10-2 Chromium (24) . . . . . . Cr 51 S 1~10-~ 5x10-' I 2x10+ 5x10-' Cobalt (27) . . . . . . . Co 57 S 3~10-~ 2x10'2 I 2~10-' 1x10-2 Co 58m S 2~10-~ 8x10-' I 9x10-6 6x10-' G-6 7~10-~ 4~10-~ 4~10~' 2x10'~ 8~10-~ 2~10-~ 1~10-~ 5~10'~ 6~10'~ 4~10'~ 6~10-~ 3~10-~ 3x10 2x10'~ APPENDIX B TO BBZO.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND e - n [See f ootnotl Element (atomic number) Is 0 tope Id of Appendix B1 Table I Table I1 Col. 1 Col. 2 Water Water s at e 1 S I Dysprorium (66) . . . . . Dy 166 I S I Einsteinium (99) . . . . Es 253 I Es 254m ~ I Es 254 S I Es 255 ~ S I S I I Er 171 S I Europium (63) . . , . . . Eu 152 fT12-9.2 hrs) I S I ~___ 4x1OW7 I 2~lO-~ I 1x10"; I 6x10A5 3x10-' 2~10-~ 1x10- 6x10-' Eu 152 I (T/2-13 yrs) S I 1x10-8 2~10-~ 4x10-10 8x10 2x10-8 ZX10-3 6x10-" 8~10-~ 4~10'~ 6~10-~ 1~10-~' 2x10" 7x10 6~10-~ 2x10"' ZxlO-' Eu 154 Eu 155 Fermium (100) . . . . . . Fm 254 f 9x10-8 6~10~~ 3x10-' 2~10-~ 7x10-' 6~10'~ 3x10-' 2~10-~ I Fm 255 I Fm 256 S I 5~10~~ 2x10-2 2~10-~ 8~10-~ 3~10'~ 1x10'2 9x10-8 5~10-~ Fluorlne (9) . . . . . . F 18 S I Revision 21 Date 08/14/97 G-7 APPENDIX B TO 5520.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND El emen t ( at omi c number ) Gadolinium (64) . . . . . Gallium (31) . . . . . . Germanium (32) . . . . . Gold (79) . . . . . . . . Hafnium (72) , . . . . . Holmium (67) . . . . . . Hydrogen (1) . . . . . . Indium (49) . . . . . . . Iodine (53) . . . . . . . [See footnotes at end of Appendix 81 Table I Table I1 Col. 1 CO?. 2 Col. 1 Col. 2 Ai r Water Air Water Isotope1 (pCi /ml 1 (pCi /ml 1 (pCi /nl 1 CpCi /ml Gd 153 S 2~10-~ 6~10*~ 8x10 2~10-~ I 9x10-8 6~10-~ 3x10" 2~10-~ Gd 159 S 5~10~~ 2~10-~ 2x104 8x I 4~10-~ 2x10'3 1x10-8 8~10'~ Ga 72 S 2x10'~ 1~10-~ 8x10-' 4~10-~ I 2~10-~ 1~10-~ 6x10-' 4~10'~ Ge 71 S 1~10-~ 5~10-~ 4~10-~ 2~10-~ I 6~10-~ 5~10-~ 2~10-~ 2~10-~ Au 196 S 1x10-6 5~10-~ 4~10-~ 2~10-~ 1 6~10-~ 4~10-~ 2x10-8 1x10'~ Au 198 S 3~10~~ 2~10-~ 1x10-8 5~10'~ I ZX~O-~ 1~10-~ SxlO-' 5~10-~ Au 199 S lXlO+j 5~10'~ 4~10-~ 2~10-~ I 8~10-~ 4~10-~ 3~10-~ 2~10-~ Hf 181 S 4~10"~ ZX~O-~ 1~10-~ 7~10'~ I 7~10-~ 2~10-~ 3x10-' 7~10'~ Ho 166 S 2~10-~ 9~10-~ 7x10-' 3~10-~ I 2~10-~ 9~10~~ 6~10~' 3~10-~ H3 S 5~10-~ 1x10-1 2~10-~ 3x I 5~10-~ 1x10'1 2~10-' 3~10-~ . ____ Sub ZX~O-~ .. ...... 4~10'~ ........ In 113111 S 8~10-~ 4~10-~ 3~10-~ 1~10-~ I 7~10-~ 4x10-' 2x10'~ 1~10-~ In 114111 S 1~10-~ 5~10'~ 4x10-' 2x10'5 I 2x10-8 5~10-~ 7xlO-l' 2~10-~ In 115m S 2x10-6 1x10-2 8~10-~ 4x10T4 I 2x204 1x10-2 6~10-~ 4~10-~ In 115 S 2~20-~ 3~10-~ 9x10*' 9~10-~ I 3~20-~ 3~10-~ 1~10-~ 9x10-5 I 125 S 5x30-' 4~10-~ 8~10-l~ 2~10-~ I 2~50-~ 6~10-~ 6x10-' 2~10-~ I 126 S 8~20~' 5~10'~ 9xlO-l' 3~10-~ I 3~80~~ 3~10"~ 1x10-8 9~10'~ I 129 S Zx30-' 1x10'~ ZXIO-; ~XIO-~ I 7x20-' 6~10-~ 2x 10 - 2x10-4 Revision 21 Date 08/14/97 6-8 1 Table I Table I1 Pb 212 s 2x104 6~10-~ 6x10-" I 2x10-8 5~10-~ 7xlO-'O Col. 2 Col. 1 , ~ "":;I- I Water ~ Air Isotope1 (pCi /ml 1 (pCi /ml 1 (pCi/ml) I 131 9x70-' 6~10~' 1x10-'10 3x90-' 2~10-~ 1x10'8 Col. 2 Water (pC1 /ml 1 Element (atomic number) Iodine (53) . . . . . . (Continued) I 132 S 2~10-~ 2~10-~ 3x10 I 9x10-' 5x10m3 3~10'~ I 2x1~~ 1x10-3 7~10-~ I 134 S 5~10-~ 4~10-~ 6x10-' I 133 s 3~10-~ 2~10'~ ~x~O-~O I 3~10-~ 2x10-2 1x10-7 I 135 S 1x10'~ 7~10-~ 1~10-~ I 4x10" 2~10-~ 1x10-8 I 4~10'~ 5~10'~ 1x10-8 Ir 390 S 1x10-6 6~10-~ 4~10-~ Iridium (77) . , . . . . I I Ir 192 S 1~10-~ 1x10'~ 4~10~' I 3~10"~ 1~10-~ ~XIO-~~ Ir 194 Iron (26) . . . . . . . Fe 59 1 ; I 1x10-7 1 2x10-3 I 5x10'9 5x10-8 2~10-~ 2~10-~ Krypton (36) . . . . , . Kr 85m f Sub 1 6~10'~ I ........ I lxlOm7 ........ . . . . . . . . . . . . * . . . .... .... 2~10-~ 2~10-~ Lanthanum (57) . . . . . ~ Lead (82) . . . . . . . . Revision 21 Date 08/14/97 G-9 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND [See footnotes at end of Appendix 83 -. Molybdenum (42) . . . . . Hg 197 Hg 203 Mo 99 1 e1 Tab 1 e II Col. 2 Water (pCi /ml 1 Col. 1 Air (pCi /ml 1 Col. 2 Water (pCi/ml) El emen t ( a tomi c number 1 lsotopt Lutetium (71) . . . . . . Lu 177 (pCi /ml 1 Manganese (25) . . . . . 1x10-8 1~10-~ 3~10-~ 2x10-8 I S I S lxlO+j I I 3~10~~ 4x10-' 9x10-8 S I 7x10F8 I 1x10.~ Neodymium (60) . . . . Nd 144 I 2x10'~ 3x10-" 1 x 10 -11 1x10'8 8x10-' Nd 147 Nd 149 8x loa3 8~10-~ ~~ ~~ Neptunium (93) . . . . . Np 237 1 1 x 10 - l3 4x10-" I Np 239 S axio-7 I I 7x10-' Nickel (28) . . . . . . . Ni 59 I ~~ 6~10-~ 6x10" 2x10'8 2~10-~ 1x10-8 3x10-' Ni 63 F Ni 65 8~10-~ 2x10-2 3~10-~ 2x10'8 Revision 21 Date 08/14/97 G-10 APPENDIX B TO 5520.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND [See footnotes at end of Appendix B1 Nb 93m Nb 95 Nb 97 El emen t ( a tomi c number S 1~10-~ 1x10-2 4x10-' 4~10-~ I 2x10'~ 1x10-2 SX~O-~ 4~10-~ S 5~10~~ 3~10-~ 2x10-8 1~10-~ I 1~10-~ 3~10-~ 3~10-~ 1~10-~ S 6~10-~ 3x10" 2~10-~ 9x10-' I 5x10m6 3x10-* zX10+ 9x10e4 Nlobium (Columbium) (41) Osmium (76) . . . . . . . Palladium (46) . , . . . Phosphorus (15) . . . . . Platinum (78) . , . . . Isotopef I Table I I Table 11 Col. 1 Col. 2 Col. 1 Col. 2 Air 1 Water I Air 1 Water (pCi /ml 1 (pCi /ml 1 (pCi /ml 1 tpCi /in1 1 Os 185 2x10'8 Os 191m 2x10'~ 7x10-' 6~10-~ f ;;3;:; I s 1 9~10-~ I 7x10" I ~xIO-~ os 191 1x10-6 5~10-~ I 4x10e7 I 5~10-~ I s Os 193 I ; 1 mo-; I 2x10-3 1x10-8 6~10-~ 3x10- I 5x10-5 Pd 103 1x10-6 1x10-2 5x10-' 3~10'~ 1 7~10-~ I 8~10-~ I 3x10-' I 3~10-~ I Pd 109 6~10-~ 3~10"~ 2x10-8 9~10~~ I 4~10-~ I ZX~O-~ I 1~10-~ I 7~10-~ I Pt 193m Pt 193 Pt 197m Pt 197 S I Revision 21 Date 08/14/97 G-11 CONCENTF I I Table I El ement ( atomi c number 1 Table I1 Plutonium (94) . . . . . Pu 238 S I Polonium (84) . . . . . . 2x10-12 1x10'~ 7~io-l~ 5~10'~ 3~10-l~ 8~10-~ 1 x 10 - 3~10-~ ~~ Potassium (19) . . . . . Pu 239 Praseodymium (591 . . . . S 2x 10 - 1x10'~ 6~10"~ 5~10-~ I 4~10'~~ 8~10-~ 1x10- 3~10-~ Promethium (61) . . . . . Pu 242 Pu 243 Pu 244 Po 210 K4 2 Protoactinium (91) . . . S 2x10-12 1~10-~ 6~10-l~ 5~10-~ I 4~10~ 9~10~~ 1 x 10 - 3~10'~ S 2x10-6 1x10-2 6x10-* 3~10-~ I 2x104 1x10-2 8~10~~ 3~10'~ S 2x10-12 1x10'~ 6~10~'~ 4~10-~ S ~x~o-~O 2~10+ 2~10-~l 7~10-~ I 2x10-lo 8~10'~ 7~10-l~ 3~10'~ S 2x10-6 9~10-~ 7x10T8 3~10-~ I 3~10-l~ 3~10-~ 1~10-'~ 1x10'~ Pa 233 isotope1 S 6~10-~ 4~10'~ 2x10'8 1x10-4 I 2~10-~ 3~10-~ 6x10 1~10-~ Col. 2 Col. 1 Col. 2 1 "":;, I Water 1 Air 1 Water (pci /m1) (pCi /ml ) (pCi Imll (pCi /ml 1 Pu 240 2x 10- Pu 241 Pr 142 2x10-7 Pr 143 1x10-8 5~10-~ I 6x10-' I 5x10e5 Pm 147 6~10-~ 6x10b3 2x10'~ I ? 1 1~10'~ I 6~10-~ I 3x10-' Pm 149 3x10e7 1~10-~ 1x10-8 4~10-~ I ZX~O-~ I l~lO-~ I 8x10-' 1 4~10-~ I i Pa 230 2x10-:' 1 7~10'~ 6~10"~ 1 2~10'~ 1 1 8x10- 7x10-' 1 3xlO-l' 2~10-~ Pa 231 lx 10 - l2 3~10-~ 4~10-l~ I 9~10'~ I I 1~10"~ I 8~10'~ 1 4~10-l~ 2x10'~ Revision 21 Date 08/14/97 G- 12 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AN0 WATER ABOVE NATURAL BACKGROUND Rh 105 S 8~10'~ 4~10'~ 3x10 1~10-~ I 5x10*' 3~10-~ 2x10'8 1x10'~ I 7~10-~ 7~10'~ 2~10-~ ZX~O-~ 1 Rb 86 S 3~10-~ 2~10-~ 1x10-8 7~10-~ [See footnotes at end of Appendix BI Re 183 Re 186 El ement ( atomi c number 1 Radium (88) . . . . . . . S 3~10-~ 2x10-2 9x10-8 6~10~~ I 2~10-~ 8~10-~ 5x10-' 3~10-~ S 6~10-~ 3~10-~ 2x10-8 9~10'~ I 2~10-' 1~10-~ 8x10-' 5~10'~ Radon (86) , . . . . . , Rhenium (75) . . . . . . Rhodium (45) . . . . . . , Rubidium (37) . . . . . . Ruthenium (44) . . . . . I Table I I Table I1 Ra 228 7~10'~~ 8~10~~ ZX~O-~~ 1 3x1OV8 1 T 1 4~10"~ 1 7x10 I 1~10-I~ 3~10'~ Rn 220 1 S I 3~10-~ I ........ I lxlO-' I ...... .. ~~ ~ ~~ Rn 22Z3 1 I 3~10'~ I ..... ... 1 3x10-' I ........ Re 187 9x10-6 7~10~~ 3~10-~ 3~10'~ I 5~10-~ I 4~10-~ I ZX~O-~ I 2~10'~ I Re 188 4~10-~ 2~10-~ 1xlO" 6~10-~ I ZXlO-' 1 9~1O-~ 1 6~10~' I 3; I s Rh 103m 8~10-~ I 4x10-'1 I 3x1OV6 1x10'~ I s I 6~10*~ 3xlO-l 2x10-6 I 1x10-2 Rb 87 1 ; I 5~10-~ I 3~10-~ 1~10-~ 7~10'~ I 2x10-4 ZX~O-~ I 1~10-~ I 8x10m8 4x10.' I : I 2x10'6 1x10-2 6x10-' I 3~10-~ Ru 105 1 ; 1 7x10-i I 3~10'~ 2x10-8 1~10-~ 3~10~~ I 2x10-8 I 1x10-4 5x10- Ru 106 8~10-~ 4~10'~ 3x10-' 1x10'~ I 6x10" I 3~10-~ I 2x10-l' I 1x10-5 I Revision 21 Date 08/14/97 6-13 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND 2~10-~ 9x10'9 1~10-~ 4~10-~ 3~10-~ 1x10-6 [See footnotes at end of Appendix Bl 1~10-~ 6x10" 4~10-~ 9~10-~ 3~10'~' 3~10-~ 8~10'~ 5x10" 3~10-~ 2x10'1 1x10'6 7~10-~ 2x10'1 1x10-6 7x10e3 6~10-~ 4~10-~ 2~10-~ El emen t ( atomi c number ) Isotc Samarium (62) . . . . . . Sm 147 S I S I - Sm 151 Sm 153 S I S I S I - - Scandium (21) . . . . /. . Sc 46 sc 47 Sc 48 S I S I S I S I - - - Se 75 Selenium (34) . . . . . Si 31 Silicon (14) . . . . . . Ag 105 Silver (47) . . . . . . . Ag llOm S I Ag 111 S 1 Sodium (11) . . . . . . . Na 22 S I S I S I - - Na 24 Strontium (38) . . . . . Sr 85m Sr 85 S I S I S I - - ZxlO-; I 3~10'~ 8x10-' 1~10-~ 1x10- 5~10'~ I 4x10" I 2x10-4 Sr 89 3~10-~ I 3x10-i I 4~10-~ 8x10- Sr 90 Revision 21 Date 08/14/97 G-14 APPENDIX B TO 8820.1

  • 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND

[See footnotes at end Isotope1 Sr 91 S I Sr 92 S I s 35 S I Ta 182 S I Tc 96m S I Tc 96 S I Tc 97m S I Tc 97 S I Tc 99m S I Tc 99 S I Te 125111 S I Te 127m S I Te 127 S Te 129m S Te 129 I I Element (atomic number) of Appendix B1 Table I Table I1 Col. 1 Col. 2 Col. 1 Cot. 2 Air Water Ai r Water (pCi /ml 1 CpCi Iml 1 (pCI /ml 1 (pCi /ml 1 4~10'~ 2~10-~ 2x10-8 7x10e5 3~10-~ 1~10-~ 9~10-~ 5~10'~ 4x10a7 ~~10'~ 2x10-8 7~10'~ 3x10 2~10-~ 1x10-8 6~10'~ 3~10'~ 2~10-~ 9x10-' 6~10~~ 3~10'~ 8~10-~ 9x10-' 3~10-~ 4x10a8 1x10'~ 1x10;90 4x10e5 2x10-8 1~10-~ 7x10- 4~10~~ 8~10-~ 4x10-' 3~10~' 1x10-2 3~10-~ 3xlO-l 1x10'6 1x10'2 6x10e7 3~10-~ 2x10-8 1~10'~ 2x1~-7 5~10'~ 5x10-' 2~10-~ 1~10-~ 5x10-' 4x10" 2~10-~ 3~10-~ 2x10-2 1x10'8 8x10-4 2~10-~ 1~10-~ 8x10-' 5~10"~ 2x104 1x10'2 8~10'~ 4x10-' 4~10'~ 2x10-1 1x10'6 6~10-~ 1x10'~ 8x10e2 5~10-~ 3~10"~ 2x10-6 1x10'2 7~10'~ 3x10a4 6~10~~ 5~10-~ 2~10-' ~~10'~ 4~10-~ 5~10-~ 1x10-8 2~10-~ 1~10-~ 3~10-~ 4x10-' 1~10-~ 1~10-~ 2~10-~ 5x10-' 6~10-~ 4~10-~ 2~10-~ 1~10-~ 5~10'~ 2XlO+j 8~10'~ 6~10'~ 3~10~'" 8~10-~ 1~10-~ 3x10-' 3~10-~ 9~10-~ 5~10'~ 3~10-~ 2x10'~ 3~10'~ 6~10'~ 1x10'~ 2~10-~ Strontium (38) , . . . , (Continued) Sulfur (16) . . . . . . . Tantalum (73) . . . . . . Technetium (43) . . . . . Tellurium (52) . . . . . Revision 21 Date 08/14/97 G-15 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND [See footnotes at c. I Th 228 Th 230 Th 231 I If Th 232 Th 234 s I Thulium (69) . . . . . . Tm 170 S I I Tm 171 I: Tin (50) . . . . . . + 1 Sn 113 ~ ; ~~ Sn 125 Tin (50) . . . . . . + 1 Sn 113 ~ ; ~~ Sn 125 d of Appendix 81 Table I1 Table I Col. 1 Col. 2 Col. 1 Col. 2 Air Water Ai r Water (pCi /mi ) (pCi /ml 1 (pCi /ml 1 (pCi /m1 ) 1x10'~ 1~10-~ 3x10-' 4~10-~ 3~10-~ 1~10-~ 1~10-~ 4~10-~ 3~10'~~ 5~10'~ 1x10-11 2~10-~ 2x 10 - '0 5~10-~ 6~lO-~~ 2~10-~ 6~10"~ 4x10'~ 2~10-l~ 1~10-~ 9x 10 "'2 2~10-~ 3~10-l~ 7x10-' .. 2x10-" 5~10-~ 8~10"~ 2x10-6 1x10-6 7~10-~ 5x10+ 2~10-~ 1x10-6 7~10~~ 4~10-~ 2~10-~ 3x10- 5x10m5 1~10-~* 2x10-6 1~10-l~ 9~10~~ 3~10-l~ 3~10-~ 3~10-l~ 1~10-~ lx 10 -I2 4~10-~ Revision 21 Date 08/14/97 G- 16 APPENDIX B TO 5tiZO.l - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND Element (atomic number) Tungsten (Wolfram) (74) . Uranium (92) ...... Vanadium (23) ...... Xenon (54) ....... Ytterbium (70) ..... Yttrium (39) ...... [See footnotes at end of ADpendix 61 Revision 21 Date 08/14/97 6-17 APPENDIX B TO §§20.1 - 20.602 CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND [See footnotes at end of Appendix B] Table I1 Col. 2 Water (NCi /ml 1 Col. 1 Ai r (rrCi /ml 1 Col. 2 Water (uCi/ml) Col. 1 Ai r (pCi /ml 1 2~10-~ 2x10-5 I sotopel '~ Element (atomi c number 1 Y 93 S I S I S I S I S f Zn 65 Zinc (30) . . . . . . . Zn 69m 1x10-8 1x10'8 Zn 69 Zirconium (40) . . . . . Zr 93 2x10-2 2x10-2 4~10-~ 1x10-8 1x10'~ 9x10-8 Any single radi onucl ide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life less than 2 hours. 1x10-'5 ........ 3x10 ....... Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous ffssion and with radioactive half -1 ife greater than 2 hours. 9~10-~ 1x10-10 3~10'~ Any single redionuclide not 1 i sted above which decays by alpha emission or spontaneous fission. 4~10-~ 2~10-l~ 3~10-~ I Revision 21 Date 08/14/97 G-18 'Soluble (SI; Insoluble (I). '"Sub" means that values given are for submersion in a semispherical infinite cloud of 3These radon concentrations are appropriate for protection from radon-222 combined with its short-lived daughters. Alternatively, the value in Table I may be replaced by one-third (113) "working level ." (A "working level" is defined as any combination of short-lived radon-222 daughters, polonium-218, lead-214, bismuth-214 and polonium-214. in one liter of air, without regard to the degree of equilibrium, that will result in the ultimate emission of 1.3 x lo5 MeV of alpha particle energy.) "working level." annual average. factor. If the percent by weight-enrichment of U-235 is less than 5. the concentration value for a 40-hour work week, Table I. is 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the product of the average concentration and time of exposure during a 40-hour work week shall not exceed 8 x SA pCi-hrlml, where SA is the specific activity of the uranium inhaled. The concentration value for Table I1 is 0.007 milligrams uranium per cubic meter of air. The specific activity for natural uranium is 6.77 x curies per gram U. The specific activity for other mixtures of U-238, U-235 and U-234, if not known, shall be: -" airborne material. The Table I1 value may be replaced by one-thirtieth (1130) of a The limit on radon-222 concentrations in restricted areas may be based on an 4For soluble mixtures of U-238, U-234 and U-235 in air chemical toxicity may be the limiting SA = 3.6 x curiesigram U U-depleted SA = (0.4 + 0.38 E + 0.0034 E2) where E is the percentage by weight of U-235. expressed as percent. NOTE: 1. If the identity and concentration of each radionuclide in the mixture are known, the E 2 0.72 In any case where there is a mixture in air or water of more than one radionuclide, the limiting values for purposes of this Appendix should be determined as follows: limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix 5 for the specific radionuclide when not in a mixture. The sum of such ratios for a71 the radionuclides in the mixture may not exceed "1" (i.e., "unity"). EXAMPLE: If radionuclides A. 5, and C are present in concentrations C,, C,, and C,. and if the applicable MPC's are MPC,, and MPC,, and MPC, respectively, then the concentrations shall be limited so that the following relationship exists: (C,/MPC,) + (C,IMPC,) + fCc/MPCc)

2. If either the identity or the concentration of any radionuclide in the mixture is not a. For purposes of Table I, Col. 1 - 6x10- b. For purposes of Table I, Col. 2 - 4~10-~ c. For purposes of Table 11, Col . 1 2~lO-'~ d. For purposes of Table 11, Col . 2 - 3~10~~ 3. If any of the conditions specified below are met, the corresponding values specified
a. If the identity of each radionuclide in the mixture is known but the concentration of one 1 known, the limiting values for purposes of Ap endix B shall be: E below may be used in lieu of those specified in paragraph 2 above. or more of the radionuclides in the mixture is not known. the concentration limit for the mixture is the limit specified in Appendix "6" for the radionuclide in the mixture having the lowest concentration limit: or b. If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in Appendix "5" are not present in the mixture, the concentration limit for the mixture is the lowest concentration limit specified in Appendix "B for any radionuclide which is not known to be absent from the mixture: or Revision 21 Date 08/14/97 G- 19
c. Element (atomic number) and isotope If it is known that Sr 90, I 125, I 126, I 129, I 131 (I 133, Table I1 only), Pb 210, Po 210, At 211, Ra 23, Ra 224, Ra 226, Ac 227, Ra 228, Th 230, Pa 231, Th 232, Th-nat, Cm 248, Cf 254, and Fm 256 are not present ........ I 129 (I 131, I 133, Table I1 only), Pb 210, Po 210, Ra 223, Ra 226, Ra 228, Pa 231, Th-nat, Cm 248, Cf 254, and Fm 256 are not present ........ If it is known that Sr 90, I 125, I 126, Table I Col. 1 Col. 2 (PT1pCi /m1) (pci /ml) Air Water ........ ~xIO-~ ....... 6~10.~ ........ I Ac 227 are not present ........ 1 3x10-" If it is known that alpha-emitters and If it is known that Sr 90, I 129 (I 125. I 126, I 131, fable I1 only), Pb 210, Ra 226, Ra 228. Cm 248, and Cf 254 are If it is known that (I 129, Table I1 only). Ra 226. and Ra 228 are not present . . Sr 90, I 129, Pb 210. Ac 227. Ra 228, Pa 230. Pu 241, and Bk 249 are not present ................

not present .............. If it is known that alpha-emitters and - - If it is known that alpha-emitters and Pb 210. Ac 227, Ra 228, and Pu 241 are not present .............. ........ zX10+ ........ 3~10'~ 3x10.' ....... 3x10-" ........ Table I1 ~~ If it is known that Ac 227. Th 230, Pa 231, Pu 238, Pu 239, Pu 240, Pu 242, Pu 244. Cm 248. Cf 249 and Cf 251 are not present Col. 1 Ai r (pCi /ml 3~10-l~ ........ ........ ....... ........ ........ 1 x10-10 lxlo- 1x10-12 iX10-l3 Col. 2 Water (WCi /ml 3~10-~ 2x10-6 6x10.' 1x10-7 ........ ........ ......... ........ 4. If a mixture of radionuclides consists of uranium and its daughters in ore dust prior to chemical separation of the uranium from the ore, the values specified below may be used for uranium and its daughters through radium-266, instead of those from paragraphs 1, 2, or 3 above. a. For purposes of Table I, Col . 1 - lxlO-lo pCi/ml gross alpha activity; or 5~10.'~ pCi/ml natural uranium or 75 micrograms per cubic meter of air natural uranium. b. For purposes of Table 11, Col. 1 - 3x10"l2 pCi/ml gross alpha activity: 2~10-l~ pCi/ml natural uranium; or 3 micrograms per cubic meter of air natural uranium. 5. For purposes of this note, a radionuclide may be considered as not present in a mixture if (a) the ratio of the concentration of that radionuclide in the mixture (CAI to the concentration limit for that radionuclide specified in Table I1 of Appendix "8" (MPC,) does not exceed 1/10, (i.e. C,/MPC, A 1/10} and (b) the sum of such ratios for all the radionuclides considered as not present in the mixture does not exceed 1/4 i.e. (C,/MPC, + C,/MPC, ... + - 1/41. T Revision 21 Date 08/14/97 G-20 Appendix H 1. "Request to Amend Previous Approvals Granted Under 10CFR20.302(a) for Disposal of Contaminated Septic Waste and Cooling Tower Silt to Allow for Disposal of Contaminated Soil", dated June 23rd, 1999, BVY 99-80 "Supplement to Request to Amend Previous Approvals Granted Under 10CFN0.30(a) to AlIow for Disposal ofContaminated Soil", dated January 4*, 2. BVY 00-02 3. "Vermont Yankee Nuclear Power Station, Request to Amend Previous Approvals Granted under 10CFR20.302 a to AIlow for Disposal of Contaminated Soil (TAC No. MA5950), dated June 15 ,2000, NVY 00-58 L) I I Revision29 Date 1/11/02 I H- 1 VERMONT YANKEE NUCLEAR POWER CORPOFMTKIN I85 Old Ferry Road, Brattleboro, VJ' 05301 -7002 (802) 257-5271 United States Nuclear Regulatory Commission A1TN: Document Control Desk Washington, DC 20555 June 23, 1999 BW 99-80

References:

(a) Letter fiom *LW. Capstick, Vermont Yankee, to USMRC, "Request to Routinely Dispose of SlightIy Contaminated Waste in Accordance with iOCFR20.302(a)", BVY 89-59, June 28, 1989 Letter &om M.B. Fairtile, USNRC, to L. A. Trembley, Vermont Yankee, "Approval Under 10CFR20.302(a) of Procedures for Disposal of Slightly Contaminated Septic Waste on Site at Vermont Yankee (TAC No. Letter from J.J. DufFy, Vermont Yankee, to USNRC, "Request to Amend Previous Approval Granted Under IOCFR20.302(a) for Disposal of Contaminated Septic Waste", BVY 95-97, dated August 30, I995 Letter from S.A. Varga, USNRC, to D. A. Reid, Vermont Yankee, "ApprovaI Pursuant to lOCFR20.2002 for Onsite Disposal of Cooling Tower Silt - Vermont Yankee Nuclear Power Station (TAC No. M93420)", Nw 94-39, dated March 4, 1996 Letter from P.D. Milano, USNRC, to D. A. Reid, Vermont Yankee, "Revised Safety Evaluation - Approval Pursuant to lOCFR20.2002 for Onsite Disposd of Cooling Tower Silt - Vermont Yankee Nuclear Power Station (TAC No. M9637I)", NVY 97-85, dated June 18,1997 (b) 73776)", NVY 89-189, dated August 30, 1989 (c) (d). (e)

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) Request to Amend Previous Amrovals Granted Under 10 CFR 20.302fa) for Disoosai of Contaminated SeDtic Waste and cool in^ Tower Silt to Allow for Disnosal of Contaminated Soil In accordance with lOCFR 20.2002 (previously 10CFR20.302(a)), Vermont Yankee submits this application to amend the previously granted approvals to dispose of slightly contaminated septic waste and cooling tower silt on-site, This application expands the allowable waste stream to include slightly contaminated soil generated as a residual by-product of on-site construction activities. This application specificatly requests approval to dispose of soil contaminated at minimal levels, which has been or might be generated through end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed soil disposd method is the same as the septic .waste and coohg tower silt disposal methods requested in References (a) and (c), and approved in References (b) and (e). The disposal method utilizes on-site land spreading in the same designated areas used for septic waste and cooling tower silt. Disposal of this waste in the manner proposed, rather than holding it for future disposal at a lOCFR Part 61 licensed facility will save substrtntid costs and reserve valuable disposal site space for waste of higher radioactivity levels. 1 Revision 29 Date 1/11/02 H- 2 VERMONT YANKEE NUCLEAR POWER CORPORATION I BVY 99-80 i Page 2 of2 A radiological assessment and proposed operational controls for the inclusion of additional earthen material (soil) for on-site disposal with septic waste and cooling tower silt is provided in Attachment A. The assessment demonstrates that the dose impact expected from the existing accumulation of approximately 25.5 cubic meters of so& in total with dI past waste spreading operations, will not approach the dose limits already imposed for septic and cooling tower silt disposal. In addition to the existing accumulated soil, VY also requests that any future low leveI contaminated soil that might be generated as a by-product of plant construction and maintenance activities be dowed to be disposed of in the same manner providcd the approved acceptance dose criteria are met. AN soil dyses will be to environmental lower limits of detection. The results of dl disposal operations will also be reported in the Annual Radioactive Efnuent Release Report. The combined radiological impact for all on-site disposd opedons wiIl continue to be limited to a total body or organ dose of a maximaIly exposed member ofthe public of less than one mredyear during the period of active'fremont Yankee control of the site, or less thaa five mredyear to an inadvertent intruder after termination of active site control. The Vermont Yankee Off-Site Dose Calculation Manual (ODCM) contains ampy of the original assessment and NRC approval *or septic waste disposal (Refereucac a and b) and the previous amendment for cooIing tower silt Peferences c and e). Upon receipt of your approval, the information contained in Attachment 1 as well as the basis for approval will be incorporated into .the ODCM. We trust that the information contained in the submittd is sufficient. However, should you have any questions or requir:: Mer information concerning this matter, piease contact Mr. Jim DeVincentis at 802-258-4236. Sincerely, mmom YANKEE: NUCLEAR POWER CORYOIWTION Attachment cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS VT Department of Public Service Licensing M-er Revision 29 Date 1/11/02 I H- 3 -

SUMMARY

OF VERMONT YANKEE COMMZTMENTS BVYNO.: 99-80 The following table identifies commitments made in this document by Vermont Yankee. Any other actions discussed in the submittal represent intended or pIanned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments. COMMITMENT I COMMITTED DATE I OR "OUTAGE" h I VYAPF 0058.04 (Sample) AP 0058 Original Page 1 of 1 H- 4 Revision 29 Date 1/11/02 ll Docket No. 50-27 1 BVY 99-80 Attachment 1 Vermont Yankee Nuclear Power Station Assessment of On-site Disposal of Contaminated Soil by Land Spreading 1 Revision 29 Date 111 1/02 H- 5 - BW 99-80 /Attachment 1 I Page 1 TABLE OF CONTENTS Page LIST OF TABLES ............................................................................ 2 I . 0 2.0 ' 3.0 4.0 5.0

6.0 INTRODUCTION

................................................................... 3 1.1 Background ..................................................................... 3 1.2 Objective ......................................................................... 3 WASTE DESC.ON ................................................................ 4 SOIL DISPOSAL AND ADMINISTRATIVE PROCEDURE REQUrREMENTS ......................................................................... 5 EVAL, UATION OF ENVIRONMENT& IMPACTS ............................... 6 4.1 Site Characteristics .................................................................. 6 4.2 RadioIogical Impact .................................................................. 6 RADIOLOGICAL PROTECTION ...................................................... 8 CONCLUSIONS ........................................................................... 9

7.0 REFERENCES

............................................................................. 9 I Revision 29 Date 1/11/02 H- 6 I I L_ BVY 99-80 I Attachment 1 I Page 2 LIST OF TABLES Table 1 : Radioanalytical Results of Composite Soil Samples.. ....................... ..lo Table 2: Estimated TotaI Radioactivity in Soil Volume.. ................................ 10 11 Table 3: Total Activity on South Field Mer Last Spreading Event.. ............... Table 4: Total Projected Radioactivity Remaining on South Filed at License ... a. Exp~~on ........ :...........................................,;....*.................... I1 Table 5: All-Pathway Critical Orgadwhole Body Dose Conversion Factors During Vermont Yankee Control of Disposal Site ......................................... 11 Table 6: MI-Pathway Critical Organ/WhoIe Body Dose Conversion Factors Post . Vermont Yankee Control of DisposaI Sites (Inadvertent Intruder) ............. 12 Table 7: Dose Contribution fiom CO-60 and Cs-137 in Soil Volume &a Land Spreading .......................................................................... 12 Table 8: Present and Future Dose Impact Due to the SoiI Spreading for Two Cases.. ............... .:. ...................................................... 13 Revision 29 Date 1/11/02 II I - BVY 99-80 I Attachment 1 1 Page 3

1.0 INTRODUCTION

1.1 Background In 1989, Vermont Yankee Nuclear Power Corporation requested approval from the NRC to routinely dispose of slightly contaminated septic waste in designated on-site areas in accordance with lOCFR20.302(a). Approval fiom the NRC was granted on August 30, 1989 and the information was permanently incorporated into the Offsite Dose Calculation Manual (ODCM) as Appendix B. In 1995, Vermont Yankee Nuclear Power Corporation requested that the previous authorization for on-site disposal of very low-level radioactive material in septic waste be amended to permit the on-site disposal of slightly con-ted cooling tower silt material. Approval fiom the NRC was granted on June 18,1997 and the information was permanently incorporated into the ODCM as Appendix IF. In 1994, approximately 25.5 rn3 of excess soil was generated during on-site construction activities. SampIing of the soil revealed low levels of radioactivity that were similar in radionuclides and activity to the septic waste and cooling tower silts previously encountered. An evaluation determined that the soil could be managed in similar fashion as the septic waste and cooIing tower silts; however, prior approval fioom the NRC would be required under 10 CFR 20.2002 (formerly 20.302(a)). 1.2 Objective The objective of this assessment is to present the data and radiological evaluation to demonstrate that the proposed disposition of the soil will meet the existing boundary conditions as approved by the NRC for septic waste and cooling tower silt. The boundary conditions established for disposal of the septic waste and cooling tower silts on the designated plots are: The dose to the whole body or any organ of a hypothetical maximally exposed individual Doses to the whole body and any organ dose of an inadvertent intruder fiom the probable Disposal operations must be at one of the approved on-site locations. must be less than 1.0 medyr. pathways of exposure are less than 5 mredyr. I Revision 29 Date 1/11/02 H- 8 I I BVY 99-80 I Attachment 1 / Page 4 ~ 2.0 WASTE DESCRIPTION The soil that is the subject of this evaluation was derived from excavations resulting fiom activities associated with a new security fence along the laut's Protected Area boundary, containing light to dark brown poorly sorted soils with some small stones, and includes small incidental pieces of asphalt. The soil was removed from its original location by shovel, backhoe and fiont-end loader, and placed into dump trucks for transport to the location between the cooling towers where it was deposited on the ground surface and covered to prevent erosion. This location was selected because it was away fiom areas routinely occupied by pIant staff, and could easily be controlled. The most probable source of the low levels of radioactive contamination is the presence of below detectable removable contamination redistributed by foot traffic from inside the plant to walkways and parking areas. Subsequent surface ruxioff carries the contamination to nearby exposed soil near the Protected Area boundary where it had accumulated over time to low level detectable concentrations. The volume of soil generated was approximately 25.5 m P , and is typical of fill material Revisloll20 Date 1/11/02 In April 1995, a total of 20 composite soil samples were collected to characterize the volume. Composites were obtained by collecting a grab sample fiom one side, the top and the opposite side at equal distances along the length of the pile, then combining the thee into one sample. Soil samples were sent to the Yankee Atomic Environmental Laboratory for analysis and counted to environmental lower limits of detection required of environmental media. ResuIts of the andyses are presented in Table 1. AualyticaI results are provided for when the samples were collected and decay corrected to the present. The results identified both Cs-137 and Co-60 in most of the composite sampIes, which verified that plant-related radioactivity was present in the soil. For the purpose of estimating the total activity in the soil pile, the actual analytical result was used for those samples that were less than the MDC to calculate the average radioactivity concentration. The mass of soiI (dry) was estimated by multiplying the totaI in-situ volume (25.5 m3) by its wet density, 1.47E+03 kg/m3, and then dividing by the wetdry ratio of I .12, thus yielding a mass of 3.35E+04 kg (dry). The mass of the soil was then multiplied by the average Co-60 and Cs-I37 concentrations measured in the soil to obtain the total activity of each radionuclide in the 25.5 m3. Table 2 presents the estimated total radioactivity in the 25.5 m3 of soil at the time of sample collection and analysis, and decay corrected to the present. H- 9 & BVY 99-80 1 Attachment 1 J Page 5 Revision 29 Date 1/11/02 3.0 SOIL DISPOSAI, AND ADMINISTRATTVE PROCEDURE REQuxxIlEbD3NTS The method of soil disposal will use the technique of land spreading in a manner consistent with the current commitments for the on-site disposal of septic waste and cooliig tower silts as approved by the NRC, The accumulation of radioactivity on the disposal plot for this soil spreading operation will be treated as if cooling tower silt or septic waste was being disposed of since the characteristics of all these residual solids are similar (earthen-type matter), The south field (approximately 1.9 acres in size) designated and approved for septic waste and cooling tower silts disposal has been used for all past disposal operations, and will be used for the placement of this soil. Determination of the radiological dose impact has been made based on the same models and pathway assumptions used in the previous submittals. H-10 Dry soil material will be dispersed using typical agricultural dry bulk surface spreading practices in approved disposd areas on-site. Incidental pieces of asphalt and stones that were picked up with the soil from area where paving ran along the fence he will be screened out before the soil is spread and disposed of as radioactive material at an off-site licensed facility if detectable radioactivity is found. Records of the disposal that will be maintained include the following: (a) The radionuclide concentrations detected in the soil (measured to (b) The total volume of soil disposed of. (c) The total radioactivity in the disposal operation as well as the total (d) The plot on which the soil was applied. (e) Dose calculations or maximum allowable accumulated activity determinations required to demonsbate that the dose limits imposed on the land spreading operations have riot been exceeded. environmental lower limits of detection). accumulated on each disposal plot at the time of spreading. To ensure that the addition of the soil containing the radioactivity will not exceed the boundary conditions, the total radioactivity and dose calcdation will include all past disposals of septic waste and coohg tower silt containing low-level radioactive material on the designated disposal plots. In addition, concentration limits applied to the disposal of earthen type materials (dry soil) restrict the placement of small volumes of materials that have relatively high radioactivity concentrations. Any farmer leasing land used for the disposal of soil will be notified of the applicable restrictions placed on the site due to the spreading of low level contaminated material. These restrictions are the same as detailed for the previously approved septic waste spreading application. L_ BW 99-80 I Attachment I I Page 6 4.0 EVALUATION OF ENVIRONMENTAL IMPACTS 4.1 Site Characteristics The designated disposal site is located on the Vermont Yankee Nuclear Power Plant site and is within the site boundary security fence. The south field consists of approximately 1.9 acres and is centered approximately 1500 feet south of the Reactor Building. This parcel of land has been previously approved by the NRC for the land disposal of septic waste and cooling tower silt. 4.2 Radiological Impact The amount of radioactivity added to the south field soil is procedurally controlled to emure that doses are maintained witbin the prior approved limits of the boundary conditions. To assess the dose received (after spreading the soil) by the maximally exposed individual during the period of plant controls over the property, and to an inadvertent intruder after plants controls of access ends, the same pathway modeling, assumptions ind dose calculation methods as approved for septic and cooling tower silt disposal were used. These dose modeIs implement the methods and dose conversion factors as provided in Regulatory Guide 1.1 09. The following six potential pathways were identified and included in the andysis: (a) Standing on contaminated &ound. (b) Inhalation of resuspended radioactivity. (c) Ingestion of leafy vegetables. (d) Ingestion of stored vegetables. (e) Ingestion of meat. (0 Ingestion of cow's milk. Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways; the difference between them is due to the occupancy time: The basic assumptions used in the radiological analyses include: (a) Exposure to ground contamination and re-suspended radioactivity is for a period of 104 hours per year during the Vermont Yankee active control of the disposal sites and continuous thereafter. The 104-hour interval is representative of a farmer's he spent on a plot of land (4 hours per week for 6 months). I Revision 29 Date 1/11/02 B-11 - BVY 99-80 / Attachment 1 /Page 7 I (b) For the purpose of projecting and'illusmting the magnitude of dose impacts over the remaining life of the plant, it is assumed that the concentration levels of activity as of April 1,1999 remain constant. Table 1 indicates the measured radioactivity leveIs for CO-60 and Cs-137 first noted in the soil, and decay corrected to April 1,1999. Revision29 Date 1/11/02 (b) For the analysis of the radiological impact during the Vermont Yankee active control of the disposal sites until 20 13, no plowing is assumed to take place and all dispersed radioactive material remains on the surface forming a source of unshielded direct radiation. (c) The crop exposure time was changed fiom 21 60 hours to 0 hours to reflect the condition that no radioactive material is dispersed directly on crops for human or animal consumption. Crop contamination is only through root uptake. (d) The deposition on crops of re-suspended radioactivity is insignificant. (e) The pathway data and usage factors used in the analysis are the same as those used in the Vermont Yankee's ODCM assessment of off-site radiological impact fiom routine releases, with the following exceptions. The fraction of stored vegetables grown on the contaminated land was conservatively increased fiom 0.76 to 1.0 (at present no vegetable crops for human consumption are grown on any of the approved disposal plots). Also, the soil exposwe time to account *or buildup was changed from the standard 15 years to 1 year. (f) It is conservatively .assumed that Vermont Yankee rdiquishes control of the disposal sites after the operating license expires in 2012 (i.e., the source term accumulated on a singIe disposal plot applies also for the inadvertent intruder). (g) For the analysis of the impact after Vermont Yankee control of the site is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of the soil; but nonetheless, undergoes re- suspension in the air at the same rate as the unpIowed surface contamination. However, for direct ground plane exposure the self- shielding due to the six-inch plow layer reduces the surface dose rate by about a factor of four. B-12 A BVY 99-80 / Attachment 1 f Page 8 As shown in the previous submittals, in which the concentrations of Co-60 and Cs-137 in septic waste exceed those identified in the soil, the liquid pathway was found to be an insignificant contributor to the dose. Therefore, the liquid pathway is not considered in this analysis. The dose models and methods used to generate deposition values and accumulated activity over the operating life of the plant are documented the ODCM. Table 3 presents the radioactivity that currently exists on the south field after the Iast spreading event which occurred on September 28,1998 (total elapsed time fiorn September 28,1998 to April 1 , 1999 is 184 days). In addition, the total activity on the south field is presented assuming the addition of the 25.5 m3 of soil subject of this evaluation. The total activiw that would be present ofi south field at license termination (Le., total elapsed time of 14 years post April 1,1999, or 2013), assuming no future additions of material containing radioactivity after disposal of the proposed soil volume was also evaluated and is presented in Table 4. In order to demonstrate compliance with the boundary conditions, the critical organ and whole body dose from all pathways to a maximally exposed individual during Vermont Yankee control, and to the inadvertent intruder were calculated. The dose calculations were performed using the dose conversion factors presented in TabIe 5 and 6 beIow which were obtained fiom the ODCM. The contribution to dose fiom Co-60 and Cs-137 to the whole body and organ at the present and at license expiration is presented in Table 7. The present and future total dose impact fiom the south field with and without spreading of the soil is presented in TabIe 8. These resdts demonstrate that disposal of the approximately 25.5 m3 of accumulated soil will be well within the accepted dose limit criteria of 1 mremfyr to any organ or whole body during the control period, and 5 mredyr to an inadvertent intruder after control of the site is assumed to be relinquished. This analysis shows that significant dase margin still exists on the approved disposal plots to accommodate potential future spreading operations. 5.0 RADIOLOGICAL PROTECTION The disposal operation of soil piles will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specific dose criteria as previously approved for septic waste and coohg tower silt disposal. I Revision 29 Date 1/11/02 H-13 - BVY 99-80 / Attachment 1 I Page 9

6.0 CONCLUSION

S Soil generated from on-site construction activities reflects an earthen type material similar in characteristics to septic waste residual soIids and cooling tower silt with respect to the radiological pathway behavior and modeling. Based on the similarity in characteristics between the proposed soil volume and waste streams that have already been approved for disposal, and the evaluation of the incrementaI dose impact, it is concluded that disposal of the approximately 25.5 m3 of existing soil through on-site land spreading wiIl meet the boundary conditions specified in the ODCM. That is, with respect to the addition of the approximately 25.5 m3 soil pile to the existing radioactivity already spread on the south field: 1. Total doses to the whole body and critical organ to the hmothetically maximally exposed individual were estimated & 3.00E-02 mredyr and 1.04E-01, respectively, which are Iess than the prescribed 1.0 mredyr. 2. Total doses to the whole body and critical organ of an inadvertent intruder fiom the probable pathways of exposure were estimated as 1.13E-01 mredyr and 2.21E-01 mredyr, respectively, which are less than 5 mredyr. 3. The disposal is assumed to take place on the south field that is the same site approved for disposal of septic waste and cooling tower silts. If the soil were spread on an approved plot which had not yet been used for disposal, the dose impact from the approximately 25.5 m3 of soil alone would at present be 4.17E-03 mredyr whole body and a maximum organ dose of 1.46E-02 mredyr. In addition, for the inadvertent intruder, the whole body dose would be 1.60E-02 mrerdyr, and a maximum organ dose of 3.1 IE-02 mredyr. Each of these doses also meet the boundary conditions specified in the ODCM.

7.0 REFERENCES

(1) Vermont Yankee ODCM, Rev 23, Appendix B, "Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont Yankee". (2) Vermont Yankee ODCM, Rev 23, Appendix F, "Approval Pursuant to 1 OCFR20.2002 for On-Site Disposal of Cooling Tower Silt". (3) USNRC Regulatory Guide I .109, Rev 1 , "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 1 OCFR Part 40, Appendix I", dated October 1997. Revision 29 Date 1/11/02 I1 H-14 L BVY 99-80 / Attachment 1 / Page 10 Radionuclide CS-137 CO-60 Table 1 Radioanalytical Results of Composite Soil Samples Muximum Vdue 81 0 739 143 84 Minimum Value I07 98 5 3 Standard Deviation 191 1 74 37 22

  • Average wet to dry sample weight ratio equal to 1.12. Average wet density equal to 1.47 gdcc. ** The apparent response of the gamma isotopic analysis which was lcss than Minimum Detectable Concentration.

of Soil Mass 6 Ci/kg-dry) (m (m3) (kg-dry) - April, 1995 April, 1999 ApriI,l995 April, 1999 25.5 3.35Ei-04 25.5 3.35E-i-04 328 299 11.0 10.0 85 50 2.8 1,.7 - Table 2 Estimated Total Radioactivity in Soil Volume I I Volume I t Average Concentration I Total Activity ~ Revision29 Date 1/11/02 H-15 7 Total activity after Iast spreading event Total activity decay corrected to April 1, Radionuclide (@/acre) ,1999 (pCi/acre) Mn-54 0,17 0.1 1 Co-60 5.93 5.5s Zn-65 0.074 0.044 CS-137 32.27 3 1.90 - BVY 99-80 / Attachment 1 / Page 11 Total activity after proposed soil disposal OrWacre) 0.1 1 6.44 0,044 37.16 Radionuclide Co-60 211-65 CS-137 Mn-54 Table 4 Total Projected Radioactivity on South Field Remaining at License Expiration Total Activity as of License Expiration (pCVacre) - 8.9E-07 0.89 7.6E-09 26.33 Critical Organ Dose Factor Table 5 Whole Body Dose Factor Radionuclide Mrl-54 CO-60 Zn-65 (mtemlyr per pCi/acre) (mrernlyr per pCi/acre) IndividuaVOrgan AdddGI-LLI 3.75E-04 I .93E-04 TeenLung 7.17E-04 5,3 1E-04 1 A4E-02 1 .a3~-02 Child/Liva Revision 29 Date 1/11/02 I1 H-16 P Radionuclide IndividuaYOrgan Mn-54 Teen/Lung CO-60 Teen/Lung Zn-65 ChildCLiver CS-137 ChildiBone BW 99-80 / Attachment 1 /Page 12 CriticaI Organ Whole Body Dose Factor Dose Factor (mremlyr per @Xiacre) (rnnmlyr per pcdacre) 1.02E-02 3.12E-03 3.19E-02 9.09E-03 1 .WE-02 1.258-02 6.98E-03 3.8 5E-03 Present Dose Impact' (Maximally exposed Case individual) Dose Individual/ (mrem/yr) Organ Cobalt-60 4.75E-04 Whole body 6.42E-04 Max. Organ Cesium-137 3.69E-03 Whole body 1.40E-02 Max. Organ Table 7 Dose Contribution from Co-60 and (3-137 in 25.5 m3 Soil Volume after Land Spreading Future Dose Impacv (Inadvertent Intruder) Dose Individual/ (mredyr) Organ 1.29E-03 Whole body 4.51E-03 Max. Organ 1.47~-02 Whole body 2.66E-02 Max. Organ Based on inventory of Co-60 of 0.895 pCi/acre and Cs-137 of 5.26 pCllacre in Apnl 1, Based on inventory of CO-60 of 0.14 1 pCi/acre and Cs- 137 of 3.82 pcilacre in April 1, 1999. 2013. 1 Revision 29 Date 1/11/02 H-17 I I BVY 99-80 / Attachment 1 f Page 13 Case Case One South Field as it currently Case Two South Field if disposal of soil volume is approved Increase in dose impact fiom disposal of soil exists Table S, Present and Future Dose'Jrnpact Due to the Soil Spreading for Two Cases Present Dose Impact (Maximally exposed individual) . Dose Individual/ (mremEyr) Organ 2.58E-02 Whole body 8.9%-02 MS. brgm 3.00E-02 Whole body 1.04E-02' Max. Organ 4.17E-03 Whole body 1.46E-02 Max. Organ Dose (mredyr) 9.7OE-02 1.89E-01 1.13E-01 2.2 1 E-0 1 1.60E-02 3.1 IE-02 Individual/ Organ Whole body Max. Organ Whole body ChiWBone Whole body Max. Organ Revision 29 Date 1/11/02 ll I ' k-18 VERMONT NUCLEAR 185 Old Ferry Road, Brattleboro, VT 05301-7002 (802) 257-5271 I / YANKEE . POWER CORPOFWTION United States Nuclear Regulatory Commission ATM: Document Control Desk Washington, DC 20555 January 4,2000 BW 00-02

References:

(a) Letter, VYNPC to USNRC, "Request to Amend Previous Approvals Granted Under 10 CFR 29.302(a) for Disposal of Contaminated Septic Waste and Cooling Tower Silt to Allow for Disposal of Contaminated Soil," BVY 99-80, dated June 23,2999

Subject:

Vermont Yankee Nuclear Power Station ' License No. DPR-28 Docket No. 50-271) Supplement to Request to Amend Previous Approvals Granted Under 10 CFFt 203021a) to Allow for Disposal of Contaminated Soil Reference (a) provided Vermont Yankee's application to amend the previously granted approvals to dispose of slightly contaminated septic waste and cooling tower silt on-site to include slightly cbntaminated soil generated as a residua1 by-product of on-site construction activities. The request was to allow the disposal of approximately 25.5 cubic meters of waste that has been accumuIated to date and to allow for disposal of future waste from construction related activities. Based on discussions with USNRC staff, additional information reIated to the estimated volume and dose consequences of the proposed future material was needed to complete your review. Attachment 1 has been revised accordingly to include the .infomation requested. Attachment 1 supercedes the evaluation previously submitted. We trust that the information will allow you to compIete your review of our submittal. However, should you have any questions or require further information concerning this matter, please contact Mr. Jim DeVincentis at 802-258-4236. . ? Sincerely, Vermont Yankee Nuclear Power Corporation 1 Gautam Sen 1 Gautam Sen Licensing Manager Attachment cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS VT Deparbnent of Public Service II . H-19 Revision 29 Date 1/11/02 7 Lb -.

SUMMARY

OF VERMONT YANKEE COMilMTMENTS COMMITMENT COMMLTIXD DATE 0R"OUTAGE . None NIA 11 BVY NO.: 00-02 The foUowing tabIe identifies commitments made in this document by Vermont Yankee. Any other actions discussed in the submittal represent intended or planned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments, ll Revision 29 Date 1/11/02 H-20 VYAPF 0058.04 AP 0058 OriginaI Page 1 of 1 I I .. 1. Docket No. 50-27 I . BVY00-02 Attachment 1 Vermont Yankee Nuclear Power Station Assessment of On-site Disposal of Contaminated Soil by Land Spreadkg Revision 29 Date 111 1/02 H-21 7 b BVY 00-02 / Attachment I I Page 1 of 17 -' TABLE OF CONTENTS - Page LIST OF TABLES ............................................................................ 2 I .O,. INTRODUCTION . . . . . . . . , . . . . . . . , , . , . , +. . . +, . , , . , . .. . . . . . . . . . .. . . . . . . . . . .. . . . . . .. 3 1.1 Background ....... .............................................................. 3 1.2 Objective . .I ...... . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .-. . . . . . . . . . . . . . . . . . . . . . . . . . ... 3 ' 2.0 WASTE DESCRIPTION ...........

..............................................

f.... 4 3.0 SOIL DISPOSAL AND ADMINISTRATNE PROCEDURE REQUIREMENTS.. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . + .: . . . . . . . . . . ..,. . . . . . .. 5 4.0 EVALUATION OF ENVIRONMENTALIMPACTS ............................... 6 4.1 Site Chcteristics , . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. :. . . . . . . . . . . . . . . . . . .:. , . . . . .;. 6 4.2 RadioIogicd Impact ................................................................... 7 5.0 RADIOLOGICAL PROTECTION ....................................................... 9

6.0 CONCLUSION

S ........................................................................... 9

7.0 REFERENCES

.................................*....,,...............................,.,,... 11 Revision 29 Date 1/11/02 I H-22 .-. BW 00-02 / Attachment 1 /Page 2 of 17 _. LIST OF TABLES Table 1: Radioanalytical Results of Composite Soil Samples ........................... Table 2: Estimated Total Radioactivity in 25.5 m3 Soil Volume.. .................. .:. 12 12 Table 3: Estimated Total Radioactivity in Future Soil Additions.. ..................... Table 4: Record of Septic and Silt Radioactive Material Spread each Year on South 13 Field Disposal Plot .......................................................................

13. .. Table 5: Total. Projected Radioactivity Remaining on South'Filed at License' . Expiration..

....... ..is.. ................................................................. I4 Table 6: All-Pathway Critical Orgadwhole Body Dose Conversion Factor&. ....... 14 Table 7: Dose Impact from Past Septic and SiIt Spreading Activity. .:. ................ 15 Table 8: Dose Impact ftom Past Septic and Silt Spreading 'and Single 25.5m3 Soil ..... -. .. . -- ._ - .- . - .. - . .... .................... Disposal.. .. .................................................. .. .. I5 Table 9: Dose Impact fiom Present and Future Soil Disposal Along with Past Septic and Silt Disposal,, ...................................................................... 16 TabIe 10: Dose Impact from Past Disposals through 7/15/99 Plus all Annual Projected Disposals of Septic, Silt and Soil.. .................................................... 1 I6 .- Table 1 1 : Summary of Dose Impacts Associated with Different Disposal - Scenarios .......................................................................

.............

17 I Revision 29 Date 1/11/02 H-23 *. I BW 00-02 I Attachment I I Page 3 of 17 1.0. INTRODUCTION . 1.1 Background In 1989, Vermont Yankee Nuclear Power Corporation requested approval from the NRC to routinely dispose of slightly contaminated septic waste in designated on-site areas in accordance with lOCFR20.302(a). Approval fiom the NRC was granted on August 30,1989 and the information was permanently incorporated into the Offsite Dose Cdcdation Manual (ODCM) as Appendix E. In 1995, Vermont Yankee Nuclear Power Corporation requested that the previous authorization for on-site disposal of very low-level radioactive material in septic waste be amended to permit the on-site disposal of slightly contaminated coohg tower silt material. Approvd fiom the NRC was granted ori June 18,1997 and the information was permanently incorporated into the ODCM as Appendix F. In 1994, approximately 25.5 m3 of excess soil was generated during on-site construction activities. Subsequent sampling and analysis of the soil revealed low levels of radioactivity that were similar in radionuclides and activity to the septic waste and cooling tower silts pfeviously encountered. An evaluation determined that the soil could be managed in similar fashion as the septic waste and cooling tower silts; however, prior approval from the NRC would be required under 10 CFR 20.2002 (formerly 20.302(a)). -. 1.2 Objective The purpose of this assessment is to present the data and radiological evaluation to demonstrate that the proposed disposition of the soil (Le., on-site disposal via land spreading on designated fields) will meet the existing boundary dose conditions as approved by the NRC for septic waste and cooling tower silt. The boundary conditions established for disposal of the septic waste and cooling tower silt on designated plots are: -' I. The dose to the whole body or any organ of a hypothetical maximally exposed individual must be less than 1 .O mredyr. 2. Doses to the whole body and any organ of an inadvertent intruder &om the probable pathways of exposure are less than 5 rnredyr. 3. Disposal operations must be at one of the approved on-site locations. Revision 29 Date 1/11/02 I H-24 V I L BVY 00-02 / Attachment 1 / Page 4 of 17 Revxion 29 Date 1/1 1/02 2.0 WASTE DESCRIPTION The existing accumulation of contaminated soil was derived fkom excavation activities associated with the construction of a new security fence along the plant's Protected Area boundary. The volume of soil generated was approximately 25.5 m3, and is typical of fill material containing light to dark brown poorly sorted soils with some small stones, and includes small incidental pieces of asphalt. The soil was removed from its original location by shovel, backhoe and fiont-end loader, and placed into dump trucks for transport to a location between the cooling towers where it was deposited on the ground surface and covered to prevent erosion. This location was selected because it was away fiom areas routinely occupied by plant sW, and could easily be controlled. The most probable source of the low levels of radioactive contamination is the presence of below detectable removable contamination redistributed by foot tr&c fiom inside the plant to walkways and parking areas. Subsequent Surface runoff carries the contamination to nearby exposed soil near the Protected Area boundary where it had accumulated aver time to low level detectable cdncentrations. In April 1995, a total of 20 composite soil samples were collected to characterize the accumulated volume. Composites were obtained by taking a grab sample from opposite sides of the pile and the top at equal distances along its length. These three grab samples were then combined into one composite sample. Soil samples were sent to the Yankee Atomic Environmental Laboratory for analysis and counted to environmental Iower Emits of detection required of environmental media Results of the analyses are presented in Table 1. For estimating the total activity in the soil pile, the actual analytical resdt was used for those samples that were Iess than the MDC to calculate the average radioactivity concentration. Analytical results are provided for both the times when the samples were collected as well as decay corrected to the present (7/15/99). The resdts identified both Cs-137 and CO-60 in most of the composite samples, which verified that plant-related radioactivity, was present in the soil. The mass of accumulated soil (dry) was estimated by multiplying the total in-situ volume (25.5 m3) by it's wet density, 1.47E-tO3 kg/m3, and then dividing by the wet:* ratio of 1.12, thus yielding a mass of 3.35E+04 kg (dry). The mass of the soil wits then multiplied by the average measured CO-BO and Cs-137 concentrations to obtain the total activity of each radionuclide in the 25.5 m3. Table 2 presents the estimated total radioactivity in the 25.5 rn3 volume at the time of sample collection and analysis, and decay corrected to the date of the most recent disposal (septic waste) spreading operation @e., July 15,1999). BW 00-02 Attachment 1 i Page 5 of 17 evaluating the radiological impact of potential future soil disposals, it is assumed that an additional 28.3 m3 per year of sand / soil is contaminated at the same concentration levels as originally observed (April 1995) in the currently collected 25.5~11~ of soiI. It is also assumed that this materid is placed on the same approved disposd fieId used for all past septic and cooling tower silt disposal operations. Table 3 shows the estimated amount of radioactivity associated with the annual disposal of the 28.3m3 of soil. It is assumed that this material is disposed of each year for the next 14 years (until the end of pIant operating license in 20 13) on the same field (South Disposal Plot) dong with the continued application of septic waste and cooling tower silt. Table 4 shows a record of the acid amount of septidsilt. materid that has been spread on. south field for the past 10 years. A review of the actual waste disposal operations show that the annuaI average radioactivity content placed on the 1.9 &re South field horn septic and silt disposds are as follows: Mu-54 0.147 uCi/year CO-60 2.58 uCi/year Zn-65 0.269 uCi/year CS-134 0.010 uCiiyear CS-137 6.21 uciyear The maximum radioactivity inventory resulting fiom the accumulated buildup of past and projected future disposal operations (i.e., septic waste, cooling tower silt;plus the existing 25:5m3 of accumulated soil along with a projected annual addition of 28.3m' of soil each year until the termination of the operating license) is shown on Table 5. 3.0 SOIL DISPOSAL AND ADMlTyISTRATIvE PROCEDURE REQUIREMENTS The method of soil disposd will use the technique of land spreading in a manner consistent

    • with the current commiments for the on-site disposal of septic waste and cooling tower silts as approved by the NRC. The accumulation of radioactivity on the disposal plot for this soil spreading operation will be treated as if cooling tower silt or septic waste was being disposed of since the characteristicsnf all these residual solids are similar (earthen-type matter). .The south field (approximateIy 1.9 acres in size) has been designated and approved for septic waste and cooling tower silt disposal and has been used for all past disposal operations, and is expected to be used for the placement of soil. Determination of the radiological dose impact has been made based on the same models and pathway assumptions used in the previous submittals.

Dry soiI material will be dispersed using typical agricultural dry bulk surface spreading practices in approved disposal areas on-site. Incidental pieces of asphalt and stones that picked up with the soil will be screened out before the soil is spread and disposed of as radioactive material at an off-site licensed facility if detectable radioactivity is found. are H-26 Revision 29 Date 1/11/02 'I .. . BVY 00-02 I Attachment 1 / Page 6 of 17 Records of the disposal that will be maintained include the following: .- (a) The radionuclide concentrations detected in the soil (measured to environmentd (b) The total voIume of soil disposed of. (c) The total radioactivity in the disposal operation as well as the total accumulated (d) The plot on which the soil was applied. (e) Dose calculations or npxhum allowable accumulated activity determinations required to demonstrate that the dose limits imposed on the land spreading lower limits of detection). OR each disposal plot at the time of spreading. operations have not been exceeded. .. To ensure that the addition of soil containiug low levels of adioactivity will not exceed the boundary dose limits, each new spreading operation will require an estimate of totat radioactivity that includes all past disposds of septic waste, cooling tower silt and soil material on the designated disposal plots. This will be compared with the boundary dose limits or equivalent radioactivity limits on a per acre basis, In. addition, concentration limits applied to the disposal of earthen type materials (dry soil) restrict the placement of small volumes of materials that have AativeIy high radioactiviv concentrations. Any farmer leasing land used for the disposd of soil (or other approved waste) will be notified of the applicable resbictions placed on the site due to the spreading of low level contaminated material. These restrictions are the same as detailed for the previously approved septic waste spreading application. 4.0 EVALUATION OF ENVIRONMENTAL EMPACTS 4.1 Site Characteristics All designated disposal sites are located OR the Vermont Yankee NucIear Power Plant site and are within the site boundary security fence. The south field consists of approximately 1.9 acres and is centered approximateIy 1500 feet south of the Reactor Building. This parcel of land has been previously approved by the NRC for the land disposal of septic waste and cooling tower silt, and is the only portion of the approved disposal areas which has been utilized to-date for the spreading of contaminated material. For estimating the rnaxhw future radiological impact, it is assumed in the analysis that all future disposal operations Will continue to use the South field as the disposal plot. Revision 2 Date 1/11/02 I H-27 I I BVY 00-02 1 Attachment 1 I Page 7 of 17 ~ 4.2 Radiological Impact _. The amount of radioactivity added to the south field is procedurally controlled to ensure that doses are maintained within the prior approved limits of the boundary conditions. Revi\ion= Date 1/11/02 To assess the dose received by the maximaIIy exposed individuaI during the period of plant controls over the property, and to an inadvertent intruder after it is assumed plat access controIs end, the same pathway modeling, assumptions and dose calculation methods as approved for septic and cooling tower silt disposd were used. These dose models implement the methods and dose conversion factors as provided in Regulatory Guide 1.109, Revision 1 (1 977). The following six potential pathways were identified and &cIuded in the analysis,: (a) Standing on contaminated ground. . (b) Inhalation of resuspended radioactivity. (c) Ingestion of Ieafl vegetables. (d) Ingestion of stored vegetables. (e) Ingestion of meat. .+ (f) Ingestion of cow's milk. As shown in the previous application for septic waste disposd, the liquid pathway was found to be an insignificant contributor to the dose for the radionuclides idenaed fixed in the soil type matrixes associated these waste forms. Therefore, the liquid pathway is not considered in this analysis. Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways, the difference between them being due to the occupancy time. The basic assumptions used in the radiologicd analyses include: (a) Exposure to ground contamination and re-suspended radioactivity is for a period of 104 hours per year during the Vermont Yankee active control of the disposal sites and continuous thereafter. The 104-hour interval is representative of a farmer's time spent on a plot of land (4 hours per week for 6 months). H-28 BW 00-02 I Attachment 1 I Page 8 of I7 occurs at the saqe time (2013) for both the Conk01 Periodand Intruder scenarios. For the analysis of the radiologicd impact during the Vermont Yankee active control of the disposal sites until 2013, no plowing is assumed to take place and aI1 dispersed radioactive material remains on the surface forming a source of unshielded direct radiation. (c) (d) The crop exposure &ne was changed from 2160 hours to 0 hours to reflect the condition that no radioactive material is dispersed directly on crops for human or animal consumption. Crop contamination is only through root uptake. I (e) The deposition on crops ofxe-suspended radioactivity is insignificant. (f) Most of the pathway data and usage factors used in the analysis are the same as those used in the Vermont Yankee's ODCM assessment of off-site radiological impact fiom routine releases. The hction of stored vegetables grown on the contaminated land was conservatively increased fiom 0.76 to 1 .O (at present no vegetable crops for human consumption are grown on any of the approved disposal plots). For each year's spreading operations, the soil exposure time to account for buildup was changed from the standard 15 years to 1 year. .. - . (g) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the operating license expires in 2013 (Le., the source term accumuIs?ted on a single disposal plot applies also for the inadvertent intruder). (h) For the analysis of the impact der Vermont Yankee control of the site is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of the soil; but nonetheless, undergoes re-suspension in the air at the same rate as the unplowed surface contamination. However, for direct ground plane exposure the self-shielding due to the six- inch pIow layer reduces the surface dose rate by about a factor of four. .

  • The dose models and methods used to generate deposition values and accumulated activiw over the operating life of the plant are documented in the Vermont Yankee ODCM. The total activity that would be present on south field at the end of the operating period (Le., total elapsed time of 14 years post July 1 5,1999, or 20 13) from the buildup of all waste streams @e., septic, cooling tower silt and soil) is presented in Table 5. I Revision 29 Date 1/11/02 H-29 BW 00-02 I Attachment 1 I Page 9 of I7 In order to evaluate the dose iqpact associated with the different disposal streams, a dose assessment was performed for the following four disposal scenarios:
0) (II) (III) Impact fiorn past septic and silt spreading only - Table 7 Impact fiom past septic and silt spreading, plus a single 25.5m3 soil disposal operation for the existing accumulated soil - Table 8 Impact from past septic and silt disposals along with the existing 25.5 m3 of accumulated soil and postulated future annual soil disposal volumes (28.3 m3 /y). -Table 9 Impact from past septic and silt disposals plus annual projected disposals of septic, silt and soil. -Table 10 For each scenario, the critical organ and whole body dose Gom all pathways to a maximally exposed individual for both the Vermont Yankee control period and the inadvertent intnzder situation were calculated.

The dose calculations were performed using the dose conversion factors presented in Table 5, which were obtained fiom the Vermont Yankee ODCM, Appendix F, "Approval Pursuaut to lOCFR20.2002 for On-Site Disposal of Cooling Tower Silt." 0 A: summary of the cdcdated dose impact associated with the four different scenarios is shown in Table 1 1. These results demonstrate that disposal of the 25.5 m3 of accumulated soil will be well witbin the accepted dose limit criteria of 1 mredyr to any organ or whole body during the control period, and 5 mredyr to an inadvertent intruder. In addition, if continued soil spreading is necessary, the resulting dose is expected to dso remain below the established limits even assuming the annual application of already approved disposal media (Le., septic waste and cooling tower silt). + 5.0 RADIOLOGICAL PROTECTION

l. The disposal operation of the soil will follow the applicabIe Vermont Yankee procedures to maintain doses as low as reasonably achievabk and within the specific dose criteria as previously approved for septic waste and cooling tower silt disposal.

6.0 CONCLUSION

S Soil generated fiom on-site construction and maintenance activities constitutes an earthen me material similar in characteristics to septic waste residual solids and cooling tower silt with respect to the radiological pathway behavior and modeling. Based on the similarity in characteristics between the proposed soil voIume and waste streams that have already been approved for disposal and the evaluation of the incremental dose impact, it is concluded that the disposal of the existing 25.5 m3 and the projected 28.3 m3/year of soil through on-site land spreading will meet the existing NRC approved boundary dose conditions specified in H-30 I Revision 29 Date 1/11/02 3W 00-02 f Attachment 1 I Page 10 of 17 the Vermont Yankee ODCM (see Appendix B for Septic Waste Disposal). That is, with respect to the addition of the initial 25.5 m3 of soil along witti the projected 28.3 m3/year of soi1 and the projected future disposal of septic and silt waste to the existing radioactivity already spread on the south field 1. Total doses to the whoIe body and criticd organ of the hypothetically maximally exposed individual were estimated as 1.1 5E-01 mredyr and 4.03E-0 1 medyr, respectively, which are Iess than the prescribed 1 .O mredyr limit during the period of active site contxol. . 2. Total doses to the whoIe body and critical organ of an inadvertent intruder fiom the . probabIe pathways of exposure were estimated as 7.57E701 mredyr and 1-17 mredyr, respectively, which are Iess than 5 mdyr limit associated with an intruder scenario following assumed loss of site accesS control as the end of the operating license. 3. For purposes of projecting maximum impact, all disposals (past and We) are assumed Therefore, the disposition of the present 25.5 m3 and the projected 28.3 m3/year of soil will chime to meet the existing boundary conditions as approved by the NRC for septic waste and cooIing tower silt. to take place on the south disposal plot. .- - Revision 29 Date 1/11/02 #I I I I -_ BW 00-02 f Attachment 1 I Page 1 l'of 17 .. 7.0 REFEFCENCES (1) Vermont Yankee ODCM, Rev 23, Appendix B, "Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont Yankee". , (2) Vermont Yankee ODCM, Rev 23, Appendix F, "Approval Fbrsuant to lOCFR20.2002 (3) USNRC Regulatory Guide 1.109, Rev I, "Calculation of Amd Doses to Man from . for On-Site Disposal of Cooling Tower SiIt". Routine Releases of Reactor Effluents for the Purpose of Evalua~g Compliance with ZOCFR Part 40, Appendix I", dated October 1977. .. . -- ._ - . . . Revision 29 Date 1/11/02 H-32 - BVY 00-02 / Attachment 1 J Page 12 of 17 TabIe 1 I Revision 29 Date 1/11/02 RadioanaIytical Results of Composite Samples Taken from 25.5m3 Soil Pile - _-. H-33. . -_ -I. . ". . .-. . Smule TD (32271 6 022717 G22718 G22719 G22720 G22721 G22722 G22723 G22724 G22725 G22726 G22727 G22728 G22729 G22730 G2273 1 G22732 G22733 G22734 G2273 5 CS-137 CO-60 @Ci/kg) (Pew Ad. 1995 July 15,1999 Auril. 1995 July 25.1999 234 212.2 49 28.0

  • 522 473.4 143 81.7 .- 337 305.7 37 21.1
  • 29 1 263.9 111 63.4 348 315.6. , 47 26.8 * . 135 122.4 ; 73 41.7 1 07 97.0 82 46.8 180 163.3 92 52.6 269 244.0 118 67.4 810 734.7 . 114 65.1 378 342.8 106 60.6 810 734.7 124 . 70.8 376 341 .O 62 35.4 33 1 300.2 87 49.7 253 229.5 5 2.9
  • 150 136.0 58 33.1 247 224.0 105 60.0 326 2957 54 30.8
  • 23 5 213.1 100 57.1 Average 328 298 85 49 Maximum 810 735 143 82 Minimum 107 97 5 3 StdDev. 186 169 36 20 222 20 1.4 140 80.0 *The apparent response of the gamma isotopic analysis was less than the Minimum DetectabIe Conceneation.

Table 2 Estimated TotaI Radioactivity in 25.Sm3 Accumulated Soil ? A BVY 00-02 /Attachment 1 /Page I3 of 17 Table 3 Estimated Total Radioactivity in Future Soil Additions Volume Soil Average Concentration of soiI Mass (pcfig-dry assuming) Total Activity Nuclide (m3) Ike-drvl cA~riI.1995 concentrations1 lUCi/VT) Cs-137 28.3 3.72E+04 . Co-60 28.3 3.72E+04 328 85 12.8 3.16 Table 4 Record of Septic and Sit Radioactive Material Spread Each Year on the South Field . ,I Spreading Materid Mn-54 Cod0 ZU-65 0-134 c5137 Ce-141 Year Date Type (uCi/acre) (uCVacre) (uCi/acre) (ucilacre) (nCilacre) (uCi/acre) t990 1990 1991 1992 1993 1994 1995 1996 1997 1998 1998 1999 10/3 1/90 11/20/90 10/19/92 10/14/93 06/ 14/94 06/29/95 06/18/97 omo/ga 09/28/98 07/15/99 Septage Septage no spreading septage septage septage septage no spreading septage septage Silt Septage - 0.00 3.89 0.17 2.03 0.00 0.00 0,ll 1.73 0.05 1.41 0.08 .0.43 0,OO 0.88 0.00 0.00 0.12 1 .oo 0.14 0.72 0.00 0.00 0.1 1 1.47 0.00 0.41 0.00 0.52 0.2 I 0.00 0.00 0.00 0.00 0.09 0.00 0.00 026 0.00 0.29 0.00 0.00 0.05 0.32 0.00 0.30 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.19 0.00 0.12 0.00 30.87 0.00 1.40E-08 0.00 0.006 0.00 0.00 0.00 .a00 0.00 0.00 0.00 0.20 0.00 0.25 0.00 (UCVacre): 0.08 1.36 0.14 0.01 3.27 0.0 1 -- 4verage Activitylyr Average Activity disposed of on 1.9 significant (uCi/yr) to be 0.147 2.58 0.269 0.010 6.21 0.001 not acre field H-34 Revision 29 Date 1/11/02 BW 00-02 1 Attachment I I Page 14 of 17 Revision 29 Date 1/11/02 Table 5 Total Projected Radioactivity Remaining on South FieId after'license Termination ' H-35 . ' :', .. Accum. Activity in Silt & Septic @ Year 2013 Nuclide a Mn-54 , 026 - CO-60 19.68 Zn-65 0.42 CS-137 119.03 CS-134 0.04 Accum. Activiw Accum. Activity in soil Total All Paths @ year 2013 @ year 2013 :luci') cuci) - 0.26 21.83 41.51 - 0.42 154.74 273.78 - ~' ' 0.04 .. Accum. Activity Total All Paths @ Year 2013 ~ (uCi/acre>* 0.14 21.85 0;22 144.09 0 -02

  • The total activity is assumed to be spread on the 1.9 acre South field to generate the uCi/acre value. Table 6 AII Pathway Critical Organ/WhoIe Body Dose Conversion Factors During W Control Post W Control putruder Scenario)

Radionuclide Mn-54 CO-60 211-65 cs-I37 XndividuaVOrvan AdddGI-LLI Teedung - - ChiId/L.iver Child50ne Critical Organ . Dose Factor (mremlyr per yciacre) 3.75E-04 7. I E-04 I .62E-02 2.66E-03 Whole Body Dose Factor (mremlyr per pcilacre) 1.938-04 5.31E-04 1.03E-02 7.02E-04 Critical Organ Dose Factor Lmremfvr uer $ifacre) 1.02E-02 3. I9E-02 1.89E-02 6.98E-03 Whole Body Dose Factor (mredyr per pciiacre) - 3.12E-03 9.09E-03 . 1.25E-02 3.85E-03 L BVY 00-02 1 Attachment 1 I Page 15 of 17 Table 7 (Scenario I) Dose Impact from Past Septic and SiIt Spreading on South Field (as of 7/15/99) Control Sccnarfa: HaISLifC .fEiEl . Mn-54 086 CoaO 527 Cs-137 30.17 zp-65 .,0.67 Intruder Scenario: Half-Life Iyears) Mn-54 0.86 CQ-60 527 20-65 0.67 - c5-137 30.17 .. . _,I_.. AI1 Other Spdmgs To Datc 030 6.86 023 - 3 192 fUCiiaCrrl AI1 mer Spdmgs To Datc 020 6.86 0.23 31.92 ~uciiacrc~ Activity on Plat Decayed to Year2013 23 IE-06 1 .OXE+OO 1.1 SE-07 231EM1 ~UCiacfcl I~Wd~l ~mrrmh.rluc'iacre) fmdwl frnrcm/vr\ 7.17E-04 531E-04 4.m-03 3.63E-03 1.62E-M 1.03EM 3.77E-03 2.40E-03 2.6633 .7.m-04 8.49E-02 224E-02 3.7sE04 133844 73935 3.788-05 Total. I 937E-02 . I 2.85E-02 I Dose Limit: 1' I ?4 of Limit 937% 2.85?6 .. MaximumOrgm WholeBody Maximum WhoteBody Dost Factor DoritFactDr OrganDosc Dose ~mrrmlvr~d~~ IdvKd~] irnrcrn/yr> {mrcdvrl 1.02EM 3.12EM 236E-08 722E-09 3.19E-02 9.09E-03 3.46E-02 9.85E-03 1.89EM 1.2SE4Q 217E-09 I.43E-09 698E-03 3.uEm 1.62E-O 1 8.9 IE-OZ % OfLimit 3.92% 1.98% Table 8 (Scenario IC) Dose Impact from Past SeptidSilt Spreading and Single 25.5m3 Soil Disposal Controt Scenario: Half-Life r(eassl Mn-54 0.86 -0 527 zn-65 0.67 CS-I37 30.17 Intruder Sctnaria: Half-Life cycan) Mu-54 0.86 (2-60 527 211-65 0.67 &I37 30.17 All spreaftiigs toDate' 7.70 0233 37.19 7.17E-04 1 .&?E42 2.66E-03 5.3 IE-04 552E-03 4.09E-05 1.03E-02 3.77E-03 2.10E-03 7.02E-04 9.89E-M 2.6 1E-02 Totalal~~~: 1 1.08E-01 I 326E-E 1 Dose Liir 1' 1 % of Liir 10.83% 3.2694 All Spreadiigs Activity on Plot Maximum Orgm Wholc Body Maximum Whole Body tom Decaycdto2013 DoscFaaor Dose Factor Organ Dose Dose luc'iaml fucilaerc) ~mmrtmlvr/uciiaete) (rnrcmh/uCidacre> $mrcm/yr) Imrcm/vtl 0.196 23 1E-06 1.ME-OZ 3.12E-03 236E-08 7.22509 7.70 1uE+oo 3.19E02 9.G9E43 3.8XE-02 1.11E42 37.19 2.70E+01 6.98E-03 3.85E-03 1.88E-01 1.04E-0 1 0233 1.15E-07 1.89E-02 I25E-M 2.17E-09 1.43E-09 Totalhsc 1 227E-01 I l-I5E*Ol % of Lit 454% 2.30% DoscLimit: . 5 5 Revision 29 Date 1/11/02 H-36 UNITED STATES :EAR REGULATORY COMMISS Revision 29 Date 1/11/02 or H-37 WASHINGTON. D.C. x)555ooo1 Mr. Samuel L. Newton June .15, 2000 NXq 00-58 Vice President, Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION, REQUEST TO AMEND PREVIOUS APPROVALS GRANTED UNDER IO CFR 20.302(a) TO ALLOW FOR DISPOSAL OF CONTAMINATED SOIL (TAC NO. MA5950) *-

Dear Mr. Newton:

By !etter dated June 23,1999, as suppiemented on January 4,2000, you submitted a request to amend a previously approved apptication granted by the Nudear Regulatory Commission (NRC) pursuant to 10 CFR 20.2002 (previously 10 CFR 20.302) to allow the addition of slightly contaminated soil and soiVsand material to the list of already approved materials-(i.e., septic waste and cooling tower silt) for on-site disposal via land spreading on designated fields. . We have completed our review of your proposal and find it to be acceptable because the previously approved bounding conditions will continue to be met. Pursuant to the provisions of 10 CFR Part 51, the NRC has published an Environmental Assessment and Finding of No Significant Impact in the Federal Register on June . 15 .- ,2000 (65 FR 37583 ). Docket No. 50-271

Enclosure:

Safety Evaluation cc w/encl: See next page John b4 . Zwolinski, Director Division of Licensing Project Management Office of Nuclear Reactor Regulation Vermont Yankee Nuclear Power Station cc: Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 .- .. I Mr. David R. Lewis Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. Washington, DC 20037-1 128 Mr. Richard P. Sedano, Commissioner Vermont Department of Public Service 11 2 State Street ' Montpelier, VT 05620-2601 Mr. Michael H. Dworkin, Chairman Public Service Board . State of Vermont 112 State Street Montpelier, VT 05620-2701 Chairman, Board of Selectmen Town of Vernon P.O. Box 116 Vernon, VT 05354-01 16 Mr. Richard E. McCullough Operating Experience Coordinator Vermont Yankee Nuclear Power Station P.O. Box 157 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq. Deputy Attorney General 33 Capitol Street Concord, NH 03301 -6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Ms. Deborah 6. Katz Box 83 Shelburne Falls, MA 01 370 Mr. Raymond N. McCandless Vermont Department of Health Division of Occupational and Radiological Health 108 Cherry Street Burlington, VT 05402 Mr. Gautam Sen Licensing Manager. Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road P.0, Sox 7002 Brattleboro, VT 05302-7002 Resident Inspector Vernont Yankee Nuclear Power 'Station U. S. Nuctear Regulatory Commission P.O. Box 176 Vernon, VT 05354 .' Director, Massachusetts Emergency Management Agency ' ATTN: James Muckerheide Framingham, MA 01702-5399 . 400 Worcester Rd. Jonathan M. Block, Esq. Main Street Putney, VT 05346-0566 - P. O..BOX 566 - 1 1 Revision29 Date 1/11/02 I . H-38 . 7 I UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554CQY Revision29 Date 1/11/02 SAFETY EVALUATION BY TH* OFFICE OF NUCLEAR REACTOR REGULATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 .. 1 .O INTRODUCTION By letter dated June 23,1999, as supplemented on January 4,2000, Vermont Yankee Nuclear Power Corporation (the licensee), submitted a request to amend a previously approved application granted by the Nuclear Regu!atory Comrnjssion (NRC) pursuant to 10 CFR 20,2002 (previously 10 CFR 20.302) to allow the addition of slightly contaminated soil and soilkand material to the list of already approved materiak (Le., septic waste and cooling tower silt) for on-site disposal via land spreading on designated fields. In 1989, pursuant to IO CFR 20.302 (current 10 CFR 20.2002), the licensee received approval from the NFIC to routinely dispose of contaminated septic waste in designated on-site areas. In 1997, the NRC amended the approved on-site disposal application to also include contaminated ' cooling tower silt material.

2. In this 10 CFR 20.2002 amendment application, the licensee identified 25.5 cubic meters of soil to be disposed of on-site immediately, and approximately 28.3 cubic meters of soikand material to be disposed of on an annual basis until the expiration of the plant's operating license in 2013. The 25.5 cubic meters of contaminated soil were generated as a result of on-site construction activities. The anticipated 28.3 cubic meters of soikand material will be generated from the annual winter spreading of sand on roads and walkways at the plant site. The licensee has performed a comprehensive radiological evaluation that includes all of the anticipated materials (Le., the current 25.5 cubic meters and the 28:3 cubic meters generated annually thereafter).

The licensee's evaluation shows that the soiVsand can be managed on-site in the same manner as the septic waste and cooling tower silt (Le-, by land spreading on designated fields). 2.0 *VALUATION ' .. The licensee will dispose of the soil and future soiVsand material using a land spreading technique consistent with its current commitments for on-site disposal of septic waste and cooling tower silts previously approved by the NRC. The licensee will continue to use the designated and approved areas of their property (approximately 1.9 acres in size) which currently receives the septic waste and cooling tower silts, Determination of the radiological dose impact of the new material has been made based on the same dose assessment models and pathway assumptions used in the previously approved submittals. H-39 2 1 The licensee wit! procedurally control and maintain records of all disposals. The following information will be recorded: H-40 Reviwnz Date 1/11/02 . 1. The radionuclide concentrations detected in the materia! (measured to radiation levels consistent with the licensee's radiological environmental monitoring program).

2. 3. The total volume of material disposed.

The total radioactivity in the disposal operation as well as the total radioactivity accumulated on each disposal plot at the time of spreading.

4. The plot on which the material was applied. 5. Dose calculations or maximum allowable accumulated activity determinations required to demonstrate that the dose condition values imposed (Le., imposed by this 10 CFR 20.2002 application) on the [and spreading operation have.

not been exceeded. The bounding dose conditions for the on-site disposals are as follows: 1. The annual dose fo. the whole body or any organ of a hypothetical maximally exposed individual must be less than 1.0 mrem; 2. Annual doses to the whole body and any organ of an inadvertent intruder from the probable pathways of exposure must be less than 5 mrern. Disposal operations must be at one of the approved on-site locations. , 3. To ensure that the addition of new material containing low levels of radioactivity will not exceed the bounding dose conditions, for each new spreading operation the licensee will calculate an estimate of the total radioactivity applied to the designated disposal plots. These calculated estimates will include all past disposaIs of septic waste, cooling tower silt, soil and soilkand material on the designated disposal plots. This wit1 be compared with the bounding dose condition value or equivalent radioactivity value on a pei-acre basis. In addition, Concentration limits will be applied to the disposed material to restrict the placement of small volumes of material that may have relatively high radioactivity concentrations. The licensee assessed the dose that may be received by the maximally exposed individual during the period of plant control over the property, and to an inadvertent intruder after plant access control ends using the same pathway m.odeling , assumptions, and dose calculation methods that were previously approved by the NRC for the septic waste and cooling tower silt disposals. The dose models are based on the guidance in NRC Regulatory Guide 1.109, Revision 1 (1 977). The licensee's dose assessment is as follows: L . .. - 3 2. Total annual doses .J the whole bAy and critical organ of an inadvertent intruder fr rn the probable pathways of exposure were estimated to be 0.757 mrem and 1.17' mrem. These values are less than the prescribed annual dose condition value of 5.0 mrem for the time period after active site control. 3. The dose calculations are based on projecting the maximum potential impact of all disposals (past and future) on the designated disposal plot of land. 3.0, CONCLUSION _- The staff finds the licensee's proposal to dispose of the tow-level radioactive soil and soilkand material, pursuant to 10 CFR 20.2002;in the same manner, location, and within the bounding dose conditions as the materials (i.e., septic waste and cooling tower silt) previously approved by the NRC to be acceptable because the bounding conditions will continue to be met. Principal Contributor: S. Klementowicz

r. Date: June 15, 2000 c c . .. I . H-41 Revision _29 Date 1/11/02 ll -. I I Appendix I 1. "Request to Amend Previous Approval Granted Pursuant to 10CFR20.2002 for DisposaI of Contaminated Soil", dated September 1 1*, 2000, BVY 00-71 2. Vermont Yankee Nuclear Power Station - Safety Evaluation for an Amendment to an Approved 10CFR20.2002 AppIication (TAC No. MA9972)", dated June 2dh, 2001, NVY 01-66 Revision 29 Date 1/11/02 ll 1-1 VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRATTLEBORO, VT 05302-7002 (802) 257-527 1 I September I 1,2000 BVY 00-71 Revirion2 Date 1/11/02 United States Nuclear Regulatory Commission A'ITN: Document Control Desk Washington, DC 20555

References:

(a) Letter, VYNPC to USNRC, "Request to Amend Previous Approvals Granted under 10 CFR 20.302(a) for Disposal of Contaminated Septic Waste and Cooling Tower Silt to Allow for Disposal of Contaminated Soil," BVY 99-80, dated June 23, 1999. Letter, VYNPC to USNRC, "Supplement to Request to Amend Previous ApFrovaIs Granted under 10 CFR 20.302(a) to Allow for Disposal of Contaminated Soil," BVY 00-02, dated January 4,2000. Letter, USNRC to VYNPC, crVermont Yankee Nuclear Power Station, Request to Amend Previous Approvals Granted under 10 CFR 20.302(a) to AHow for Disposaf of Contaminated Soil (TAC No. MA5950),"

NVY 00-58, dated June 15,2000. Letter, USNRC to VYNPC, "Revised Safety Evaluation - Approval Pursuant to 10 CFR 20.2002 for Onsite Disposal of Cooling Tower Silt - Vermont Yankee NucIear Power Station (TAC No. M96371)," NVY 97-85, dated June 18,1997. ..- (b) (c) (d)

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) Request to Amend Previous Approval Granted Pursuant to 10 CFR 20.2002 for Disposal of Contaminated Soil In accordance with 10 CFR 20.2002 (previously 10 CFR 20.302(a)), Vermont Yankee (VU) submits this application to amend the previously granted approval to dispose of slightly contaminated soil. This application expands the allowable waste stream to include slightly contaminated soil generated as a residual by-product of other types of on-site construction activities. In References (a) and (b), VY requested approval to dispose of approximately 25.5 m3 of accumulated soil that was generated due to construction .activities. In addition, it was requested that VY be aiIowed to dispose of approximately 28.3 m3 of soil that is spread annually on station roads and walkways during the winter, NRC acceptance is documented in Reference (c). This application specifically requests approval to dispose of contaminated soil that is created due to other on-site construction related activities including but not limited to design change implementation and land maintenance. 1-2 - BVY 00-7 I / fage 2 of 2 I Revision 29 Date 1/11/02 VERMONTYANKEENUCLEAR POWERCORPORATION 1-3 in addition, VY requests that NRC's review recognize that, although VY indicated in Reference (b) that the south disposal field (approximately 1.9 acres in size) is currently expected to be used for disposal of the subject material, VY is also authorized to use the alternate north disposal field (approximately i 0 acres in size). Approval to use both the north and south fields for disposal was granted in Reference (d). VY's radiological impact assessments have conservatively assumed all of the disposal activities occur on the smalter south field to maximize potential caIculated doses. These assessments bound the situation where a portion of the land spreading occurs an the north field. VY will continue to limit the total activity spread, from approximately 28.3 m3 of soil generated each year, to within the limits assumed in the radiological assessment previously submitted in Reference (b). A radiological assessment and proposed operational controls for the inclusion of the additional material for on-site disposal was provided in Reference (b). The assessment demonstrates that the dose impact expected from the proposed activity, in total with all past waste spreading operations, will not approach the dose limits already imposed for septic and cooling tower silt disposal. All soil analyses will be to environmental lower limits of detection. The results of all disposal operations will be reported in the Annual Radioactive Effluent Release Report. The combined radiological impact, for ail on-site disposal operations, will continue to be limited to a total body or organ dose of a maxirnaIly exposed member of the pubIic of less than oie mremjyear during the period of active VY control of the site, or less than five rnrem/year to an inadvertent intruder after termination of active site control. . Upon receipt of your approval, this request as well as the basis for approval will be incorporated into the Off-Site Dose Calculation ManuaI. We trust that the information contained in the submittal is sufficient. However, should you have any questions or require further information concerning this matter, please contact Mr. Jim. DeVincentis at 802-258-4236. Sincerely, Vermont Yankee Nuclear Power Corporation n Licensing Manager cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS VT Department of Pubtic Service

SUMMARY

OF VERMONT YANKEE COMMITMENTS r COMMITMENT COMMITIED DATE OR "OUTAGE" I BW NO.: 00-71 None 1.- The following table identifies commitments made in this document by Vermont Yankee. Any other actions discussed in the submittal represent intended or planned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regdatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments. NIA I Revision 29 Date 1/11/02 VYAPF 0058.04 AP 0058, Revision 1 Page I of 1 1-4 June 26, 2001 Mr. Michael A. Balduzzi NVY 01-66 Vice President, Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road P.O. Box 7002 Brattleboro, VT 05302-7002

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - SAFETY EVALUATION FOR AN AMENDMENT TO AN APPROVED io CFR 20.2002 APPLICATION (TAC NO. MA9972)

Dear Mr. Balduzzi:

The US. Nuclear Regulatory Commission (NRC) staff hqs completed its review of the Vermont Yankee Nuclear Power Corporation (VYNPC) request dated September 11 , 2000, to amend an approved 10 CFR 20.2002 (previously 10 CFR 20.302) application dated June 23,1999, as supplemented on January 4,2000. The licensee requested NRC approval to allow the addition of slightly contaminated soil resulting from on-site construction-related activities, including but not limited to, design change-implementation and land maintenance, to the list of already approved materials (i.e., septic waste, cooling tower silt and soiVsand from roads and walkways) for on-site disposal. Based on our review, we find the proposed changes to be acceptable because the previousIy approved bounding conditions will continue to be met. The enclosure to this letter provides our safety evaluation of WNPC's application. ' Pursuant io the provisions of 10 CFR Part 51, the NRC has published an Environmental Assessment and finding of No Significant Impact in the Federal Register on June 14,2001 (66 FR 32399). Sincerely, yk47JQ. Joh A. Zwolinski, Director Office of Nuclear Reactor Regulation Divis \ on of Licensing Project Management Docket No. 50-271

Enclosure:

Safety Evaluation cc w/encl: See next page I Revision 29 Date 1/11/02 1-5 Vermont Yankee Nuclear Power Station Revision 29 Date 1/11/02 cc: . Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 . 1-6 Mr. David R. Lewis Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. Washington, DC 20037-1 128 Ms. Christine S. Salembier, Commissioner Vermont Department of Public Service 11 2 State Street Montpelier, VT 05620-2601 Mr. Michael H. Dworkin, Chairman Public Service Board State of Vemiont 112 State Street MontpeIier, VT 05620-2701 Chairman, Board of Selectmen Town of Vernon P.O. Box 11 6 Vernon, vf 05354-01 16 Mr. Richard E. McCullough Operating Experience Coordinator Vermont Yankee Nuclear Power Station P.O. Box 157 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq. Deputy Attorney General 33 Capitol Street Concord, NH 03301 -6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Ms. Deborah B. Katz . Box 83 Shelburne Falls, MA 01370 Mr. Raymond N. McCandless -f Vermont Department of Health Division of Occupational t 08 Cherry Street Burlington, VT 05402 and Radiological Health Mr. Gautam Sen Licensing Manager Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road P.O. Box 7002 Brattleboro, VT 05302-7002 Resident Inspector Vermont Yankee Nuclear Power Station U. S. Nuclear.Regutatory Commission P.O. *!ox 176 Vernon, VT 05354 Director, Massachusetts Emergency Management Agency ATTN: James Muckerheide 400 Worcester Rd. Framingham, MA 01702-5399 Jonathan M. Block, Esq. Main Street P. 0. Box566 Putney, VT 05346-0566 7 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 & 'SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 1 .O INTRODUCTION f By letter dated September 11,2000, Vermont Yankee Nuclear Power Corporation (VYNPC/ licensee) submitted a request to amend.s Title 10 of the Code of Federal Regulations (10 CFR) Section 20.2002 (former 10 CFR 20.302) application, dated June 23, 1999, as supplemented on January 4,2000, that was approved by the US. Nuclear Regulatory Commission (NRC). This amendment will allow the addition of slightly contaminated soil resulting from on-site construction-related activities, including but not limited to, design change implementation and land maintenance, to the list of already approved materials (Le., septic waste, cooling tower silt and soiVsand from roads and walkways) for on-site disposal via land spreading on designated disposal fields. In 1 989, pursuant to 10 CFR 20.302 (current 10 CFR 20.2002), the licensee received approval from the NRC to routinely dispose of contaminated septic waste in designated on-site areas. In 1997, the NRC amended the approved on-site disposal application to also include contaminated cooling tower silt material. In 2000, the NRC amended the approved on-site disposal application to aIso include a one-time disposal of slightly contaminated sol and an annual disposal of 28.3 cubic meters of slightly contaminated soiVsand material. In this 10 CFR 20.2002 amendment application, the licensee requested that slightly contaminated soil resulting from on-site construction-related activities be disposed of on-site on an annual basis until the end of the plant's operating license in 2013. The anticipated annual volume of soil generated by on-site construction, as identified by the licensee, combined with the soiVsand generated from the annual winter spreading of sand on roads and walkways at the plant site will not exceed 28.3 cubic meters. This volume is the same volume that was approved in the January 4,2000, request. The licensee performed a comprehensive radiological evaluation which included the annual disposal of 28.3 cubic meters of soil and soiVsand materials, and shows that these materials can be managed on-site in the same manner as the septic waste and cooling tower silt (i.e., land spreading on designated fields). - .- 1 2.0 EVALUATION The licensee will dispose of the future soil material using a land spreading technique consistent with the current commitments for on-site disposal of septic waste, cooling tower silts and sandsoil material previously approved by the NRC. The licensee will continue to use the I- 7 I Revision 29 Date 1/11/02 - designated and approved areas of their property which include approximately 1.9 acres, which currently receive the septic waste, cooling tower silts and soiVsand material, and approximately 10 acres which have not been previously used for disposal. Determination of the radiological dose impact of the new material has been made based on the same dose assessment models and pathway assumptions used in the previously approved submittals. The licensee will proceduratty control and maintain records of all disposals. The foIlowing information will be recorded: 1 I The radionuclide concentrations detected in the material (measured to radiaon levels consistent with the licensee's radiological environmental monitoring program); ,..' .:. , .I .. ..: .. 2. 3. The total volume of material disposed; The total radioactivity in the disposal operation as well as the total radioactivity accumulated on each disposal plot at the time of spreading; The plot on which the material was applied; Dose calculations or maximum allowable accumulated activity determinations required to demonstrate that the dose condition values imposed (Le., imposed by the approved 10 CFR 20.2002 application dated June 23,1999) on the land spreading operation have not been exceeded. ' 4. 5. The bounding dose conditions for the on-site disposals are as follows: 1. The annual dose to the whole body or any organ of a hypothetical maximally exposed individual must be less than 1 .O mrern. 2. Annual doses to the whole body and any organ of an inadvertent intruder from the probable pathways of exposure must be less than 5 mrem. 3. Disposal operations must be at one of the approved on-site focations.

4. Total annual combined volume of soil and soiVsand materials must not exceed 28.3 cubic meters. To ensure that the addition of new material containing low levels of radioactivity will not exceed the bounding dose conditions, for each new spreading operation the licensee will calculate an estimate of the total radioactivity that includes all past disposals of septic waste, cooling tower silt, and soil/sand and soil material on the designated disposal plots. This will be compared with the bounding dose condition value or equivatent radioactivity value on a per acre basis. The licensee assessed the dose from soil and soiVsand material that may be received by the maximally exposed individual during the period of plant control over the property, and to an inadvertent intruder after plant access control ends using the same pathway modeling, assumptions, and dose calculation methods that were previously approved by the NRC for the septic waste and cooling tower silt disposals.

The dose models are based on the guidance in NRC Regulatory Guide 1 .I 09, Revision I (1 977). Revision 29 Date 1/11/02 :I ~ 1-8 I 1 3- The licensee's dose assessment is as follows: 1. Total annual doses to the whole body and critical organ of the hypothetically maximally . exposed indwidual were estimated to be 0.1 15 mrem and 0.403 rnrern respectively. .These values are less than the prescribed annual dose condition value of t .O mrem for the time period of active site control. Total annual doses to the whole body and critical organ of an inadvertent intruder from the probable pathways of exposure were estimated to be 0.757 mrem and 1.17 mrem. These values are less than the prescribed annual dose condition vahe of 5.6 mrem for the time period after active site contro1. The dose calculations are based on projecting the mdmum potential impact, of all disposals (past and future) on the approved disposal site.

2. 3.

3.0 CONCLUSION

The staff finds the licensee's proposal to dispose of the low-level radioactive soil material, pursuant to 10 CFR 20.2002, in the same manner, tocation;and within the bounding dose conditions as the materials (i.e., septic waste, cooling tower silt and soiVsand from roads and walkways) previously approved by the NRC to be acceptable. The licensee has committed to permanently incorporate this modification into their Offsite Dose Calculation Manual. Principal Contributor: A. Hayes Date: June 26, 2001 Revision 29 Date 1/11/02 I1 1-9 -::1804?5K% ;EPTERSSN-LEMD:QEUINTR-OOQNUAK3QAMSED:TQRTAMSSNK9/2;(&%(&&'FNQ4MCQEARENFSHE-MMTAK>NKTLE6ILISAMD9ME$SILE<OQEADIMGNF/TQQEMS4MUEMSNQX# DASED9CSNBEQ)#(&&)#.>@&)$& ((% <AFESX1UAKTASINMNF;EPTERSSN-LEMD:QEUINTR-OOQNUAKR3QAMSED:TQRTAMSSNK9/2;(&%(&&($>EQLNMS@AMJEE8TCKEAQ:NVEQ<SASINM!=-/8N%7/*'&)" DASED5TKX',#(&&*#8>@&*$&,&

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