IR 05000213/1997011

Insp Rept 50-213/97-11 on 971006-09 & 1103-07.No Violations Noted.Major Areas Inspected:Programs for Radioactive Liquid Control

ML20198C752
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/29/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20198C746	List: IR 05000213/1997011 ML20198C743
References
50-213-97-11, NUDOCS 9801080048
Download: ML20198C752 (19)

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U.S. NUCLEAR REGULATORY COMMISSION f

REGION l i

Docket No:

50 213 License No:

DPR 61

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i Report No:

50 213/97 11

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Licensee:

Connecticut Yankee Atomic Power Company Hartford, CT 061410270 i

Facility:

Haddam Neck Station

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Location:

Haddam, Connecticut

Dates:

October 6 9, and November 3 7,1997 Inspector:

Dr. Jason C. Jang, Senior Radiation Specialist Approved by:

John R. White, Chief

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Radiation Safety Branch Division of Reactor Safety

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Bepart Details R1 Radiological Protection and Chemistry (RP&C) Controls R 1.1 Igur of Selected Radioloalcal Envirg1 mental Monitorina Proaram (REMP) Facilities a.

Insocction Scone (84750-03)

The inspection consisted of walkdown of: (1) the meteorological monitoring station; (2) specific REMP sampling and monitoring sta.' ions along the discharge canal (i.e., sediment sampling and thermoluminescent dosimeter (TLD) stations; and (3) process water well(i.e., A and B pump stations).

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Observations and Findinas The inspector toured the meteorological monitoring tower. The meteorological monitoring tower had two levels (at 33 ft and 200 ft) at which monitoring sensors (wind speed, wind direction, and air temperature detectors) were mounted, as required by Section 3/4.3.4 of the TS. The inspector noted that the true wind speed and direction were not able to be measured at the 33 f t level sensors because of overgrown trees that perturbed windflow. The only sensor being used at the 33 f t level was a temperature sensor. The inspector noted that the licensee was able to compensate for the wind direction sensor by the backup system that had the capability to provide redundant meteorological data relative to wind speed, wind direction, and temperature. All meteorologicalinstruments were operable at the time of this inspection.

The inspector confirmed that the licensee sampled bottom sediment at the vicinity of liquid effluent discharge point and positioned a TLD at the mouth of discharge canal, as required by the Offsite i ose Calculation Manual (ODCM).

During t'ie site tour on November 5,1997, the inspector observed an area outside

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the RCA, on owner controlled property, which contained material dredged from the discharge canalin the period between 1976 and 1987. According to licensee surveys, the dredged material contained trace concentrations of radioactive material. The pile occupied an area of about 11,200 square meters. The inspector reviewed the licensee's Sursay/ Sampling Work Plan for the dredge pile. The inspector determined that the Survey / Sampling Work Plan was complete and well documented for guiding decommissioning offorts.

The requirements of 10 CFR 20.2002 describes that, in part, "the licensee may apply to the Commission for approval of proposed procedures, not otherwise authorized in the regulations in this chapter, to dispose of licensed material generated in the licensee's activities." The licensee was not able to determine if they had ever made an application to the NRC to dispose of dredging spoils onsite in the owner controlled area, and was continuing to review. From review of NRC records, it is not apparent that such application was ever received. This item is considered unresolved pending verification that such application was or was not submitted relative to this matter. (URI 50 213/97 11 01).

2 The inspector determined that the licensee did have dredging approval permits issued by the U.S. Army Corps Engineers (Permit No. 87 5024)and by the Commissioner of Environmental Protection, State of Connecticut (Permit No.109, January 15,1987).

The inspector examined well water stations A and B which had been generally Operational since the commencement of the plant operations. Wells A and B were always used to supply process water, with the exception of three months (November 1986 to January 1987), when well water stations C and D were made operational. The C and D wells were subsequently discontinued due to the very high mineral content that made the water unusable for plant process purposes.

W911 water stations A and B were operational at the time of this tour and were subject to frequent sampling in accordance with environmental monitoring program requirements.

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Conclusion Within the scope of these particular observations and findings, the inspector determined that the licensee implemented an appropriate sampling program to support the REMP relative to these specific monitoring stations and requirements.

R1.2 Imolementation of the Tritium (H 3) Effluent Control Proaram a.

Insoection Scone (84760 03)

The purpose of this review was to ascertain the radiological consequence and impact on public health and safety (and the environment), with reference to applicable regulatory requirements, relative to tritium released from, or monitored at, Haddam Neck. During this inspection, tSe inspector reviewed: (1) the potential for an unquantified tritium release pathway to the discharge canal, from ground water collected in the external containment sump (ECS)(i.e., tritium activity that may have been released but not normally monitored or controlled); and (2) impact to public health and safety and the environment due to H 3 release from the site. To investigate these issues, the inspector reviewed licensee's annual reports, dose assessment results, and the radioactive liquid offluent control program, including H 3 monitoring and analysis efforts, a.1 The Potential Unauantified H-3 Releases and H 3 Analytical Methodoloav:

To assess the potential unquantified H 3 releases and the licensee's H 3 analytical methodology, the inspector performed the following:

(1)

Reviewed the ECS water release pathway from the ECS to the discharge canal; (2)

Interviewed former Chemistry Managers; (3)

Reviewed tritium measurement results and release permits;

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(4)

Reviewed annual reports; (5)

Performed an independent projected dose calculation using the NRC PCDose

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code;and (6)

Reviewed the licensee's H 3 analytical methodology and laboratory quality control (OC) program, a.2 The Evaluation of the Public Health and Safety and the Environment:

To assess the evaluation of the public health and safety and the environment, the inspector performed the following:

(1)

Reviewed historical H 3 discharge data; (2)

Reviewed historical H 3 measurement results for the onsite well A and B; and (3)

Evaluated total body du:e due to H 3 in the onsite well A and B water.

b.

Observations and Findinag b.1 The Potential Unauantified H 3 Releases and H 3 Analvtica14ethodoloav b.1.1 Review of the ECS Water Release Pathway The inspector reviewed the ECS water release pathway. The ECS ground water was normally released to the discharge canal (a sampling location) through the storm drain system upon being pump to, and drained from, an open trench surrounding the 115KV switchyard. However, configuration of the trench may have occasionally allowed ECS water to be drained from the trench to an area outside of the radiological controlled area that was not normally sampled. To alle.vlate this problem, the licensee blocked the open trench with a dam in September 1997 near the ECS to direct the water flow to the storm drain system and discharge canal.

From that point on, ECS water was generally released only through the storm drain system. Release events involving contaminated liquid drained from the open trench are documented in Inspection Report No. 50 213/97 08.

b.1.3 Interviews with Former Chemistrv Manangtg The inspector interviewed three former Chemistry Managers (serving from 1969 to 1994) relative to H 3 measurement and dose assessment methodologies for the ECS samples, including H 3 activity in 1976, the first year in which tritium was measured in ECS water samples. Based on these discussions and record reviews, the following information was developed:

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On May 19,1976, the 'icensee discovered H 3 activity in the routine ECS water l

sample. The licensee prepared Plant Information Reports (PIR) accordingly (PIR

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Nos. 76 66 and 76138). The licensee's investigation suggested that the source of

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H 3 was likely due to leakage from any one of a number of potential sources j

(e.g., radioactive waste tank, test tanks, 'ho steam generator blowdown, or the

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radwaste test tank discharge line under the drumming rcom floor. Subsequently, the drumming room floor was core drilled in the vicinity of where the discharge line ties into the service water return line. Coro drilling Indicated severe erosion of

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discharge line which resulted in the accumulation of water in the area which was

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likely collecting in the ECS sump. The licensee repaired the discharge line. Since i

i the repair, only rninor tritium activity has been measured in the ECS, as shown in Column 5 of Tables 1 and 2.

The tritium activity at the ECS samples indicated that the leakage was likely from the test tanks due to similarity of the tritium activity. The inspector noted that the

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ECS sump was the lowest elevation in the surrounding area, therefore, any

subterrain leakage in the vicinity would be expected to be collected in the ECS.

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in accordance with the design of the liquid waste processing system, processed water 10 collected in the test tanks to be sampled and analyzed prior to release to i

the discharge canal. A grab sample is obtainert and analyzed for radioactivity

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(including H 3), to assure conformance with regulatory requirements prior to release to the discharge canal. As part of this process, a projected dose calculation is made to demonstrate that the resultant dose will not execed regulatory specifications.

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At the time that this leakage pathway was discovered in 1976, chemistry mmusgement reasoned, that since the test tank samples were always collectad and pubik,'ed for gamma and tritium activities, and projected dose calculations to ady were always performed L store discharge (as required by the TS), additional pro $cted dose calculations to account for the minor leakage of tritium to the ECS from the test tanks would constitute redundant accounting of the activity, and i

consequently was unnecessary. There were no gamma emitters detected in the ECS water samples; and dose contribution was determined to be insignificant, as shown in Column 5 of Tables 1 and 2. Accordingly, no separate accounting of ECS water was accomplished.

The 1976 projected dose to the public (whole body dose for adults) due to all radioactive liquid releases from Haddam Neck was 0.086 mrem, including tritium.

This is a fraction of the TS limit (3 mrem / year). The 1975 and 1977 projected doses to the public (whole body doses for adults) were 0.81 mrem and 0.56 mrem, respectively.

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b.1.4 Review of Tritium Measurement Retplts and Release Permits

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in December 1996, the licensee discontinued any liquid discharges from tanks to the environr,ent. Only ECS water was pumped to the discharge canol. The analytical results of the ECS water Indicated only minor tritium activity. Since that

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time, the licensee has accounted fer tritium released throt gh this ECS pathway by

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considering it as a batch release in accordance with existeg procedures and regulatory requirements.

in this manner, specific sampling and analysis is performed and documented (including projected dose to the public), before ECS water la pumped and released to the discharge canal. Tho inspector noted that gamma emitters were not detected in any ECS samples. The licensee has updated the ODCM and associated procedures to reflect this practice.

in summary, since December 1996, the ECS water was the only radioactive liquid effluent source. Measured tritium activities in the ECS water (i.e.,6.86E 6 to 3.15E-4 Cl/ml) were lower than the regulatory value found in 10 CFR 20, Appendix B (i.e.,1.0E 3 pCl/ml). Dose assessment information is contained in Table 2 of this inspection report.

b.1.5 Hpview of Annual Reootta The inspector reviewed the se!ective licensee assessment of annual dose to the public as a result of tritium releases by examining the 1973 to 1996 samlannual/ annual of fluent and environmental reports that the licensee is required to make in accordance with regulatory specifications. The inspector determined that the dose contribution by H 3 was minimal and well within regulatory requirementr.,

as shown in Table 2 of this inspection report.

b.1.6 NRC PCDose Code The inspector reviewed the 1997 ECS weter discharge permits including associated projected dose calculation results. The inspector independently performed a projected dose calc"lation using the NRC PCDOSE code. The total amount of H 3 release from Januray 'i997 to September 1997 was 17,4 curies. The average dilution flow rate y as about 7,000 gallons / minute during this period. Projected dose to the public (whole body dose for adults) using the NRC PCDOSE code was 3.76E 4 mrem, a bmall fraction of TS limits (3 mrem / year).

b.1.7 }i.;1Analvtical Methodoloav and QC Prooram

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The inspector reviewed the licensee's analytical methodology for H 3, The licensee used two H 3 analytical approaches: (1) filtering the ECS water sample using a mixed resin bed to remove any complex lons or naturally occurring radioactive

. elements, such as radium 226, radium 228, and potassium 40; or (2) distilling the ECS water sample when the water sample contained a high turbidity (brackish

' water). The inspector noted that the licensee made efforts to effect the optimum assessment of tritium in the ECS water sample, and determined that the licensee's methodolog!es were acceptable,

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7 The OC program for analyses of H 3 samples was conducted by the chemistry

laboratory. The H 3 OC program consisted of measurements of blind duplicate, spike samples, blank samples, and control charts. The inspector reviewed selected

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data (September and October 1997) and determined that the licensee's H 3 QC program was very wellimplemented in accordance with associated procedures.

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b.2 The Evaluation of the Public Health and Safety and the Environment

b.2.1 Review of EPA 520/3 74-007

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The inspector reviewed * EPA 520/3 74 007, Radiological Surveillance Study at the d

Haddam Neck PWR Nuclear Power Station, Office of Radiation Programs, USEPA, December 1974." This document characterized and described: (1) radionuclides in

. water on site (plant water); (2) airborne radioactive discharges; (3) radionuclides in

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liquid wastes; (4) radionuclides in the aquatic environment; (5) radionuclides in

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environmental air; (6) radionuclides and radiation in the terrestrial environment; and (7) summary and conclusions. The inspector used this document to establish a radiological point of reference, b.2.2 Historical H 3 Discharne Drsta The NRC published the Radiological Effluent Technical Specifications (RETS)in 1981 to provide numerical guides for design objectives and limiting conditions to meet the criterion "As Low As is Heasonably Achievable (ALARA)in light water-cooled nuclear power reactor effluents" (10 CFR 50, Appendix I). The RETS specifies the annual dose limit, such as 3 mrem / year for radioactive liquid releases.

The licensee adopted the RETS in 1986.

Prior to the RETS, the licensee was required to comply with 10 CFR 20, Appendix B, Table ll effluent concentrations. For example, the effluent concentration limit for H 3 was 3E 3 Ci/cc. The inspector compared historical H 3 discharge concentration against the 10 CFR 20, Appendix B, Table il effluent l

concentrations from the commencement of the plant operations through 1980.

From 1981 (when NRC published the new RETS) to present, the inspector compared the H 3 releases to the RETS annual dose limitation of 3 mrem / year.

The comparison results uf H 3 activities are listed in Table 1 of this report. The licensee always met the H 3 concentration limits for the effluent requirement as

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listed in 10 CFR 20, Appendix B,- Column 2. The licensee did not measure any

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positive H 3 activity from the commencement of the plant operations in 1967 to 19751n the ECS water, as shown in Table 1 of this inspection report. In 1976, the licenseo started measuring H 3 activity in routine ECS water samples, as described in Section b.1.3 of this inspection report. The licensee estimated, conservatively, the annual H 3 release through the ECS using the highest H 3 measurement result and maximum water flow rate for the ECS (listed in Column 4 of Table 1 of this report). The highest percentage of potentially unquantified H 3 release was 1.87%

of total quantified H 3 released in 1977.

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The comparison results of projected doses due to H 3 are listed in Table 2 of this inspection report. The licensee's projected doses, as listed in Column 1 of Table 2 this inspection report, were well below the limit. The licensee conservatively estimated the annual H 3 release through the ECS usirg the highest H 3 measurement result and maximum water flow rate for the ECS (listed in Column 3 of Table 2). The inspector used the PCDose code to calculate the projected dose due to potentially unquantified tritium and listed the results in Column 4. The highest percentage dose contribution due to potentially unquantified tritium release-was 1.72% in 1983. The NRC requirements permitted unquantified release to a maximum 10% of total dose due to radioactive liquid release (Regulatory I'osition of Regulatory Guide 1.109). Accordingly, the licensee met the NRC requirements relative to this monitoring and analysis of tritium release to the environment, b.2.3 Historical H 3 Measurement Results for the Onsite Well Thc licensee monitored H 3 activities for onsite wells, which are located along the

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discharge canal outside of the security fence in the peninsula. The licensee had used onsite well water (known as Welh, A or B) for specific domestic usage, such as shower and toilet. Historical H 3 measurement results of the onsite well water are listed in Table 3 and illustrated in Figu'e 1 in this report. As shown, the highest H 3 measurement results for the onsite well water were during the period of May-July 1975, which was during a refueling outage (May 17 June 30,1975). Other elevated H-3 measurements (e.g., January 1978 and January 1982, etc.) were also during the refueling outages. The empirical evidence suggests that, due to the shallowness of the wells A or B (about 5-10 feet depth), and the minimum service water discharge during the outages. H-3 activities in wells A or B rnay be elevated during refueling outages.

The inspector requested to the licensee to take grab samples along the discharge canal and from the well water system (Wells A&B and in-plant well water) on November 4,1997. The licensee took grab samples and analyzed them on November 5,1997. The sampling locations and H-3 analytical results are shown in

. Figure 2 in this report. All analytical results were less than 215 pCill, which was about background for tritium in the environment. This observation appears to confirm that the source of H-3 in well water was most likely from the discharge canal due to shallowness of wells; and minimum service water flow (which results -

in minimum dilution) during the refueling outages, in July 1976, the National Interim Primary Drinking Water Regulations were publishs d by the EPA. An average annual concentration resulting in total body dose of 4 miem/ year was established as 20,000 pCi/l of H-3 based on standard annual drinking water consumption. The EPA drinking water regulations were established for public water suppliers (those that serve more than 25 people) and considered all age groups, such as infant, child, teen, and adult.

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exceeding 20,000 pCl/l of H 3 of the onsite well water in 1975, as listed in Table 3, did not constitute a violation of any NRC reqitirement.

b.2.4-Evaluation of Total Body Dose for Onsite Well A/B Water Tritium As previously discussed, the licensee used onsite well water (known as Wells A or

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B) for specific domestic usage, such as shower w. toilet. Thocgh it was not usually used for drinking water due to mineral we ', taste, and some biological fouling of the well, it is not evident that CY ever utablisht ? a specific prohibition against drinking the water, though bottled water was available onsite for drinking

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purposes,

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During a review of the historical H 3 act vity data for the onsite well water, the inspector noted that 1975 had the highest H 3 measurement results since the commencement of plant operations. Therefore, the inspector calculated a projected dose, assuming that thli, water was consumed by an individual at a standard rate.

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The inspector used the basic equation listed in Reguletory Guide 1.109.

Dose = (Activity) (Drinking Water Consumption Rate) (Dose Factor)

mrem = (pCl/ liter) (liter / month) (mrem /pCi)

where: Drinking Water Consumption Rate for adult = 730 liters / year

= 60.8 liter / month Dose Factor = 1.05E 7 mrem /pCi

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The maximum organ doso rate conversion factors (dose factor) for ingestion of drinking water was pubehbed by the NRC in January 1990, NUREG/CR 5512, Residual Radioactive Contamination From Decommissioning (Draft). The dose factor

. of tritium was specified as 6.7E-8 mrem /pCl, a lower value than listed in Regulatory Guide 1.109. Notwithstanding, the inspector urM the H 3 dose factor value listed in Regulatory Guide 1.109 for this dose assessment (1.05E-7 mrem /pCi).

The dose assessment of the monthly and the annual doses are listed in Table 4.

The annual total body dose would have been 0.82 mrem in 1975, for any person drinking only the onsite well water for the entire year. This assessment indicates that there would be insignificant dose impact to licensee employees or the public that could have been exposed to tritium in drinking water as a result of plant operations.

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Conclusion Based on the above reviews and interviews, the inspector determined the following conclusions:

Tritium released thmagh the ECS water in May 1976 was monitored and reported in the 1976 semiannual effluent reports;

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• Analytical methodology, including the OC program, for the ECS tritium was good;

Establishing the ECS water discharge permit to control rete 1es, not only for H-3 but also for gamma emitters, was good;

Monitoring and analysis records support that the licensee did not exceed any regulatory limit relative to liquid effluent release of tritium or violate H-3 release limits to the discharge canal;

The source of wc!! water H-3 appeared to be from the discharge canal;

Tritium activities of onsite well water system and the discharge canal were less than 215 pCi/l, which were background level, on November 5,1997;

The ECS H-3 discharges did not impact the public health and safety and the environment since the commencement of the plant operations; and

The specific use of the onsite well water did not have any significant dose consequence to the licensee employees.

R8 Previously Identified item (Closed) URI 50-213/9_7-08-04 During the previous inspection conducted during August 1. - September 19,1997, one unresolved item (URI 50-213/97-08-04)was identified by an NRC inspector.

The content of the URI was, in part, " reporting of releaces of H 3 from ground water sources to the NRC was an unresolved item pending NRC review of the licensee's bases for not " permitting"ine releases until December 1996. Based on the above reviews, the inspector stated that the URI 50-213/97-08-04was closed since no violation of NRC regulations was apparent (See Section b.2.2 of this inspection report for detail).

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' PARTIAL LIST OF PERSONS CONTACTED

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. Licensee a

L'#G. Bouchard, Services Director I

• 1. J. Bourwsa, QA Supervisor

'S._Carnesl, System Engineer

1. W. Eakin,' Site Characterization

1. J. Haley, Licensing

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'J. Haseltine, Engineering Director

• #S. Herd, Chemistry Manager s

'B. van Nieuwenhuise, Chemistry Supr rvisor e

• G. van Noordenner, Licensing Manager :

'#R. Mellor, Director Site Operation 8. Decommissioning

1. R. Shippe,' Site Characterization ( *J. Tarzia, HP/ Chemistry Technical Support

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1. A. Yates, Chemistry NBC

'W. Raymond, Sr. Resident inspector

• Denotes those present at the exit meeting on October 13,1997.

1. Denotes those present at the exit meeting on November 7,1997. The inspectors also interviewed other licensee personnel.

ITEMS OPENED, CLOSED, AND DISCUSSED Opened URI 50-213/97-11-01,NRC approval for Dischtrge Canal Dredging.

Closed URI 50-213/97 08-04, Review of potential unquantified H 3 releases.

Discussed None x

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11 Table 1, Amount of Tritium Release since Haddam Neck Operation Before Radiological Effluent TS Requirement Issued

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(2)

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Effluent Average Total H 3 Potentially

% of Remarks Release Released Release Unquant'fied Potentially e

Limit, Activity, H-3 Release, Unquantified Ci/ml pCi/ml (curies)

ECS (curies)

H 3 relet.sss (7)

1967 3.0E 3 1.16E-6 220 MDA (6)

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1968 3.0E-3 9.13E-6 1,735 MDA

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1969 3.0E-3 2.72E 5 5,163 MDA

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1970 3.OE 3 1.10E-5 7,377 MDA

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1971 3.0E-3 8.20E-6 5,832 MDA

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1972 3.0E 3 7 70E-6 5,890 MDA

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1973 3.0E 3 2,00E 5 3,900 MDA

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1974 3.0E-3 3.20E-6 2,241 MDA

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1975 3.0E 3 8.51 E-6 5,670 MDA

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19*/5 3.0E 3 7.96E 6 4,854 1,931 (8)

39.8 % (8)

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19',7 3.OE-3 8.97E-6 6,666 124.4 1.87 %

1978 3.0E-3 5.12E-6 3,944 38.8 0.98%

1979 3.0E-3 5.70E-6 3,546 7.4 0.21 %

1980-3.0E 3 1.01 E-6 3,291 29.9 0.91 %

(1) H 3 Effluent Concentration Limit,10 CFR 20, Appendix B, Table il

.(2) Annual Average Released Activity (3) Total H-3 Release (4) Potentially Unquantified H-3 Release through the ECS (5) [ Column (4)/ Column (3)) x 100 (6) MDA = Usinimum Detectable Activity

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(7) Operation started in October,1967 (8) Reported through routine report mechanism 4,,

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Table 2, Amount of Tritium Release since Haddam Neck Operation Atlet Radiological Effluent TS Requirement Year (1)

(2)

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TB Dose, Monitored Potentially TB Dose due

% Dose due due to H-3 Unquantified to to all Liquid Release H 3 Release, Potentially Potentially -

Pathway through ECS Unquantified Unquantified (mrem)

(Curies)

(Curies)

H3 H 3 Release (mrem)

1981 1.0 3,291 214 4.62E-3 0.758 %

(6)

1982 0.61 5,290 15.7 3.39 E-4 0.056 %

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1983 0.086 4,050 68.6 1.48E 3 1.72 %

1984 1.30 3,600 6.6 1.43E 4 0.011 %

1985 0.13 5,760 12.8 2.77E-4 0.213 %

1986 0.594 2,580 8.37 1.81 E-4 0.030 %

(7)

1987 0.93 3,170 4.15 8.95E-5 0.0096 %

1988 0.292 1,180 2.37 5.12E 5 0.0153 %

1989 0.0922 4,810 34.1 7.37E-4 0.80 %

1990 0.3 989 5.89 1.27 E-4 0.0424 %

1991 0.827 4,630 25.15 5.43E-4 0.0657 %

1992 0.401 863 42.12 9.10E-4 0.227 %

1993 0.2038 4,000 1.58 3.41 E-5 0.0168 %

1994 0.5627 1,420 3.55 7.67E-5 0.0136 %

1995 0.1756 699 3.60 7.78 E-5 0.0443 %

1996 0.066 540 3.03 6.55 E-5 0.0992 %

1997 3.76E-4 17.4 None

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(1) Total Body Dose (Adult) due to Radioactive Liquid Release Pathways (2) Total Monitored Release, published in Semiannual / Annual Reports (3) Potentially Unquantified H 3 Release through the ECS (4) Total Body Dose (Adult) due to Potentially Unquantified H-3 Release (5) % Dose due to Potentially Unquantified H 3, (Column (4)/ Column (1)] x 100 (6) Effective the NRC RETS (7) Effective the Licensee's RETS (8) From January 1997 to September 1997

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Table 3, Historical Tritium Data for the Onsite Well Date H 3, p Ci/l Date H 3, pCi/l Date H 3, pCill

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Jan.70 4,277 Mar. 75 4,840 Jan.78 12,000 Feb. 70 4,180 Apr. 75 4,500 Feb.78 11,600 Mar. 70 4,018 May 75 27,300 Mar.78 11,400 5,720 Apr. 70 3,823 Jun.75 28,000 Apr. 78 i

Jun.70 4,698 Jul. 75 20,300 May 78 4,750 Jul 70 6,674 Aug.75 7,890 Jun.78 5,680

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Aug.70 3,920 Sep.75 8,180 Jul. 78 5,960 Sep.70 5,702 Oct. 75 10,100 Aug 78 4,510

,

Oct. 70 6,318 Nov.75 6,300 Sep.78 4,780 Dec.70 6,836 Dec.75 2,500 Oct. 76'

4,060 Jan 71 6,156 Jan.76 5,380 Nov.78 3,650 Apr. 71 6,739 Feb.76 3,970 Dec.78 2,690 Oct. 71 5,573 Mar. 76 4,090 Jan 79 3,770 Jan.72 5,249 Apr. 76 5,620 Feb.79 4,170 Jun.72 5,087 May 76 5,210 Mar. 79 5,910 Sep.72 3,953 Jun.76 6,670 Apr. 79 5,270 Nov.72 4,277 Jul. 76 6,450 May 79 7,300 Mar. 73 3,065 Aug.76 8,630 Jun 79 7,060-Aug.73 1,353 Sep.76 5,960 Jul 79 3,710 Dec.73 6,091 Oct. 76 4,770 Aug.79 3,130 Jan.74 1,690 Nov.76 6,540 Sep.79 3,170 Feb.74 4,600 Dec.76 4,700 Oct. 79 4,570 Mar. 74 7,900 Jan.77 2,190 Nov.79 6,510 Apr. 74 8,100 Feb.77 3,100 Dec.79 5,690 May ?4 9,300 Mar. 77 3,150 Jan.80 5,470 Jun.74 6,600 Apr. 77 2,618 Feb.80 5,270 Jul. 74 6,816 May 77 3,290 Mar. 80 3,990 Aug.74 4,330 Jun.77.

3,090 Apr. 80 5,780 Sep.74 4,340 Jul. 77 2,570 May 80 7,330 Oct. 74 3,680 Aug-77 6,590 Jun.80 4,080 Nov.74 3,400 Sep.77 13,900 Jul. 80 4,800 Dec.74 3,410 Oct. 77 13,100 Aug.80 4,960 Jan.' 75 3,290 Nov.77 15,100 Sep.80 5,870 Feb.75 4,620 Dec.77 15,i OO Oct. 80 1,770

.

..

.

-=

.

-.

.

.

-

....

i

.

Table 3,- Historical Tritium Data for the Onsite Well (Cont'd)

Date~

H 3, pCi/l Date H 3, pCi/l-Date H o,pCi/l Nov.80-2,550 Jan.83 9,9:

Mar. 85 3,600 e

Dec.80 3,550 Feb.83 6,80v Apr. 85 -

4,300 Jan.81 1,920 Mar. 83 6,090 May 85 10,000

'

Feb.81 2,480 Apr. 83 7,040 Jun.85 5,300 Mar. 81 2,010 May 83 6,970 Jul. 85 9,100 Apr. 81-2,790 Jun.83-4,830 Aug.85 4,000 May 81

.3,000 Jul. 83 3,000

.Sep.85 6,700 Jun.81 2,930 Aug.83 2,030 Oct. 85 7,380 Jul. 81 8,570 Sep.83 4,250 Nov.85 7,000 A79 81 8,505 Oct. 83 4,080 Dec.85 8,300 Sep.81 14,700 Nov.83 3,590 Jan.86 7,100

- Oct. 81 5,960 Dec.83 5,880 Feb.86 6,200

'

Nov.81 14,400 Jan.84 7,000 Mar 86 7,100 Dec.81 12,700 Feb. 84 7,-450 Apr. 86 -

4,900 Jan.82 7,910 Mar. 84

'6,220 May 86 3,400 Feb.82 5,160 Apr. 84 5,130 Jun.86 3,200 Mar. 82 8,860 May 84 4,680 Jul. 86 3,000 Apr. 82 4,090 Jun.84 8,830 Aug.86 1,800 May = 82 5,500 Jul. 84 6,160 Sep.86 2,700

'

Jun 82 3,420 Aug.84 4,700 Oct. 86 2,000 Jul. 82 5,250 Sep.84 5,250 Nov.86

• Aug.82 8,670 Oct. 84 5,150 Dec.86

< 70 *

_

Sep.82 4,150 Nov.84 9,900 Jan.87

< 84 *

Oct. 82 '

8,270 Dec.84 5,700 Feb. 87 1,800 Nov.82 7,120 Jan.85 5,500 Mar. 87 2,700 Dec.82 8,250 Feb. 85 3,000 Apr. 87 2,800

,

Wells C and D were very deep wolls and L. sed for three months period for

the domestic usage. The use of water from these wells were discontinued due to very high mineral contents, such as iron.

J.

J

.

.

,-.

'

.

'

%

. Table 3,. Historical Tritium Data for the Onsite Well (Cont'd)

Date H 3, pCi/l-Date H-3, pCi/l Date H-3, pCi/l May 87 4,400 Jul. 89 7,400 Mar. 95 2,070 Jun.87 2,300 Augi89 7,300 Jun.95 741 Jul. 87 7,000 Sep.89 2,900 Sep.95 720 Aug.87 7,600 Oct. 89 4,200 Dec.95 286 Sep.87 8,700 Nov.89 3,500 Mar. 96

< 502 Oct. 87 7,000 Dec.89 2,300 Jun.96

< 462 Nov.87 3,310 Mar. 90 3,150 Sep.96 1,523 Dec.87 2,800 Jun.90 1,910 Dec.96 864 Jan.88 3,900 Sep.90 919 Feb. 88 4,000 Dec.90 445 Mar. 88 4,400 Mar. 91 1,630 Apr. 88 2,400 Jun.91 2,980 May 88 2,000 Sep.91 4,470 Jun.88 3,800 Dec.91 4,560 Jul. 88 2,300 Mar. 92 2,570 Aug.88 1,300 Jun.92 2,200 Sep.88 2,000 Sep.92

< 130 Oct. 88 1,350 Dec.92 908 Nov.88 1,200 Mar. 93 2,840 Dec.88 1,200 Jun.93 5,430 Jan.89 1,100 Sep.93 889 Feb. 89 3,000 Dec.93 893 Mar. 89 2.100 Mar. 94 944 Apr. 89 3,300

,lun.94 1,341 May 89 7,200 Sep.94 3,291 Jun.89 6,000 Dec.94 1,544

,

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A: River Intake B : Well Water (In-Plant)

C: Discharge Point (Weir)

D, E, G, H : Along the Discharge Canal F : On-Site Well

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1. ~

Figure 2. Tritium Measurement Results along the Discharge Canal

._%

( All Measurement Results were less than 215 pCi/1)

-

.

.

Table 4, Adult Total Body Dose due to Onsite Well Water Drinking Month,1975 Well Water H 3 Activity Adult Total Body Dose (pCl/l)

(mrem / month)

January 3,290 2.10E-2 February 4,620 2.95E 2 March 4,840 3.09E-2 April 4,500 2.87 E-2 May 27,300 1.74 E-1 June 28,000 1.79E-1

_-

July 20,300 1.30E-1 August 7,890 5.04E 2 September 8,180 5.22E-2 October 10,100 6.45E 2 November 6,300 4.02E-2 December 2,500 1.06E-2 Annual Total Body Dose 8.16E-1 mrem /1975

,

.