LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 11.6, Offsite Radiological Monitoring Program

From kanterella
(Redirected from ML17046A520)
Jump to navigation Jump to search
Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 11.6, Offsite Radiological Monitoring Program
ML17046A520
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A520 (2)


Text

11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM Since 1968 an Offsite Radiological Environmental Monitoring Program (REMP) has been conducted on the Artificial Island Site. Starting in December 1972, more extensive radiological monitoring programs were initiated with the purpose of identifying and quantifying the concentration of various radioactive elements in the different environmental media surrounding the Salem Generating Stations. 11.6.1 Program Objective The objectives of the operational radiological environmental program are: 1. To fulfill the obligations of the radiological Environmental Monitoring sections of the Technical Specifications for the Salem Generating Station 2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways 3. To determine if the station has caused an increase in the radioactive inventory of long lived radionuclides 4. To detect any change in ambient gamma radiation levels 5. To verify that the Salem Generating Station operations have no detrimental effects on the health and safety of the public or on the environment The basis for the selection of sample locations was determined from site meteorological, hydrological, and geographical constraints enclosed by local demography and land use. Sample locations chosen are consistent with the U.S. Nuclear Regulatory Commission Branch Technical Position on the REMP. Sample locations were divided into two basic classes, indicator and control stations. Indicator stations were situated in areas most likely to be affected by a station release. All control stations were presumed to be located at a distance from the station to be unaffected by normal and accident plant operation. In this manner, fluctuations in the level of radionuclides and direct radiation at an indicator station could be compared to those, if any, at a control location to determine if the station was the cause of the fluctuations. 11.6-1 SGS-UFSAR Revision 16 January 31, 1998 11.6.2 Preoperational and Operational Programs The operational REMP for the Artificial Island Site was initiated in December 1976 after Unit 1 achieved criticality. The current operational program is described in the Offsite Dose Calculation Manual (ODCM). Table 11.6-2 provides the results obtained during the preoperational phase of the program. 11.6.3 Expected Pathways The scope of the REKP is to determine whether any significant increases have occurred in the concentration of radioactive materials in the critical pathways as well as to determine if there is an increase in the radioactive inventory of long-lived radionuclei. During the months when cows are in pasture, the critical pathway has been determined to be the air, grass, milk, to man pathway. During those months when cows are not on pasture the air, broadleaf vegetation, to man pathways predominates. The selection of sample type was based upon these established critical pathways of the transfer of radionuclei, from the environment to man as well as experience of the preoperational phase of the program. 11.6.4 Physical Characteristics of Samples The physical characteristics of the samples are summarized in the Offsite Dose Calculation Manual (ODCM). The sensitivity of the analytical procedures used are consistent with the Branch Technical Position on the procedures for Environmental surveillance programs and are provided in the Radiological Monitoring sections of the Technical Specifications. The sensitivity of the analytical measurements was selected to verify that the measurable concentrations of radioactive materials are not higher than expected based on effluent monitoring and modeling. The sensitivity requirements listed in the Radiological Monitoring sections of the Technical Specifications are sufficiently low to discern dose commitments which are a fraction of lOCFRSO, Appendix I for there predicted critical pathways. It should be noted that deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or the malfunction of automatic sampling equipnent. All deviations from the sampling schedule are documented in the annual report. Descriptions of the analytical methods utilized are provided in the Annual Radiological Reports. 11.6-2 SGS-UFSAR Revision 16 January 31, 1998