ML17108A344
| ML17108A344 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/30/2017 |
| From: | Tallman D Sacramento Municipal Utility District (SMUD) |
| To: | Cruz Z Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| DPG 17-059 | |
| Download: ML17108A344 (26) | |
Text
DPG 17-059 March 30, 2017 U.S. Nuclear Regulatory Commiss.ion.
Attention: Document Control Desk*
Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear. Generating Station License No. DPR-54 RECORDS REQUIRED TO BE FORWARDED TO THE NRC PRIOR TO RANCHO SECO 10 CFR PART 50 LICENSE TERMINATION Attention: Zahira Cruz This letter documents the manner in1which the Sacramento Municipal Utility District (SMUD) has met the NRC requ.iremer1.ts fo.dorwarding certain records to the NRC prior to terminating the Rancho Seco 10 CFRPart 50*1icense. The Rancho Seco 10 CFR Part 50 license contains conditions*that*allowxeceipt; possession, and use of byproduct, source, and special nuclear mater.iaHn accordance with 10 CFR Parts 30, 40, and 70 requirements,* respectively. SMUO;has reviewed the (equirements in .10 CFR Parts 30, 40 and 70 and has identified several regul.atio:ns that require forwarding specified records to the NRC prior to license termination. The applicable regulatory requirements for records forwarding are provided in the table below; Regulations RegulatOrL* Recorc!.Forwarding Reguirements 10 CFR30.51(d) Prior to license termination; *each Ucensee authorized to possess.
radioactive material with a*half.,life.greater than.120 days, in.an unsealed form, shall forward the following records to the appropriate NRG Regional Office:
(1) Records of disposal oflicensed material made under*
§§20.2002 (including burials authorized before January 28;.1981), 20.2003,20.2004, 20.2005; and*.
(2) Records required by 20.2103(b)(4).
10 CFR 30.51(f) Prior-to license termination, each licensee shall forward th~ records.
required by 30.35(g) to. the appropriate NRC Regional Office.
Rancho Seco Nuclear Generating Station I 14440 Twin Cities Road I Herald, CA 95638-9799 I 916.452.3211 I smud.org ~
Printedon Recycled Paper
Zahira Cruz DPG 17-059 10 CFR 40.61 (d) Prior tO.'license termination, each licensee authorized to possess source material, in an unsealed form, shall forward the following records to the appropriate NRC Regional Office:
i!' ,-- .'-\
(1) Records of disposal of Hcensed material made under 20.2002 (including burials authorized before January 28, 1981), 20.2003, 20.2004, 20.2005; and (2) Records required by 20.2103(b)(4).
10 CFR 40.61 (f) Prior to license termination, each licensee shall forward the records required by 40.36(f) to the appropriate NRC Regional Office.
10 CFR 70.51 (a) Before license termination, licensees shall forward the following records to the appropriate NRC Regional Office:
(1) Records of disposal of licensed material made under 20.2002 (including burials authorized before January 28, 1981 }, 20.2003, 20.2004, 20.2005; (2) Records required by 20.2103(b)(4); and (3) Records required by 70.25(g).
10 CFR 30.51(d)(1), 10 CFR 40.61(dlf1), and 10 CFR 70.51(a)(1)
The record forwarding requirements of 10 CFR 30.51(d)(1), 10 CFR 40.61(d)(1), and 10 CFR 70.51(a)(1) are identical and are addressed together. Specifically, these regulations require a licensee to forward to the appropriate NRC Regional Office, prior to license termination, those records of disposal of licensed material made under 10 CFR 20.2002, 20.2003, 20.2004, and 20.2005. These 10 CFR Part 20 regulations address, in respective order:
- 1. Applications made to NRC for licensed material disposal in a manner not covered by regulations
- 2. Disposal of licensed material by release into sanitary sewerage
- 3. Treatment or disposal of licensed material by incineration
- 4. Disposal of specific wastes as if they were not radioactive.
Rancho Seco has not disposed of any licensed material under 10 CFR 20.2002, 20.2003, 20.2004, or 20.2005. Hence, records of such disposals do not exist because
Zahira Cruz DPG 17-059 these types of disposals Were never made at the H~ncho Seco facility. SMUD considers the record forwarding requirements in 10 CFR 30.51(d)(1), 10 CFR 40.61(d)(1), and 10 CFR 70.51(a)(1) to be met in support of Rancho Seco license termination.
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The record forwarding requirements of 10 CFR 30.51(d)(2), 10 CFR 40.61(d)(2), and 10 CFR 70.51(a)(2) are identical and are addressed together. Specifically, these regulations require a licensee to forward to the appropriate NRC Regional Office, prior to license termination, those records required by 10 CFR 20.2103(b)(4). This regulation addresses records of the results of measurements and calculations used to evaluate the release of radioactive effluents to the environment.
As required by 10 CFR 50.36a(a)(2), the Rancho Seco Technical Specifications, and the Rancho Seco Quality Manual (RSQM), Rancho Seco has submitted its Annual Radioactive Effluent Release Report (ARERR) to the NRC throughout the duration of the Rancho Seco operating license. The ARERR provides a summary of gaseous and liquid radioactive effluents released of from Rancho Seco to the environment during the period of January 1 through December 31 for a given calendar year. The ARERR also provides the results of measurements and calculations used to evaluate the radiation dose for a hypothetical individual at or beyond the applicable site boundary.
The last ARERR submitted to the NRC, for calendar year 2016, was SMUD letter DPG 17-045, dated to the NRC on March 14, 2017. Attachment 1 provides the ARERR for 2017, which includes one radioactive waste shipment. There were no gaseous or liquid effluent releases made in 2017. With the prior submittal of the records required by 10 CFR 20.2103(b)(4) as described above, SMUD's submittal of the 2016 and YTD 2017 reports will satisfy the requirements of 10 CFR 30.51(d)(2), 10 CFR 40.61(d)(2), and 10 CFR 70.51(a)(2).
10 CFR 30.51(f), 10 CFR 40.61(f), and 10 CFR 70.51Ca)(3)
The record forwarding requirements of 10 CFR 30.51 (f), 10 CFR 40.61 (f), and 10 CFR 70.51 (a)(3) are similar and are addressed together. Specifically, these regulations require a licensee to forward to the appropriate NRC Regional Office, prior to license termination, those records of information important to facility decommissioning as required by Paragraphs (1), (2), (3), and (4) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g), respectively. The record forwarding requirements of 10 CFR 30.51(f),
10 CFR 40.61(f), and 10 CFR 70.51(a)(3) are satisfied as described below.
Paragraph (1) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g)
Paragraph (1) of 10 CFR 30.35(g), 10 CFR 40.36{f), and 10 CFR 70.25(g) addresses records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site.
Zahira Cruz DPG 17-059 Rancho Seco has provided this information in various previous submittals. Beginning in July 2001, SMUD began conducting a Historical Site Assessment (HSA) of the Rancho Seco owner controlled area. T,he HSA was conducte,d. in accordance with the guidance in NUREG-1575 "Multi-Agen'cy Radiation Survey arid *site Investigation Manual (MARSSIM)" and identified known and potential sources of radioactive material and radioactively contaminated areas within the Rancho Seco owner controlled area.
~** ~!
HSA, Section 6.9 "Incident Descriptions" discusses previous radiological spills, chemical spills, loss of radioactive material control (including incidents with the potential for spreading radioactive contamination), and system cross-contamination. Results from the HSA were incorporated into the Rancho Seco License Termination Plan (LTP),
which was submitted to the NRC for approval and is included as an addendum to the Rancho Seco Defueled Safety Analysis Report (DSAR). The Radioactive Material Storage and Decommissioning Safety Analysis Report (RADSAR) replaced the Defueled Safety Analysis Report (DSAR) through Amendment No. 7 as the primary licensing basis document applicable to activities at the Rancho Seco 10 CFR Part 50 licensed facility. Periodic updates to the LTP have been submitted to the NRC, in accordance with 10 CFR 50.71(e).
Previous hydrogeological reports have indicated that the permeability of the site soils result in infiltration rates that preclude any radiological impact on aquifers in the vicinity of the Rancho Seco site. The results from the hydrogeological investigations were also included in the LTP, which was previously submitted to the NRC.
Paragraph (2) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g)
Paragraph (2) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g) requires records to include as-built drawings and modifications of structures and equipment in restricted areas where radioactive materials are used and/or stored and of locations of possible inaccessible contamination such as buried pipes that could be subject fo radioactive contamination. Paragraph 2 also allows that if drawings are not available, licensees must substitute appropriate records of available information concerning these areas and locations.
Rancho Seco has previously provided this information to the NRC as part of the Final, Status Survey (FSS) Reports. The FSS Reports for the first phase of decommissioning were submitted to the NRC in 2008 and early 2009. The FSS Report for the final phase of decommissioning was submitted to the NRC in SMUD letter DPG 17-038, dated February 28, 2017.
The FSS Reports include isometric drawings and/or other engineering drawings that depict structures, systems, and embedded piping within the Rancho Seco lndustrial 1 Area that have undergone final status surveys, in accordance with NRG-approved final 1
The Rancho Seco Defueled Safety Analysis Report and Radioactive Material Storage and Decommissioning Safety Analysis Report each use the term "Industrial Area," which meets the definition of "restricted area" in 10 CFR 20.1003.
Zahira Cruz DPG 17-059 survey methodology. These reports and the associated drawings indicate the location, type, and number of survey measurements taken within the restricted area to identify any remaining residual radio,,~ctivity and to verify thatthis radioactivity, including inaccessible contamination within embedded piping, is well below regulatory limits allowing release of the Rancho Seco site for unrestricted use. Based on the above, it is concluded that the FSS Report drawings satisfy.the intent of Paragraph (2) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g).
Paragraph (3) of 10 CFR 30.35(g), 10 CFR 40.36(f}, and 10 CFR 70.25(g)
Paragraph (3) of 10 CFR 30.35(g), 10 CFR 40.36(f), and 10 CFR 70.25(g) requires, except for specified areas, records to include a list contained in a single document and updated every two years, of the following:
(i) all areas designated and formerly designated as restricted areas as defined under 10 CFR 20.1003 (ii) All areas outside of restricted areas that require documentation under 10 CFR 30.35(g)(1), 40.36(f)(1), or 70.25(g)(1) (regarding spills)
(iii) All areas outside of restricted areas where current and previous wastes have been buried as documented under 10 CFR 20.2108 (iv) All areas outside of restricted areas that contain material such that, if the license expired, the licensee would be required to either decontaminate the area to meet the criteria for decommissioning in 10 CFR 20, Subpart E, or apply for approval for disposal under 10 CFR 20.2002.
Consistent with Item (3)(i), the Rancho Seco Industrial Area is described in the Radioactive Material Storage and Decommissioning Safety Analysis Report and License Termination Plan. Updates to these documents are submitted to the NRC at least every two years in accordance with 10 CFR 50.71(e).3 There are no Rancho Seco records related to Item (3)(ii) because there have been no spills outside the Rancho Seco Industrial Area. There are no Rancho Seco records related to Item (3)(iii) because there have been no licensed material wastes buried outside the Rancho Seco Industrial Area.
There are no Rancho Seco records related to Item (3)(iv) because there are no areas outside the Rancho Seco Industrial Area that require decontamination or application for approval of disposal under 10 CFR 20.2002.
Paragraph (4) of 10 CFR 30.35(g), 10 CFR40.36(f}, and 10 CFR 70.25(9)
Paragraph (4) of 10 CFR 30.35(g), 10 CFR40.36(f), and 10 CFR 70.25(g) addresses i
records of the cost estimate performed for the decommissioning funding plan, and
- 1. records of the funding method used for assuring funds. SMUD has previously provided thi~ information to the NRC. Specifically, the Rancho Seco decommissioning cost
Zahira Cruz DPG 17-059 estimate and associated finding plan are incorporated into Chapter 7 of the Rancho Seco License Termination Plan.
The Rancho Seco decommissioning cost estimate and funding status is updated annually and a copy is forwarded to the NRC in accordance with 10 CFR 50.75(f)(1) and 10 CFR 72.30(b)(6). The latest update to the Rancho Seco Report on Decommissioning Funding Status was submitted to the NRC in SMUD letter DPG 17-051, dated March 22, 2017.
With the prior submittal to the NRC of those records applicable to Rancho Seco and required by Paragraphs (1 ), (2), (3), and (4) of 10 CFR 30.35(g), 10 CFR 40.36{f), and 10 CFR 70.25(g), Rancho Seco considers the requirements of 10 CFR 30.51(f), 10 CFR 40.61 (f), and 10 CFR 70.51 (a)(3) to be satisfied for Rancho Seco license termination.
With the records provided to the NRC in prior submittals, this letter satisfies the applicable requirements in 10 CFR 30, 10 CFR 40, and 10 CFR 70 for forwarding required records to the appropriate NRC Regional Office prior to termination of the Rancho Seco 10 CFR Part 50 license.
If you or members of your staff have any questions requiring additional information or clarification, please contact me at (916) 732-4893.
Sincerely, Dan Tallman
.Manager, Rancho Seco Assets (BJ/DT)
Enclosure (Attachment 1: 2017 Annual Radioactive Effluent Release Report) cc: w/attachment Kriss Kennedy, Administrator, NRC Region IV Jack Parrott, NRC, Project Manager RIC 1F.099
Attachment 1 2017 Annual Radioactive Effluent Release Report
. .-. . RANCHO se,co NUCLEAR GENERATING STATION LICENSE NUMBERS DPR-54 and SNM-2510 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE OF CONTENTS INTRODUCTION ........................................................................................................................................... 1 I. SUPPLEMENTAL INFORMATION .................................................................................................. 2 A. Regulatory Limits & Guidelines for Effluent Releases ...................... ,.................................. 2 B. Maximum Effluent Concentrations ...................................................................................... 3 C. Measurement Methods for Total Radioactivity .................................................................... 3 D. Batch Releases (via monitored pathways) .......................................................................... 4 E. Unplanned Releases ........................................................................................................... 4 F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 Days ....................................................................................................................................4 II. ESTIMATION OF ERROR .......... ~ .................................................................................................... 5 Ill. GASEOUS EFFLUENTS .................................................................................................................. 6 TABLE Ill-A: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES .................................. 7 TABLE 111-B: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES ......................................... 7 TABLE 111-C: GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION ................... 8 TABLE 111-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES ............................................................................................................................ 9 IV. LIQUID EFFLUENTS ...................................................................................................................... 10 TABLE IV-A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES ..................................... 11 TABLE IV-B: LIQUID EFFLUENTS ................................................................................................ 12 TABLE IV-C: LIQUID EFFLUENTS - TYPICAL LOWER LIMITS*OF DETECTION ....................... 13 TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES ........................................................................................................................ 14 V. SOLID WASTE ............................................................................................................................... 15 TABLE V-A: Low-Level Radioactive Waste, Resins, Filters, and Evaporator Bottoms ................. 15 TABLE V-A: Low-Level Hadioactive Waste, Dry Active Waste ...................................................... 15 TABLE V-A: Low-Level Radioactive Waste, Irradiated Components ............................................. 16 TABLE V-A: Low-Level Radioactive Waste, Other Waste ............................................................. 16 TABLE V-A: Low-Level Radioactive Waste, Sum of All Low-Level Waste Shipped from Site .................................................................................................................................... 17 ATTACHMENTS None
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 INTRODUCTION Rancho Seco Nuclear Generating Station (RSNGS) Unit No. 1 is located in Sacramento County, California approximately 25 miles sout~east"of Sacramento and 26 miles north-northeast of Stockton.
Rancho Seco Unit No. 1 began commercial operation on April 17, 1975. The single unit on the Rancho Seco site was a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity was 913 megawatts electrical. Because of a public vote on June 6, 1989, Sacramento Municipal Utility District (SMUD) shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8, 1989. Transfer of the spent fuel rod assemblies from the Spent Fuel Pool into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) was completed on August 21, 2002.
Radiological dismantlement of the nuclear facility was completed in December 2008 and the release of the Rancho Seco property, except for the area associated with the Interim Onsite Storage Building (IOSB), from NRG license DPR-54 was approved on September 25, 2009. With the completion of Phase I of decommissioning, the facility was placed in a SAFSTOR-type condition awaiting a suitable disposal option for the low-level radioactive waste in storage in the IOSB. In 2014, the Class B & C radioactive waste stored in the IOSB was shipped to a suitable disposal facility in Texas. Phase II of decommissioning (the IOSB and surrounding area) began in 2015 and was completed in the first quarter of 2017.
This Annual Radioactive Effluent Release Report (AR ERR) provides a summary of gaseous and liquid effluent releases made from Rancho Seco during the period of January 1, 2017 through March 30, 2017.
This report also provides a summary of solid radioactive waste shipments during the reporting period.
In the current condition, there are no radioactive liquids or liquid systems at the facility. Radioactive material handing during limited remediation activities associated with the Phase II decommissioning effort, as well as subsequent waste packaging activities were monitored with local air sampling as was the exhaust ventilation system. None of these portable air samples returned activity levels above MDA, eliminating the potential of radioactive material being released from the facility in gaseous effluents.
Accordingly, there were no radioactive liquid or gaseous effluent releases made from Rancho Seco during the reporting period.
One shipment of solid radioactive waste was made during the reporting_period utilizing contract brokerage services This report has been prepared by SMUD to meet the requirements of Rancho Seco Quality Manual (RSQM), Appendix A, Section 1.5.2.4 and Offsite Dose Calculation Manual (ODCM) Revision 23, Step 6.10.1. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. Radiation doses associated with radioactive effluents in liquids and gasses would be calculated for a hypothetical individual who receives the maximum possible exposure at or beyond the applicable Site Boundary, had any releases occurred.
Since there were no releases of radioactivity in gaseous and liquid effluents during this report period, the limits of 1 O CFR 20 were not exceeded, nor were the numerical guidelines of 10 CFR 50, Appendix I exceeded. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix I.
1
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 I. SUPPLEMENTAL INFORMATION A. Regulatory Limits & Guidelines for Effluent Releases
- 1. Gaseous Effluents
- a. Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.9.3):
1500 mrem/year to any organ
- b. Dose commitment to a member of the public at or beyond the Site Boundary for Gaseous Effluents from Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.9.4, numerical guidelines of 10 CFR 50, Appendix I):
7.5 mrem per calendar quarter to any organ 15 mrem per calendar year to any organ
- 2. Liquid Effluents
- a. The concentration of radioactive material in liquid effluents released beyond the Site Boundary for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 2, Column 2.
- b. Dose commitment to a member of the public at or beyond the Site Boundary for Liquid Effluents from radioactive materials in liquid effluents shall be limited to (numerical guidelines of 10 CFR 50, Appendix I):
1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter to any organ 3 mrem per calendar year to the total body 10 mrem per calendar year to any organ NOTE: The noble gas source term was removed when spent fuel transfer to the ISFSI was completed in August 2002. Reference to noble gases was completely removed from the ODCM.
2
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 B. Maximum Effluent Concentrations
- 1. Gaseous Effluents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (air) are not directly used in calculations for determining permissible gaseous effluent release rates.
The annual dose limits of 10 CFR 20 for unrestricted areas are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 2, Column 1. ODCM Technical Requirement dose rate limits (mrem/yr) for gaseous effluents are provided to ensure that the dose rate from gaseous effluents at any time at the Site Boundary for Gaseous Effluents will be within the annual dose limits of 10 CFR 20 for unrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release rates.
- 2. Liquid Effluents The concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2 are used in calculations to determine permissible liquid discharge flow rates. The most conservative Maximum Effluent Concentration (MEC) value for each radionuclide detected in the liquid effluent sample is used in the calculations.
C. Measurement Methods for Total Radioactivity The methods listed below are examples should radioactive effluents be discharged.
- 1. Gaseous Effluents Liquid Scintillation (H-3)
Gamma Spectroscopy (HPGe)
Beta Proportional (Sr-90, gross beta)
Alpha Proportional (gross alpha)
- 2. Liquid Effluents Gamma Spectroscopy (HPGe)
Liquid Scintillation (H-3)
Beta Proportional (Sr-90, gross beta)
Alpha Proportional (gross alpha)
NOTE: HPGe refers to Hyper-Pure Germanium 3
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 D. Batch Releases (via monitored pathways)
Quarter 1 Quarter 2 Quarter 3 Quarter4 Liquid Discharges Number of batch releases 0 NIA NIA NIA Total time period for batch releases (hours) NIA NIA NIA NIA Maximum time period for a batch release (hours) NIA NIA NIA NIA Average time period for a batch release (hours) NIA NIA NIA NIA Minimum time period for a batch release (hours) NIA NIA NIA NIA Average Plant Effluent Flow (cfs) NIA NIA NIA NIA None E. Unplanned Releases This section describes unplanned releases of radioactivity in liquid and gaseous effluent.
Gaseous None None F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 Days None 4
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
.JANUARY - MARCH 2017 II. ESTIMATION OF ERROR The methods for establishing error estimates included review of applicable station procedures, inspection of sampling equipment, engineering e~timates, statistical. applications, review of calibration setpoint data, and communication with plant personnel. The various sources of error (s) in reported values of gaseous
.effluents, liquid effluents, and solid waste are assumed to be independent, and thus the total error is calculated according to the formula:
where: cri =relative error associated with component i Sources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficiency, counting, and calibration.
Sources of error for liquid effluents include collection container volume, dilution water flow rate, grab sampling, counting, and calibration.
Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose rate meter reading, computer program dose-to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 Ill. GASEOUS EFFLUENTS Table Ill-A, Gaseous Effluents - Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of tritium and particulates with half-lives greater than 8 days. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows: ., ,
- L[(Fi)(Avg Rel Rate)(X I Q)(Dose Factor)]
% Tech Req Limit = ~--------*----- x 100%
(Dose Rate Limit) where:
Fi = The fraction of the total number of Curies of nuclide i out of the total curies in that category for that quarter (unitless).
NOTE: Fi always equals 1.0 for H-3 because it is the only nuclide in the category.
(Total Curies per category per quarter:( E +~~µCi) 1 Avg Rel Rate=-------------..,-'----~
(# seconds in the quarter)
XIQ = A default dispersion factor determined to be conservative when compared to the use of actual data (sec/m3).
Dose Factor = The values derived for each nuclide i from NRG Regulatory Guide 1.109 (Ki, Li+1.1 Mi, or Raij). [Units in (mrem/yr)/(µCi/m3)]
Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed in Section I of this report (mrem/yr).
NOTE: Particulates with half-lives less than 8 days are not included in this calculation.
The methodology used to calculate the Estimated Total Error(%) in Table Ill-A is presented in Section II of this report.
Table 111-B, Gaseous Effluents - Ground Level Releases, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batch releases are provided for particulates and tritium. Data reported for batch releases results only from unplanned releases.
Table 111-C, Gaseous Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in µCi/cc for various radionuclides.
Table 111-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 2017 Annual REMP Report). The maximum calculated organ dose is listed for each quarter along with an annual total. The direct radiation dose results, based on monitoring badge dosimetry, are also listed. Presented in this table for each category is a comparison versus ODCM Technical Requirement dose limits with the exception of direct radiation measurements.
6
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE 111-A: GASEOUS EFFLUENTS - SUMMAflON OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error.%
A. Particulates
- 1. Particulates with half-lives>8 days Ci O.OOE+OO N/A N/A N/A N/A
- 2. Average Release Rate for period µCi/sec O.OOE+OO N/A N/A N/A
- 3. Percent of Tech Req limit % N/A NIA N/A N/A
- 4. Gross Alpha radioactivity Ci O.OOE+OO N/A N/A N/A B. Tritium
- 1. Total Release Ci O.OOE+OO N/A NIA N/A N/A
.~. '::
- 2. Average Release Rate for period µCi/sec O.OOE+OO N/A N/A N/A :*
- "":i*
- 3. Percent of Tech Req limit % N/A N/A N/A N/A TABLE 111-B: GASEOUS EFFLUENTS -GROUND LEVEL RELEASES Nuclides Released
- 1. Particulates None
- 2. Tritium None 7
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE 111-C: GASEOUS EFFLUENTS -TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES LLD (µCi/cc)
- 2. Particu Iates:
Manganese-54 2.08 E-12 Cobalt-58 2.29 E-12 lron-59 5.89 E-12 Cobalt-60 3.11 E-12 Strontium-89 2.00 E-15 Strontium-90 5.00 E-15 Cesium-134 1.52 E-12 Cesium-137 1.88 E-12 Barium-140 3.06 E-12 Cerium-141 1.15 E-12 Cerium-144 3.69 E-12 8
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE 111-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:
2017 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 YTD A. Tritium, Particulate
- 2. Percent of Tech Req limit % NIA NIA NIA' NIA NIA NOTE: No releases of gaseous radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2017.
1 None of the Indicator stations indicate significant radiation attributable to facility operations.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MAROH 2017 IV. LIQUID EFFLUENTS .\.-*.'
Table IV-A, Liquid Effluents - Summation of All Releases, provides a detailed summary of liquid effluent releases per ql!arter. This table,,summarizes releases of fission and activation products, tritium, dissolved and entrained gases, and gross alpha radioactivity.
Also listed is the volume of waste released prior to dilution and the volume of dilution water used during each quarter.
The following methodology is used to calculate the Average Diluted Concentration and the Percent of ODCM Technical Requirement Limit in Table IV-A:
% Tech Req Limit = I[ Ci ]
i MECi where: n = The total number of radionuclides identified Ci = The average diluted concentration of radionuclide i (Total Release per Category per Quarter in µCi)
=
(Total Release Volume(part Fin Table IV -A)in ml)
The MECof the i1h radionuclide, from 10 CFR 20, Appendix B, Table 2, The methodology used to calculate the estimated total error in Table IV-A is presented in Section II of this report.
Table IV-B, Liquid Effluents, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed in Table IV-A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data is provided only for batch releases.
Table IV-C, Liquid Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in µCi/ml for various radionuclides.
Table IV-D, Radiological Impact on Man Due To Liquid Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Liquid Effluents (actual doses will be assessed in the 2015 Annual REMP Report). The maximum calculated total body dose and organ dose are listed for each quarter along with an annual total. A comparison versus ODCM Technical Requirement dose limits is also presented.
10
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE IV-A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error,%
A Fission & Activation Products N/A N/A
- 1. Total Release (not including tritium, gases, alpha) Ci 0.00 E+OO N/A N/A N/A N/A
- 2. Average diluted concentration during period µCi/ml 0.00 E+OO N/A
- 3. Percent of Tech Req limit % N/A NIA N/A N/A
- 8. Tritium N/A N/A N/A
- 1. Total Release Ci 0.00 E+OO N/A N/A NIA , N/A
- 2. Average diluted conce.ntration during period µCi/ml 0.00 E+OO
- 3. Percent of Tech Req limit % N/A N/A N/A N/A C. Dissolved and Entrained Gases NIA N/A N/A
- 1. Total Release Ci 0.00 E+OO N/A N/A NIA N/A
- 2. Average diluted concentration during period µCi/ml 0.00 E+OO D. Gross Alpha radioactivity N/A N/A N/A
- 1. Total Release Ci 0.00 E+OO N/A N/A N/A N/A E. Volume of Waste Released (prior to dilution) Liters 0.00 E+OO N/A F. Volume of dilution water used during period Liters N/A N/A N/A N/A N/A 11
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE IV-B: LIQUID EFFLUENTS Nuclides Released
- 1. Fission and activation products (excluding tritium. gross alpha)
None
- 2. Dissolved and entrained gases None NOTE: No releases of liquid radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2017.
12
RSNGS ANNUAL RADiOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE IV-C: LIQUID EFFLUENTS -TYPICAL lOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (µCi/mil
- 2. Particulates:
Manganese-54 2.11 E-09 lron-59 3. 71 E..:09 Cobalt-57 2.12 E-09 Cobalt-58 1.93 E-09 Cobalt-60 1.98 E-09 Zinc-65 4.34 E-09 Strontium-90 5.00 E-10 Ruthenium-106 1. 79 E-08 Silver-110m1.94 E-09 Antimony-125 5.78 E-09 Cesium-1341.93 E-09 Cesium-1362.23 E-09 Cesium-1372.30 E-09 Barium-140 7.75 E-09 Cerium-141 3.60 E-09 Cerium-1441.59 E-08 13
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 TABLE IV-D: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:
2017 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 YTD A. Maximum Total Body Dose mrem 0.00 E+OO NIA NIA NIA 0.00 E+OO Percent Tech Req limit % NIA NIA NIA NIA NIA B. Maximum Organ Dose mrem 0.00 E+OO NIA NIA NIA 0.00 E+OO Percent Tech Req limit % NIA NIA NIA NIA NIA 14
RSNGS ANNUALRAplOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 V. SOLID WASTE A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
Table V-A: Low-Level Waste 1 Resins1- Filters, and< *
- *Evaporiiior
~*' . ,, ; ' ,. /};,-<' ..:,..
Bottoms.
' ,,<<* * ~:<'."~"~<->'.~
A 0.00 E+OO 0.00 E+OO 0.00 E+OO 8 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None
""/'***.***\ ' ~<-J.."* , ,,.s~.:; .,,
.*;*.~~~4~1~~~{§hipp~~-'.0,._
A 3.95 E+02 1.12 E+01 2.19 E-02 8 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 3.95 E+02 1.12 E+01 2.19 E-02 Major Nuclides for the Above Table: Ba-133; H-3 15
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- MARCH 2017 Table V-A: Low-Level Waste continued A 0.00 E+OO 0.00 E+OO 0.00 E+OO B 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None
!'.< ::;)/<\
.:curi~s.Sbippect;;,';~
,. ',% . *: '" '; ' ... , ' '/ '::J:" '.',*
-;,~
A 0.00 E+OO 0.00 E+OO 0.00 E+OO B 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO 0.00 E+OO Major Nuclides for the Above Table: None 16
-- I RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - MARCH 2017 Table V-A: Low-Level Waste continued
>Sum:*ofAll Low-Lev~{. Volume Waste Shipped from
,.. *
- Site .
Waste Class:*
A 3.95 E+02 1.12 E+01 2.19 E-02 B 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 3.95 E+02 1.12 E+01 2.19 E-02 Major Nuclides for the Above Table: Ba-133; H-3 17