ML090900745
| ML090900745 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/18/2009 |
| From: | Adams W Oak Ridge Institute for Science & Education |
| To: | John Hickman NRC/FSME |
| References | |
| RFTA #06-003 | |
| Download: ML090900745 (66) | |
Text
P. 0.
Box11 Oa Rig, N373 C)GR-I S 1E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION March 18, 2009 Mr. John Hickman Mail Stop: T-8F5 Office of Federal and State Materials and Environmental Management Programs U.S. Nuclear Regulatory Commission 11545 Rockville Pike Rockville, MND 20852
SUBJECT:
DRAFT-CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA DCN 1695-SR-04-DRAFT (DOCKET NO. 50-312, RFTA NO.06-003)
Dear Mr. Hickman:
The Oak Ridge Institute for Science and Education (ORISE) performed confirmatory survey activities on structural surfaces in the Auxiliary Building (Rooms 132 and 319), the Auxiliary Steam Supports, The Turbine Building (North Condensate Area, Condensate Pump Pit, Lube Oil Pit, North Central Floor, and Grade Level South), and the Fuel Storage Building [+40 Level and the Spent Fuel Pool (Floor, East Wall, West Wall, North Wall and South Wall)] at the Rancho Seco Nuclear Generating Station in Herald, California on September 9 through 11 and October 27 through 30, 2008. These survey activities were requested and approved by the U.S. Nuclear Regulatory Commission (NRC). Enclosed is the draft report that summarizes ORISE's survey procedures and results of the confirmatory surveys. The surveys included beta and gamma surface scans, direct measurements for total net beta activity, and smears for removable alpha and beta activity.
If you have any questions, please direct them to me at 865.576.0065 or Tim Vitkus at 865.576.5073.
Sincere ly,
/
Wade C. Adams ORISE Health Physicist/Project Leader Survey Projects WCA:ar Enclosure c:
T. Carter, NRC/FSME/DWMEP/DD/SP T-8F5 T. Patterson, NRC/FSME/TWFN 8A23 T. Youngblood, NRC/FSME/DWMEP/TWVFN 8 F5 R. Evans, NRC/Region IV E. Abelquist, ORISE S. Roberts, ORISE T. Vitkus, ORISE File 1695 Distribution approval and concurrence:
Initials.M Technical Review u"l' Laborarory Review QualityI ReviewF Voice: 865.576.0065 Fax: 865.241.3497 E-mail: Wade.Adanmisorau.or*
CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Prepared by W. C. Adams ORISE Prepared for the.
U.S. Nuclear Regulatory Commission DRAFT REPORT March 2009 This draft report has not been given full review and patent clearance, and the dissemination of its information is only for official use. No release to the public shall be made without the approval of the funding agency or other customer.
This report is based on work performed by the Oak Ridge Institute for Science and Education under contract number DE-AC05-06OR23100 with the Department of Energy.
Prepared bythe Oak Ridge Institute for Science and Education, under interagency agreement (NRC FIN No. J1008) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.
Rancho Seco Nuclear Generating Station 1695-SR-04-DRAF1T
ACKNOWLEDGMENTS The author would like to acknowledge the significant contributions of the following staff members:
FIELD STAFF B. D. Estes T. D. Herrera E. Montalvo LABORATORY STAFF R. D. Condra J. S. Cox W. P. Ivey W. F. Smith CLERICAL STAFF R. M. Fink K. M. Moore A. Ramsey ILLUSTRATORS T. L. Brown K. M. Moore Rancho Seco Nuclear Generating Station 1695-SR-04-DR-AFTf
TABLE OF CONTENTS PAGE List of Figures.......................................................................................................................................................
ii List of Tables.....................................................................................................................................................
iv A bbreviations and A cronym s............................................................................................................................
v Introduction and Site H istory..........................................................................................................................
1 Site D escription..................................................................................................................................................
2 O bjective.............................................................................................................................................................
2 D ocum ent R eview.............................................................................................................................................
3 Confirm atory Survey Procedures..........................................................................................................
3 Reference System...........................................................................................................................................
4 Surface Scans..................................................................................................................................................
4 Surface A ctivity M easurem ents...........................................................................................................
5 Sam ple A nalysis and D ata Interpretation..................................................................................................
5 Findings and Results.....................................................................................................................................
6 D ocum ent Review............................................
6 Surface Scans...................................................................................................................................................
6 Surface A ctivity Levels.................................................................................................................................
6 Com parison of Results W ith Site Release Criteria..................................................................................
7 Conclusion..........................................................................................................................................................
7 References............................................................................................................................................
............... 9 Appendices:
Appendix A:
Figures Appendix B:
Tables Appendix C:
Major Instrumentation Appendix D:
Survey and Analytical Procedures Rancho Seco Nuclear Generating Station i
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LIST OF FIGURES PAGE Figure A-1: Location of Rancho Seco Nuclear Generating Station, Herald, California............... A-1 Figure A-2: Plot Plan of the Industrial Area at Rancho Seco Nuclear Generating Station............... A-2 Figure A-3: SurveyUnit F8130731, Auxiliary Building, Room 51, Section 3 Wall - Direct M easurem ent and Sam pling Locations......................................................................................................
A -3 Figure A-4: Survey Unit F813121 1, Auxiliary Building, Room 132 - Direct Measurement and S am p lin g L o catio n s........................................................................................................................................
A -4 Figure A-5: Survey Unit F8131372, Auxiliary Building, Rooms 208 and 211 - Direct M easurem ent and Sam ple Locations...................................................................................................
A -5 Figure A-6: Survey Unit F8131781, Auxiliary Building, Room 319 - Direct Measurement and S am p le L o catio n s..........................................................................................................................................
A -6 Figure A-7: Survey Unit F8132133 and F8132134, Auxiliary Steam Support Pads - Direct M easurem ent and Sam ple Locations.........................................................................................................
A -7 Figure A-8: Survey Unit F8260010, Turbine Building, North Condensate Pit Area - Direct M easurem ent and Sam ple Locations.........................................................................................................
A -8 Figure A-9: Survey Unit F8260004, Turbine Building, Condensate Pump Pit - Direct M easurem ent and Sam ple Locations.........................................................................................................
A -9 Figure A-10: Survey Unit F8260011, Turbine Building, Lube Oil Pit - Direct Measurement and S am p le L o catio n s...........................................................................................................................
- ............ A -10 Figure A-11
- Survey Unit F8260171, Turbine Building, North Central Floor - Direct M easurem ent and Sam ple Locations................................................................................................
A -1 1 Figure A-12: Survey Unit F8260151, South Turbine Building - Direct Measurement an d Sam p le L o cation s...............................................................................................................................
A -12 Figure A-13: Survey Units F8261003 and F8261004, High Pressure Turbine Pedestals -
Direct Measurement and Sample Locations......................................................................................
A-13 Figure A-14: Survey Unit F8121001, Fuel Storage Building +40' Elevation - Direct M easurem ent and Sam ple Locations.................................................................................................
A -14 Figure A-15: Survey Unit F8120005, Spent Fuel Pool Floor - Direct Measurement and S am p le L o catio n s........................................................................................................................................
A -15 Figure A-16: Survey Unit F8120003, Spent Fuel Pool, East Wall - Direct Measurement an d Sam ple L o cation s................................................................................................................................
A -1 6 Figure A-17: Survey Unit F8120001, Spent Fuel Pool, West Wall - Direct Measurement an d Sam ple L o cation s................................................................................................................................
A -17 Figure A-18: Survey Unit F8120004, Spent Fuel Pool, North Wall - Direct Measurement an d Sam ple L o cation s................................................................................................................................
A -1 8 Rancho Seco Nuclear Generating Station ii 1695-SR-04-DRAFT
LIST OF FIGURES (continued)
PAGE Figure A-19: Survey Unit F8120121, Fuel Storage Building, West ExteriorWall - Direct M easurem ent and Sam ple Locations............................. ;....................................................................... A -19 Figure A-20: Survey Unit F8000104, Pump Alley Access Corridor - Direct Measurement and S am p le L o catio n s.........................................................................................................................................
A -2 0 Figure A-21: Survey Unit F834001 1, Industrial Area Railway - Direct Measurement L o catio n s........
A -2 1 Rancho Seco Nuclear Generating Station 111 1695-SR-04-DRAFT
LIST OF TABLES PAGE Table 1: ORISE Confirmatory Survey Areas...........................................................................................
4 Table B-I: Derived Concentration Guideline Levels and Elevated Measurement Comparisons fo r S u rv eyed A reas.........................................................................................................................................
B -1 Table B-2: Survey Unit Classification and Scan Coverage.......................................................................
B-3 T able B -3: Surface A ctivity L evels..............................................................................................................
B -5 Rancho Seco Nuclear Generating Station iv 1695-SR-04-DRAFT
ABBREVIATIONS AND ACRONYMS bi d'
as stotal BKG cm cm2 Co-60 COC cpm Cs-137 CsIrl)
DCGL DCGLFMc DP dpm/100 cm2 DQOs DTBD FSS FSSP FSSR GM IEAV ISFSI ISM ITP JHA keV LTP mg MAPEP MARSSIM MDC MDCR MeV mrem /yr msl MWe NaI(T1)
NIST NRC NRIP ORAU number of background counts in the interval index of sensitivity instrument efficiency surface efficiency total efficiency background centimeter square centimeter cobalt-60 contaminants of concern counts per minute cesium-137 cesium iodide (thallium-activated) derived concentration guideline level DCGL elevated measurement comparison decommissioning plan disintegrations per minute per 100 square centimeters data quality objectives decommissioning technical basis document final status survey final status survey plan final status survey report Geiger-Mueller Independent Environmental Assessment and Verification independent spent fuel storage installation Integrated Safety Management Intercomparison Testing Program job hazard analysis kiloelectron volts license termination plan milligram Mixed Analyte Performance Evaluation Program Multi-Agency Radiation Survey and Site Assessment Manual minimum detectable concentration minimum detectable count rate million electron volts millirem per year mean sea level megawatt electric sodium iodide (thallium-activated)
National Institute of Standards and Technology U.S. Nuclear Regulatory Commission NIST Radiochemistry Intercomparison Program Oak Ridge Associated Universities Rancho Seco Nuclear Generating Station V
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ABBREVIATIONS AND ACRONYMS (continued)
ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram PSDAR Post Shutdown Decommissioning Activities Report PWR pressurized water reactor RSNGS Rancho Seco Nuclear Generating Station sec second SMUD Sacramento Municipal Utility District SU survey unit Sr/Y-90 strontium/yttrium-90 SRC site release criteria Tc-99 technetium-99 TEDE total effective dose equivalent TI -204 thallium-204 Generating Station vi 1695-S Rancho Seco Nuclear(
- R-04-DRAFT
DRAFT CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA INTRODUCTION AND SITE HISTORY The Sacramento Municipal Utility District (SMUD) operated the Rancho Seco Nuclear Generating Station (RSNGS) from 1976 to 1989 under Atomic Energy Commission Docket Number 50-312 and License Number DPR-54. RSNGS was a 913-megawatt electrical (MWe) pressurized water reactor (PWR) designed by Bechtel Power Corporation. The plant incorporated a pressurized water type nuclear steam supply system supplied by Babcock and Wilcox Company, a turbine generator and electrical systems, engineered safety features, radioactive waste systems, fuel handling systems, instrumentation and control systems, the necessary auxiliaries, and structures to house plant systems and other onsite facilities.
On June 7, 1989, RSNGS permanently shut down, due to a public vote the previous day, after approximately 14 years of operation. On August 29, 1989, SMUD formally notified the U.S.
Nuclear Regulatory Commission (NRC) of the permanent cessation of operations at the RSNGS.
In May 1991, SMUD submitted the Rancho Seco Decommissioning Plan (DP), which was approved by the NRC in March 1995. SMUD submitted the Post Shutdown Decommissioning Activities Report (PSDAR), in accordance with 10CFR50.82 (a) (4), in March 1997. SMUD began decommissioning activities in February 1997 and completed transfer of all the spent nuclear fuel in August 2002. SMUD is currently completing decontamination efforts and performing final status surveys (FSS) in the remaining structural surfaces and open land areas.
In April 2006, SMUD submitted a license termination plan (LTP) that the NRC approved on November 26, 2007 (SMUD 2006a and NRC 2007). SMUD is currently conducting decontamination efforts and performing FSS on the remaining structural surfaces and in open land areas. The major contaminants of concern (COC) identified by SMUD at RSNGS are beta-gamma emitters-fission and activation products-resulting from reactor operation. Cesium-137 (Cs-137) and cobalt-60 (Co-60) have been identified during characterization as the predominant radionuclides present on structural surfaces.
Rancho Seco Nuclear Generating Station 1695-SR-04-DRAFT'
The NRC's Headquarters and Region IV Offices have requested that the Independent Environmental Assessment and Verification (IEAV) Program of the Oak Ridge Institute for Science and Education (ORISE) perform confirmatory surveys of structural surface survey units (SU) in several Auxiliary, Turbine and Fuel Storage Building rooms, the Pump Alley, and the Fuel Storage Building exterior excavation at the RSNGS (Figures A-1 and A-2). The confirmatory surveys were performed during the period of September 9 through 11 and October 27 through 30, 2008.
SITE DESCRIPTION The RSNGS is located in the southeast part of Sacramento County, California and is approximately 26 miles northeast of Stockton and 25 miles southeast of Sacramento. The site lies between the Sierra Nevadas to the east and the Pacific Coast Range bordering the Pacific Ocean to the west in an area of flat to slightly rolling terrain at an elevation of approximately 200 feet above mean sea level.
The land surrounding the site is used almost entirely for agricultural purposes, as grazing land, and for grape production. The owner-controlled site is approximately 2,500 acres with all acreage being owned by SMUD. An 87-acre fence-enclosed Industrial Area (Figure A-2) containing the nuclear facility is within the owner-controlled area. Approximately 0.5 miles south of the Industrial Area boundary is a 30-acre gas-fired power plant. The site also contains the 560-acre Rancho Seco Reservoir and Recreation Area, a 50-acre solar power electrical generating station, and a 10-acre independent spent fuel storage installation (ISFSI).
The RSNGS design included several structures that were engineered and constructed to contain radioactive material. These structures were located within the Industrial Area boundaries and included the Auxiliary Building, the Containment/Reactor Building, the Spent Fuel Building, the Fuel Storage Building, the Turbine Building, the Cooling Towers and structures containing tanks for storage of radioactive liquids. The site also included ancillary facilities that were used to support normal plant operations. These facilities consisted of warehouses, water and sewage treatment plants, and administrative office buildings.
OBJECTIVE The objective of the confirmatory survey was to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's FSS results.
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DOCUMENT REVIEW ORISE reviewed the licensee's preliminary final radiological survey data for adequacy and appropriateness, taking into account data quality objectives (DQOs) contained in the LTP (SMUD 2006a). ORISE also reviewed and evaluated final status survey plans (FSSP) and final status survey reports (FSSR) in accordance with the ORISE site-specific survey plan to ensure that FSS procedures and results adequately met site LTP commitments and Multi-Agengy Radiation Survey and Site Investigalion Manual (MARSSIM) considerations (ORISE 2007a, SMUD 2006a and NRC 2000).
CONFIRMATORY SURVEY PROCEDURES T6 expedite the confirmatory survey process, ORISE coordinated and worked with the NRC site representative to conduct confirmatory surveys as the licensee provided preliminary FSS survey data.
This provided the NRC the quality assurance metric that the site's reported radiological status satisfied the site license termination criteria. ORISE survey activities were performed in a manner that addressed the confirmatory objective listed above. ORISE performed confirmatory survey activities in judgmentally selected survey units on the RSNGS site. These confirmatory survey activities assessed whether remediation activities met the DQOs for unrestricted release.
In September and October 2008, ORISE conducted radiological confirmatory survey activities of the RSNGS structural surfaces within the Auxiliary, Turbine and Fuel Storage buildings.
Confirmatory surveys included beta and gamma surface scans and surface activity measurements, and collecting radiological soil samples. Locations of elevated direct radiation that potentially exceeded the derived concentration guideline levels (DCGLs) were marked for further investigation.
Confirmatory surveys were performed in accordance with a site-specific survey plan that was submitted to and approved by the NRC (ORISE 2007a). The site-specific sdirvey. plan followed the guidance provided in the IEAV Survey Procedures Manual and the Oak Ridge Associated Universities Quality Program Manual (ORISE 2008a and ORAU 2007).
ORISE performed confirmatory survey activities on structural surfaces within the following buildings and exterior areas:
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Building/Area Figures Rooms 51, 132, 208, 211, 319, Auxiliary Building 320, and the Auxiliary Steam.
A-3 through A-7 Supports Condensate Pits, the Lube Oil Pit, the Main Feed :Pump Area, Turbine Building on the High Pressure Turbine A-8 through A-13 Pedestals and at various locations on the grade level floor Spent Fuel Pool floor and Fuel Storage Building walls, the +40 foot level floor A-14 through A-19 and lower walls and the West Exterior Wall Pump Alley Access Corridor Other Exterior Areas and the Industrial Area Railway A-20 through A-21 Class 1 Areas REFERENCE SYSTEM Measurements and sampling locations were referenced to the existing RSNGS grid system and/or on RSNGS provided figures.
SURFACE SCANS Surface scans for beta and gamma radiation were performed on structural surfaces that could be safely accessed. Scan coverage percentage was based upon the SU classification and increased or decreased depending on findings as the survey progressed and project time constraints. Scans for gamma and beta radiation were performed using sodium iodide, thallium-activated. [NaI(Tl)]
scintillation, gas proportional, and/or Geiger-Mueller (GM) detectors. Particular attention was given to cracks and joints in the surfaces, exposed concrete surfaces, and other locations where material may have accumulated. Locations of elevated direct radiation, suggesting the presence of residual contamination, were marked and identified for judgmental measurements. All detectors were coupled to ratemeters or ratemeter-scalers with audible indicators.
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SURFACE ACTIVITY MEASUREMENTS Direct measurements for total beta activity were performed at judgmentally-selected locations where residual contamination, identified by surface scans, exhibited radiation levels potentially above acceptat~le unrestricted release limits established for the site. The number of judgmental direct measurements performed depended on findings as the survey progressed and project time constraints.
Based on beta and gamma surface scan results, direct measurements for beta activity were performed at 66 judgmentally-selected locations on the evaluated structural surfaces within the Auxiliary, Turbine, and Fuel Storage buildings. In addition, four direct measurements were performed in the Pump Alley Access Corridor and three direct measurements were performed in the Industrial Area Railway. Direct measurements were performed using hand-held gas proportional and GM detectors coupled to ratemeters-scalers. With the exception of the Industrial Area Railway, dry smears, for determining removable gross alpha and beta activity, were collected from each direct measurement location. Direct measurement and smear locations are indicated on Figures A-3 through A-21.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to the ORISE laboratory in Oak Ridge, Tennessee for analysis and interpretation. Samples were analyzed in accordance with the ORISE Laboratory Procedures Manual (ORISE 2008b). Smears were analyzed for gross alpha and gross beta activity using a low-background proportional counter. Smear results and direct measurements for total surface activity were converted to units of disintegrations per minute per 100 square centimeters (dpm/100 cm 2). The data generated were compared with the licensee's gross beta and design DCGLs for each specific SU where confirmatory surveys were performed (Table B-I).
The primary COCs for the RSNGS are beta-gamma emitters-fission and activation products-resulting from reactor operation. Cesium-137 and Co-60 were identified by SMUD during characterization as the predominant radionuclides present on structural surfaces and in the soils. SMUD developed site-specific DCGLs, which were approved by the NRC, based on dose modeling to future occupants not to exceed 25 millirem per year (mrem/yr) total effective dose equivalent (TEDE) as presented in Section 6 of the LTP (SMUD 2006a and NRC 2007). The Rancho Sect Nuclear Generating Station 5
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structural surface DCGL's were modified by SMUD to reflect the ratio of radionuclide concentrations (account for the presence of unmeasured contaminants based on contaminant ratios) in the specific SUs that were being evaluated. The DCGL's for the evaluated structural surfaces (refer to Table B-I) for these confirmatory surveys were provided in the preliminary FSS data packages for each evaluated SU and were derived from the LTP and decommissioning technical basis document (DTBD)-05-015 (SMUD 2006a and b).
Additional information regarding instrumentation and procedures may be found in Appendices C and D.
FINDINGS AND RESULTS The results for the confirmatory surveys are provided below.
DOCUMENT REVIEW ORISE's review of SMUD's preliminary FSS data packages indicated that the procedures and methods implemented for the FSS were appropriate and that the resultant data were acceptable.
SURFACE SCANS Beta and gamma surface scans, in the Auxiliary, Turbine and Fuel Storage buildings, determined that localized areas of residual elevated beta and gamma radiation were present on floors, lower walls, and upper surfaces within the evaluated SUs.
Gamma scans of the Pump Alley Access Corridor and Industrial Area Railway did not detect any residual elevated gamma radiation levels. Beta scans of the Pump Alley Access Corridor also did not indicate any locations of elevated residual beta radiation.
The survey unit classifications and scan percent coverage are provided in Table B-2.
SURFACE ACTIVITY LEVELS Total beta activity measurements ranged from -170 to 1,300,000 dpm/100 cm 2. Residual surface activity levels approaching and exceeding the site-specific gross beta DCGL but less than the SU Rancho Seco Nuclear Generating Station 6
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specific design DCGL elevated measurement comparison (DCGLFMc) were limited to small areas that were interspersed throughout the SUs.
Removable gross alpha and gross beta activity ranged from 0 to 6 and -5 to 190 dpm/100 cm2, respectively.
Beta measurements were performed at seven locations within the Pump Alley Access Corridor and the Industrial Area Railway SUs. Total beta activity measurements ranged from
-40 to 690 dpm/100 cm2. Removable gross alpha activity for the concrete surfaces of the Pump Alley Access Corridor was 0 dpm/100 cm2; beta activity in the same area ranged from
-2 to 1 dpm/100 cm 2. Removable activity measurements were not performed in the Industrial Area Railway. Surface activity and removable activity level results are presented in Table B-3.
COMPARISON OF RESULTS WITH SITE RELEASE CRITERIA With the exception of the Pump Alley Access Corridor and the Industrial Area Railway which had land area DCGL's, confirmatory survey data for structural surfaces were compared with the structural site-specific DCGL for the evaluated SUs. Fourteen of the 66 direct beta activity measurement results on the survey units that had structural surface DCGLs exceeded the Gross Beta DCGL of 43,000 dpm/100 cm 2. Using the gross activity DCGL as determined in DTBD-05-015 (SMUD 2006b) and the area factor determined for each SU, SMUD calculated Design DCGL,,M values which are also provided in Table B-1. The fourteen confirmatory survey results that exceeded the structural surface DCGLs were less than 1 M 2. All confirmatory direct surface activity measurements on the structural surfaces in the evaluated SUs were within the site-specific SU DCGLEMc as provided by SMUD in the preliminary FSS data packages. Also, the maximum gross beta activity measurement of the seven direct measurements performed on the Pump Alley Access Corridor and the Industrial Area Railway was 690 dpm/100 cm 2; and direct measurements in these SUs were well below the structural surface DCGL of 43,000 dpm/100 cm 2.
CONCLUSION During the period of September 9 through 11 and October 27 through 30, 2008, ORISE performed confirmatory radiological survey activities which included beta and gamma surface scans, beta Rancho Seco Nuclear Generating Station 7
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activity direct measurements, and removable gross alpha and gross beta activity measurements on structural surfaces within the Auxiliary, Turbine and Fuel Storage buildings.
Beta and gamma surface scans identified several areas of elevated beta radiation on the structural surfaces of the evaluated SUs. Additional investigations of these locations indicated that the majority of the elevated radiation levels were attributable to localized areas of residual beta-gamma radiation within the matrix of the concrete media. In general, the elevated surface activity was limited to small areas (less than 1 mi2) that were interspersed throughout the rooms. Direct measurements were performed at 66 locations. Fourteen direct measurements exceeded the site-specific gross beta DCGL but all were within the SU specific design DCGLEMc criteria. Direct measurements were also performed at seven locations on the Pump Alley Access Corridor concrete pad and the Industrial Area Railway asphalt pad surfaces. The maximum gross beta activity measurement on these pads was 690 dpm/100 cm2 which is well below the structural surface DCGL of 43,000 dpm/I00 cm2.
The confirmatory survey results for the evaluated SUs are in agreement with the radiological status of these SUs as presented in the licensee's preliminary FSS data packages.
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REFERENCES Oak Ridge Associated Universities (ORAU). Quality Program Manual for the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee; November 1, 2007.
Oak Ridge Institute for Science and Education (ORISE). Final Confirmatory Survey Plan for the Remaining Structural Surfaces, Embedded Piping, Standing Water-and Open Land Area Survey Units, Rancho Seco Nuclear Generating Station, Herald California PDocket No. 50-312; RFTA No. 06-003]. Oak Ridge, Tennessee; August 10, 2007a.
Oak Ridge Institute for Science and Education. Survey Procedures Manual for the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee; May 1, 2008a.
Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee; December 5, 2008b.
Sacramento Municipal Utility District (SMUD). License Termination Plan, Rancho Seco Nuclear Generating Station, Herald, California; April 2006a.
Sacramento Municipal Utility District. Decommissioning Technical Basis Document: Structure Nuclide Fraction and DCGLs. DTBD-05-015, Revision 0. Rancho Seco Nuclear Generating Station, Herald, California; June 2, 2006b.
U.S. Nuclear Regulatory Commission (NRC). Multi-Agengy Radialion Survey and Site Investzgation Manual (MARSSIM), NUREG-1575; Revision 1. Washington, DC; August 2000.
U.S. Nuclear Regulatory Commission. Letter from J. Hickman (NRC-HQ) to S. Redeker (SMUD);
SUBJECT:
Rancho Seco Nuclear Generating Station - Issuance of Amendment RE: License Termination Plan (TAC No. J52668). Washington, DC; November 27, 2007.
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APPENDIX A FIGURES Rancho Seco Nuclear Generating Station 1695-SR-04-DRAFT
N JL.
NOT TO SCALE Figure A-i: Location of Rancho Seco Nuclear Generating Station, Herald, California Rancho Seco Nuclear Generating Station A-1 1695-SR-04-DRAFT
SPRAY PONDS ISFSI COOLI CHLORINE BUILDING WATER TREATMENT PLANT SEWAGE TREATMENT AREA,
, TURBINE BUILDING
-FUEL STORAGE BUILDING
, REACTOR BUILDING BUILDING T & R BUILDING N
NOT TO SCALE Figure A-2: Plot Plan of the Industrial Area at Rancho Seco Nuclear Generating Station cho Seco Nuclear Generating Station A-2 1
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N MEASUREMENT/SAMPLE LOCATION
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- SINGLE POINT - LOWER WALLS NOT TO SCALE Figure A-3: Survey Unit F8130731, Auxiliary Building, Room 51, Section 3 Wall -
Direct Measurement and Sampling Locations Rancho Seco Nuclear Generating Station A-3 1695-SR-04-DRAVTf
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NOT TO SCALE Figure A-4: Survey Unit F8131211, Auxiliary Building, Room 132 -
Direct Measurement and Sampling Locations Rancho Seco Nuclear Generating Station A-4 1695-SR-04-DRAFT
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FLOOR AND LOWER WALLS SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-5: Survey Unit F8131372, Auxiliary Building, Rooms 208 and 211 -
Direct Measurement and Sample Locations Rancho Sect Nuclear Generating Station A-5 1695-SR-04-DRAFT
ELEVATION LOOKING NORTH AT COL. LINE 9.7 Figure provided by SMIUD.
N MEASUREMENT/SAMPLE LOCATION 0
SINGLE POINT -
FLOOR AND LOWER WALLS NOT TO SCALE Figure A-6: Survey Unit F8131781, Auxiliary Building, Room 319 -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-6 1695-SR-04-DRAFT
Survey Unit F8132133 0' Elev 744 69.1 Survey Unit F8132134 Figure provided by SMUD.
N MEASUREMENT/SAMPLE i
LOCATION
-L SINGLE POINT - FLOOR NOT TO SCALE Figure A-7: Survey Unit F8132133 and F8132134, Auxiliary Steam Support Pads -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-7 1695-SR-04-DRAFT
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17I78$ 17885 1798$ b18OBS 18185 109BS{208BS 207BS 2068SI 2058S1 2048$ý 203BS 128$ 12138$ 2146BS 21585! 216BS1 2178S 21888 18$
18 8
7 11 Ni 174BS 1 21085 2 2118S 2 S3485 2 za i
33BS 2328S 2318SI 2308S 229MBS 2288S 227BSI 2358S 2360S I 237BS 238B8 2398Si 240B8 254BSý 253B' 2418S 242BS 2528S 2518S 2028 2018S 20085, 21985ý 2208S 22185ý 22885 2258S 2248S, 24365 2448S 24585'
'2498 24885 u) 270851 2878$;
29285 30985 3106 3118Sj 3168ý 31884 ý4 J
2588S 257BS I 2568S 25585 2598S 2608SF 261BS 2628SI 2638Si 2648SI 2658S 2668W 2788S, 277BS 12768$, 275BS 2798S 280BS 30085 2998S 3018$ 30285 324BS 323BS 28185 28285 29885 ý29785S 30385; 3046S 3228$I 32185 2748¶
-S27385 28385' 2848W 29685 2958S 3208.
3198M 272BS 271B8 2858S 2868B5 2948S 2936S 307BS 30880 318BS 31780 Figure provided by SMUD.
MEASUREMENT/SAMPLE LOCATION N
0 SINGLE POINT -
NOT TO SCALE FLOOR AND LOWER WALLS Figure A-8: Survey Unit F8260010, Turbine Building, North Condensate Pit Area -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-8 1695-SR-04-DRAF'T
0i~~Q Figure provided by SMUD.
MEASUREMENT/SAMPLE LOCATION N
- SINGLE POINT -
NOT TO SCALE FLOOR AND LOWER WALLS Figure A-9: Survey Unit F8260004, Turbine Building, Condensate Pump Pit -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-9 1695-SR-04-DRAFT
Figure provided by SMUD.
N MEASUREMENT/SAMPLE I
LOCATION SINGLE POINT -
FLOOR AND LOWER WALLS NOT TO SCALE Figure A-1O: Survey Unit F8260011, Turbine Building, Lube Oil Pit -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-10 1695-SR-04-DRAE-T
o 00 fo o:
Figure provided by SMUD.
N MEASUREMENT/SAMPLE LOCATION SINGLE POINT - FLOOR NOT TO SCALE Figure A-11: Survey Unit F8260171, Turbine Building, North Central Floor -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-11 1695-SR-04-DRAF'T
.1 Figure provided by SMIJD.
N MEASUREMENT/SAMPLEI LOCATION SINGLE POINT - FLOOR NOT TO SCALE Figure A-12: Survey Unit F8260151, South Turbine Building -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-12 1695-SR-04-DILAFF
70785 to Swl~t Cokas a
64BS
?'53S~
East Cowrimn Looking East South Cokoun Looking South G'01 w~aps to right $4do
.1 Nonh Coham
,Map F8261004.12) 2 Stan Grid raps to left goo Wt Was Cokmih (Map Rt2ftttD4.121 Figure provided by SMUD.
MEASUREMENT/SAMPLE N
LOCATION 0
SINGLE POINT - LOWER WALLS C,
A SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-13: Survey Units F8261003 and F8261004, High Pressure Turbine Pedestals -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-13 1695-SR-04-DRAFT
D i
D
~i
_7 w
w I
vided by SMUD.
N MEASUREMENT/SAMPLE LOCATION 0
SINGLE POINT - FLOOR NOT TO SCALE Figure pro' irvey Unit F8121001, Fuel Storage Building +40' Elevation -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-14 1695-SR-04-DRAF'r
Figure provided by SMUD.
N MEASUREMENT/SAMPLE LOCATION L
0 SINGLE POINT - FLOOR NOT TO SCALE Figure A-15: Survey Unit F8120005, Spent Fuel Pool Floor -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-15 1695-SR-04-DRAFT
3
_jý__,5BD{
- 12BD 23
--A --
ý-' -------------------
4!..
2ý zrv I----
038 w
- 4...............................
F
-I 0BD l--
_22BD_____
___________ 2BD_______(-_
w
-=i
_1 It
---- I-t-
--1 l--
5B D-
- 1 8BD:
45BD
__ __ __ BDSB 6--
L ----
ilF r_-1
~-1----
-~
t I
Figure provided by SMUD.
N MEASUREMENT/SAMPLE LOCATION J
A SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-16: Survey Unit F8120003, Spent Fuel Pool, East Wall -
Direct Measurement and Sample Locations Generating Station A-16 Rancho Seco Nuclear 1695-SR-04-DRAFT
Height in meters
-i LA 3 I a
& IL.
L.0.... If C I
- in**~
p*1~ 'I CUt.'"
II )LJ."....
II I *1J I
Linees 8.79 m 6.17 m 3.55 m 10 0.93m 1
4AJ L41
'H I ýJ It l ------
--- i r---
l L
-j -
El. 40' 0" Bend Lines Qlt. 15_
0"
=
tsuy;ýtý wzbu UbUftttz%!ftý 3r" 19BD 860 7BDQ _
660
-~----------
E r"i E~
E E
E E
- o I I F-L q" Q" El -~tj~"
Figure provided by SMUD.
MEASUREMENT/SAMPLE N
LOCATION JL 0
SINGLE POINT - LOWER WALLS
- SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-17: Survey Unit F8120001, Spent Fuel Pool, West Wall -
Direct Measurement and Sample Locations Generating Station A-17 Rancho Seco Nuclear 1695-SR-04-DRAI-T
Figure provided by SMUD.
N MEASUREMENT/SAMPLE LOCATION
- SINGLE POINT - LOWER WALLS NOT TO SCALE Figure A-18: Survey Unit F8120004, Spent Fuel Pool, North Wall -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-18 1695-SR-04-DRAI-T
g.V 3.6 m 1.05M Figure provided by SMUD.
MEASUREMENT/SAMPLE N
LOCATION SINGLE POINT - LOWER WALLS A
SINGLE POINT - UPPER SURFACES A
NOT TO SCALE Figure A-19: Survey Unit F8120121, Fuel Storage Building, West Exterior Wall -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-19 1695-SR-04-DRAF'T
Figure provided by SMUD.
N MEASUREMENT/SAMPLE I
LOCATION
- SINGLE POINT - FLOOR NOT TO SCALE Figure A-20: Survey Unit F8000104, Pump Alley Access Corridor -
Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-20 1695-SR-04-DRAFT
Figure provided by SMUD.
N MEASUREMENT LOCATION I
- SINGLE POINT - FLOOR NOT TO SCALE Figure A-21: Survey Unit F8340011, Industrial Area Railway -
Direct Measurement Locations Rancho Seco Nuclear Generating Station A-21 1695-SR-04-DRAFT
APPENDIX B TABLES Rancho Seco Nuclear Generating Station 1695-SR-04-DRAFT7
TABLE B - 1:
DERIVED CONCENTRATION GUIDELINE LEVELS AND ELEVATED MEASUREMENT COMPARISONS FOR SURVEYED AREAS RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA BSurvey Unit/
Building/Roomn' Class Gross Beta DCGLb (dpm/100 cm 2)
Design DCGLEMCc (dpm/100 cm 2) /Area Factor F8130731, Auxiliary.
43,000 154,800/3.6 Building, Room 51
.F81.3121 1, Auxiliary 2
43,000 Class 2d/NA Building, Room 132 F8131371, Auxiliary Building Rooms 208 1
43,000 154,800/17.11 and 211 Floor F8131372, Aiixiliary Building Rooms 208 and 211 Walls and Ceiling FuidingAuRgom1 43,000 167,700/3.9 Building, Room 319 F8132133, Auxiliary 1
43,000 215,900/5.02 Steam Support F8132134, Auxiliary 1
43,000 3,551,800/82.6 Steam Support 3,03,580/2.
F8260Q10, Turbine Building, North 1
43,000 154,800/3.6 Condensate Area F8260004, Turbine Building, Condensate 1
43,000 154,800/3.6 Pump Pit F826001 1,Turbine, Building, Lube Oil Pit 1
43,000 154,800/3.6 F8260171, Turbine Building, North 1
43,000 563,500/13.1 Central Floor F8260151, Turbine Building, Grade Level 1
43,000 640,700/14.9 South Rancho Seco Nuclear Generating Station B-1 1695-SR-04-D3RAFT
RANCH SE, NULA GEEATN SAIO HERLD CALIFORNIA a -U.
- Il.
f Survey Unit/
Gross Beta DCGLb Design DCGEmcC' Building/Rooma Class (dpm/100 cm 2)
(dpm/100 CmT)/Area Factor.
F8261003 and F8261004, Turbine Building High Pressure Turbine Pedestals 1
43,000 163,400/3.8 F8121001, Spent Fuel.
1 43,000 154,800/3.6 Building +40 F8120005, Spent Fuel Poo F
oo 43,000 154,800/3.6 Pool, Floor F8120003, Spent Fuel 1
.43,000 154,800/3.6 Pool East Wall F8120001, Spent Fuel 1
43,000 154,800/3.5 Pool West Wall F8120002, Spent Fuel 1
43,000 154,800/3.6 Pool South Wall F8120004, Spent Fuel 1
43,000 154,367/3.6 Pool North Wall F8120121 West 1
43,000 154,800/3.6 Exterior Wall F8000105 Pump 2
NA' NA Alley Access Corridor F8340601' Industrial NA NA Area Railway NA_
1 1
'Refer to Figures A-3 through A-21.
bGross beta DCGL accounts for radionuclide fractions and hard to detects as specified in the DTBD-05-15 (SMUD 2006b).
cDCGLi-ýoc provided by SMUD and accounted for area factors (also provided by SMUD) determined for each specific survey unit.
dClass 2 Survey Unit, DCGLEMC not applicable.
.cThe original survey unit (18132132) was a Class 2 area; however, based on FSS findings, a 2-meter portion was classified as Class 1 resulting in a high DCGLEMc value. Final SMUD scan data did not exceed 31,000 dpm/100 cm 2.
qNA -= Not applicable; survey units were considered land areas and DCGL's were in pCi/g. Pump Alley Access Corridor DCGL and DCGLIt~ic were 51.2 and 97.8 pCi/g, respectively. Industrial Area Railway DCGL and DCGLEmc were 51.2 and 154.28 pCi/g, respectively.
Rancho Seco Nuclear Generating Station B-2 1695-SR-04-DRAFTr
TAL B
2:
Percent Scan Coverage
.Building Survey Unit/Rooma I
Class Auxiliary Building F8130731 Room NAb/75 NA 75 c
51Reactor Wall F8131211 Room 132 2
100/---
75 75 F8131212 Room 132 1
100/---
100 75 F8131371 Rooms 208 an.d21F~o'1 100/NA 75 NA NA and 211 Floor F8131372 Rooms 208 and 211 Walls/Ceiling F8131781 Room 319 1
100/---
75 75 10 F8131791 Room 320 2
100/---
75 75 F8132133 Auxiliary 1
100/NA 75 NA NA Steam Supports F8132134 Auxiliary, 1
100/NA 100 NA NA Steam Supports Turbine Building F8260010 North Condensate Pit 1
F8260004 Condensate 1
100/---
75 75 Pump Pit F8260011 Lube Oil Pit 1
100/---
90 75 F8260032 Main Feed NA PmAra2 100/---
75 25 N
Pump Area F8260171 North Central For1 100/NA 100 NA NA Floor F8260151 Grade Level 1South 100/NA 100 NA NA F8261003 and F8261004 High Pressure Turbine 1
NA/---
NA 75 5
Pedestals Rancho Seco Nuclear Generating Station B-3 1695-SR-04-DR-AFT
RACOSC NULA GEEAIN STAIO HERLD CALIFORNIA Percent Scan Coverage I
Building Survey Unit/Rooma Class Turbine Building - continued F8260161 N orth Turbine 1 0 -
0
,Building 0' Elevation Fuel Storage Building F8121001 +40 Level For1 100/---
75 NA NA Floor
,;F8121003 +40 Level 1
NA/---
NA 75 NA Lower Walls F8120005 Spent Fuel For1 100/NA 75 NA NA Floor F8120003 East Wall 1
NA/75 NA 60 3
F8120001 West Wall 1
NA/100 NA 75 5
F8120002 South Wall 1
NA/75 NA F8120004 North Wall 1
NA/---
NA 10 F8120121 West Exterior 1
NA/---
NA 75 Wall Exterior Areas F8000104 Pump Alley 1
100/NA 90 NA NA Access Corridor F8340011 Industrial Area Railway 1
100/NA
.5 NA NA
'Refer to Figures A-3 through A-21.
bNot Applicable.
cScans not performed.
Rancho Seco Nuclear Generating Station B-4 1695-SR-04-DRAFFr
LSurvey
-iti ieaAn.
Unit/
Surfaceb
- Activity I
- Location, (dpm/100 cm)2),
Alpha F8130731, Auxilia Building, Room 51 1LW 48,000 0
3 NO/YES 2
LW 19,000 0
4 YES/YES 1
FL 2,800 0
1
[
YES/NA 2
LW 15,00_0 2
15 YES/NA F8131371,.Au.xlary,Buildingi;Rooms 208 and 211,-;:
1 FL 6,600 0
1 YES/YES 2
FL 720 0
-1 YES/YES 3
FL 420 0
4 YES/YES 4
FL 760 0
-1 YES/YES F8131372, Auxiliar B uld g R ooms 208:and *211Pý....
5 LW 13,000 2
74 YES/NAe 6
LW 280 2
-2 YES/NA 7
LW 17 0
-3 YES/NA 8
US 630 2
6 YES/NA 9
US 640 0
-1 YES/NA 10 US 1,000 0
9 YES/NA 11 US 210 0
-3 YES/NA F8131781,,AuxaryBuildig, Room 319 '______
1 LW 39,000 0
10 YES/YES 2
LW 4,700 0
-1 YES/YES 3
LW 36 0
-1 YES/YES 4
FL 6,300 2
6 YES/YES 5
FL 22,000 0
-2 YES/YES 6
FL 22,000 2
6 YES/YES F8132133, Au'iliar' Building. Steam Support 1
FL 1,700 0
2 YES/YES F81321-34, Auxlary Building 2ooteam ropport 1
FL 12,000 0
5 T
YES/YES Rancho Seco Nuclear Generating Station B-5 1695-SR-04-DRAFTr
1 FL 22,000 1
0
-4 YES/YES 2
FL 3,200 0
-3 YES/YES 3
LW 8,800 0
1 YES/YES i.*j0*° ieBj*ig odest
.~i 1_
1_FL 5,700 0
2 YES/YES 2
LW_
6,500 0
3 YES/YES 3
FL 280 0
-4 YES/YES F8260011,.Tu."rb6"i-*
-.iii.din, Lvb&
-il Pit,--,
1 FL 9,900
'0
-2 YES/YES 2
FL 6,000 0
1 YES/YES 3
LW 360.
0
-2 YES/YES 1
FL_
4,300 0
J
-5
[
YE/YE 1
FL 4,400 22YE/S 1
US
-88 0
-3 YES/YES 2
US 9
0 1
YES/YES 3
US 40 0
-3 YES/YES 4,
LW 2,400 0
3 YES/YES 1
FL 5;400 0
3 YES/YES 2
FL 6,400 0
3 YES/YES 3
FL 16,000 0
-4 YES/YES 4
FL 17,000 0
6 YES/YES 5
FL 7,900 2
-1 YES/YES Rancho Seco Nuclear Generating Station B-6 1695-SR-04-DRAFT
TAL B-3 SUFCACIIYLVL RANCHO SEC NUCLEA GENERATIN STAT~uae n~
uw ~~~u rION HERLD CAIORI Survey Total Beta Unit/
Surfaceb Activity Locationa (dpm/100 cm2)c Removable Activity (dpm/100 cm 2)
Alpha Beta Activity Meets Gross -Betad DCGL/DCGLEMc d F8120005, Spent Fuel Pool Floor.
1 FL 20,000 0
-2 YES/YES 2
FL 13,000 0
2 YES/YES 3
FL 17,000 6
7 YES/YES 4
FL 7,200 0
-3 YES/YES F8120003, Spent Fuel Pool East Wall 1
US 1,300,000 2
48 NO/YES 2
US 27,000 0
17 YES/YES 3
US 27,000 0
5 YES/YES 4
US 590,000 0
48 NO/YES 5
US 53,000 0
10 NO/YES F8120001, Spent Fuel Pool West Wall 1
LW 140,000 0
6 NO/YES 2
LW 32,000 0
-4 YES/YES 3
US 220,000 0
18 NO/YES 4
US 200,000 2
14 NO/YES 5,
US 98,000 0
3 NO/YES 6
US 51,000 0
8 NO/YES 7
US 240,000 0
59 NO/YES F8120004, pent Fuel Pool North Wall 1
LW 43,000 2
31 NO/YES 2
LW 130,000 2
130 NO/YES 3
LW 170,000 2
190 NO/YES 4
LW 76,000 0
19 NO/YES 5
LW 5,700 2
13 YES/YES F8120121, Fuel Storage Building, West Exterior Wall 1
LW 1
19,000 1
0
-1 YES/YES 2
1 US 1
-170 0
1 3
I YES/YES Rancho Seco Nuclear Generating Station B-7 1695-SR-04-DRAFT
TAL B
-p3 HERLD CALIFORNIA Survey I I Total Beta I
Rernovable Act~ivy IAcit Mes Unit/
Location' Surfaceb Activity (dpm/100 cm2)C (dpm/100 cm 2)
Alpha
, I Beta Gross Beta DCGL/DCGL-MCd I
h I "
F8000105, Pump Alley Access Corridor i,__._..._....
1 FL 650 0
-2 NA 2
FL 600 0
1 NA 3
FL 690 0
-2 NA 4
FL 43 0
1 NA F8340011, Industrial Area Railway 1
FL T 120
-NA 2
FL
-40 NA 3
FL 88 NA aRefer to Figures A-3 through A-21.
bStructural surfaces; FL = floor, LW = lower wall, and US = upper surfaces.
cDirect measurement results rounded to two significant digits.
dDCGL values are provided in Table B-1. All surface activity measurements that were greater than the gross beta DCGL were less than the design DCGLEMCS determined for each specific survey unit based on the area factors for the survey unit.
eNot Applicable.
fMeasurement not performed.
Rancho Seco Nuclear Generating Station B-8 1695-SR-04-DRAFT
APPENDIX C MAJOR INSTRUMENTATION Rancho Seco Nuclear Generating Station 1695-SR-04-DRAFT
APPENDIX C MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.
SCANNING INSTRUMENT/DETECTOR COMBINATIONS Beta Ludlum Floor Monitor Model 239-1 combined with Ludlum Ratemeter-Scaler Model 2221 coupled to Ludlum Gas Proportional Detector Model 43-37, Physical Area: 550 cm 2 (Ludlum Measurements, Inc., Sweetwater, TX)
'Ludlum Ratemeter-Scaler Model 2221 coupled to Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm 2 (Ludlum Measurements, Inc., Sweetwater, TX)
Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to Eberline Geiger-Mueller Detector Model HP-260, Physical Area: 20 cm2 (Eberline, Santa Fe, NM)
Gamma Ludlum Pulse Ratemeter Model 12 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to Fluke MiomedicalNaI(Tl) Scintillation Detector Model 489-55, Crystal: 3.2 cm x 3.8 cm (Fluke Biomedical, Cleveland, OH)
DIRECT MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS Beta Ludlum Ratemeter-Scaler Model 2221 coupled to Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm 2 (Ludlum Measurements, Inc., Sweetwater, TX)
Rancho Seco Nuclear Generating Station C-1 1695-SR-04-DRAFT
DIRECT MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS (CONTINUED)
Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to 2
Eberline Geiger-Mueller Detector Model HP-260, Physical Area: 20 cm (Eberline, Santa Fe, NM)
LABORATORY ANALYTICAL INSTRUMENTATION Low Background Gas Proportional Counter Model LB-5100-W (Tennelec/Canberra, Meriden, CT)
Rancho Seco Nuclear Generating Station C-2 1695-SR-04-DRAFT
APPENDIX D SURVEY AND ANALYTICAL PROCEDURES Rancho Seco Nuclear Generating Station 1695-SR-04-DR-AFT
APPENDIX D SURVEY AND ANALYTICAL PROCEDURES PROJECT HEALTH AND SAFETY The proposed survey and sampling procedures were evaluated to ensure that any hazards inherent to the procedures themselves were addressed in current job hazard analyses (JHA). All survey and laboratory activities were conducted in accordance with ORISE health and safety and radiation protection procedures.
Pre-survey activities included the evaluation and identification of potential health and safety issues.
Survey work was performed per the ORISE generic health and safety plans and a site-specific integrated safety management (ISM) pre-job hazard checklist. SMUD also provided site-specific safety awareness training.
CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards/sources, traceable to the National Institute of Standards and Technology (NIST).
Analytical. and field survey activities were conducted in accordance with proc-edures from the following ORAU and ORISE documents:
- Survey Procedures Manual (May 2008)
-Laboratory Procedures Manual (December 2008)
- Quality Program Manual (November 2007)
The procedures contained in these manuals were developed to meet the requirements of 10 CFR 830 Subpart A, Quality Assurance Requirements, Department of Energy Order 414.1C Quality Assurance, and the U.S. Nuclear Regulatory Commission Quality Assurance Manualfor the Office of Nuclear Material Safety and Safeguards and contain measures to assess processes during their performance.
Quality control procedures include:
Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
Rancho Seco Nuclear Generating Station D-1 1695-SR-04-DRAF'17
" Participation in MAPEP, NRIP, and ITP Laboratory Quality Assurance Programs.
" Training and certification of all individuals performing procedures.
" Periodic internal and external audits.
CALIBRATION PROCEDURES Detectors used for assessing surface activity were calibrated in accordance with ISO-7503' recommendations. The total beta efficiency (F.o.,
was determined for the instrument/detector combination used for all surface activity measurements and consisted of the product of the 27E instrument efficiency (e) and surface efficiency (s,):
8rotal = F, x E,. The total surface efficiency was determined based on a beta energy multi-point calibration, development of instrument efficiency to beta energy calibration curves, and the calculation of the weighted efficiency representing the primary contaminants of concern (Cs-137 and Co-60) for the RSNGS site. SMUD calculated the radionucide mix fraction of Cs-137 to Co-60 as 0.87 and 0.13, respectively (SMUD 2006b).
Carbon-14 (C-14), technetium-99 (Tc-99), thaUium-204 (TI-204), and strontium/yttrium-90 (Sr/Y-90) were selected as the beta calibration sources to represent the energy distribution of the detectable beta-emitters at the RSNGS. The 27 interpolated F' factors for the detectable beta-emitters ranged from 0.34 to 0.67 for the gas proportional detectors (Figures D-1 through D-3) and were 0.09 to 0.66 for the GM detector (Figure D-4). ISO-7503 recommends an F, of 0.25 for beta emitters with a maximum energy of less than 0.4 MeV and an F, of 0.5 for maximum beta energies greater than 0.4 MeV. The ORISE calculated multi-point calibration total weighted static 8t,.
values for the hand-held gas proportional detectors used for the confirmatory surveys were 0.23 and 0.24 as presented in Figures D-1 through D-3; the ORISE calculated multi-point calibration total weighted static Ftot* value for the GM detector used for the confirmatory surveys was 0.18 as presented in Figure D-4.
International Standard. ISO 7503-1, Evaluation of Surface Contamination - Part 1: Beta-emitters (maximum beta energy greater than 0.15 MeV) and alpha-emitters. August 1, 1988.
Rancho Seco Nuclear Generating Station D-2 1695-SR-04-DRAFr
SURVEY PROCEDURES Action Levels The field action level for the hand-held gas proportional instrument based on the specific site criteria and background was calculated as follows:
0 SMUD Site Release Criteria (SRC): 43,000 dpm/100 cm 2 43-68 multipoint total efficiency (P....D: 0.24 0
Background (BKG): 250cpm Time (T): 1 minute count time
- G geometry Physical Detector Area cm2 100.
Determine Action Level Action Level (cpm) = (SRC
- e,..,
- G *I) ÷ (BKG
- T)
Action Level = 13,253 cpm In a similar calculation, the action level for the GM detector was determined to be 1,602 counts per minute (cpm). A field count at or above the calculated action level value indicates that further investigation of the area would be necessary.
Surface Scans Structural surface scans were performed by passing the detectors slowly over the surface; the distance between the detector and the surface was maintained at a minimum-nominally about 1 cm. Building surfaces were scanned using a floor monitor (550 cm 2), a small area (126 cm 2) hand-held gas proportional, and/or a GM pancake (20 cm 2) detector. A Nal scintillation detector was used to scan for elevated gamma radiation throughout the SUs. Identification of elevated radiation levels was based on increases in the audible signal from the recording and/or indicating instrument.
Specific scan minimum detectable concentrations (MDC) for the Nal scintillation detector for Cs-137 and Co-60 in concrete were not specifically determined as the instrument was used solely as Rancho Seco Nuclear Generating Station D-3 1695-SR-04-DRAFT
a qualitative means to identify elevated gamma activity where further investigation would be required. MDCs for radionuclides in the concrete would approximate those contained in NUREG-1507.
Beta surface scan MDCs were estimated using the calculational approach described in NUREG-1507.2 The scan MDC is a function of many variables, including the background level.
Additional parameters selected.for the calculation of scan MDCs included a one-second observation interval, a specified level of performance at the first scanning stage of 9 5% true positive rate and 25% false positive rate, which yields a d'value of 2.32 (NUREG-1507, Table 6.1), and a surveyor efficiency of 0.5. The scanning,,otal was determined for the hand-held gas proportional, GM and floor monitor detectors in the same fashion as above for the static hand-held gas proportional and GM detectors except typical scanning efficiencies for the detectors were used rather than specific calibrations for this survey. The scanning 8,to, value for a hand-held gas proportional detector was 0.18 (Figure D-5); 0.03 for a GM detector (Figure D-6); and, 0.15 for a floor monitor (Figure D-7).
To illustrate an example for a hand-held gas proportional detector using a concrete background of 560 cpm, the minimum detectable count rate (MDCR) and scan MDC can be calculated using the following relationships:
si = d'(b)1 / 2 ;
MDCR = si * (60/i); and MDCRsurveyor = MDCR/(P)1/2 Where:
Si the minimum detectable number of source counts d'
the specified level of performance of 2.32 bi the number of background counts in the observation interval MDCR = minimum detectable count rate i
observation interval p
surveyor efficiency of 0.5 2NUREG-1 507. Minimum Detectable Concentrations With Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, US Nuclear Regulatory Commission. Washington, DC; June 1998..
Rancho Seco Nuclear Generating Station D-4 1695-SR-04-DRAF-
The equations are combined and the variables are then calculated as follows:
bi = (250 cpm)(1 s)(1 min/60 s) = 4.17 counts, MDCR = (2.32)(4.17 counts)1/2 [(60 s/min)/(1 s)] = 284 cpm, MDCRs....yor = 284/(0.5)
= 402 cpm The scan MDC is calculated assuming a total efficiency (otO,) of 0.18:
AMDCRsu yor 2
ScanMDC =dpm
/ l cm For the given background, the estimated scan MDC was 2,228 dpm/100 cm 2 for the hand-held gas proportional detector. In the same manner, the scan MDCs for the GM and floor monitor detectors were 5,822 and 6,367 dpm/100 cm2, respectively (Refer to Figures D-5 through D-7).
Surface Activity Measurements Measurements of total beta surface activity levels were performed using hand-held hand-held gas proportional and GM detectors coupled to portable ratemeter-scalers. Count rates which were integrated over one minute with the detector held in a static position, were converted to activity levels (dpm/100 cm 2) by dividing the count rate by the total static efficiency (&ixz) and correcting for the physical area of the detector. ORISE did not determine construction material-specific backgrounds for each surface type encountered for determining net count rates.
Instead, ORISE took the conservative approach and did not subtract material specific backgrounds indetermining surface activity levels.
The MDC for surface activity measurements was calculated using the following equation:
MDC =3 + (4.65*jB)
T*
Ttl *G Where:
B
= background (total counts) in time interval, T T
= count time (min) used for field instruments To-Taal = total efficiency = Ei x Es Rancho Seco Nuclear Generating Station D-5 1695-SR-04-DR-AFT
zi
= instrument efficiency
= source efficiency G = geometry (physical detector area cm 2/100)
The beta static MDC for the gas proportional detector was 258 dpm/100 cm 2 using the total efficiency of 0.24 and an instrument background of 250 cpm (Figure D-1). The physical surface area assessed by the gas proportional detector used was 126 cm 2. The beta static MDC for the GM detector was 1,019 dpm/100 cm 2 using the total efficiency of 0.18 and an instrument background of 54 cpm (Figure D-4). The physical surface area assessed by the GM detector used was 20 cm2.
Removable Activity Measurements Smear samples for removable gross alpha and gross beta contamination were obtained from biased direct measurement locations based on surface activity measurement results. Removable activity samples were collected using numbered filter paper disks, 47 mm in diameter. Moderate pressure was applied to the smear and approximately 100 cm 2 of the surface was wiped. Smears were placed in labeled envelopes with the location and other pertinent information recorded.
RADIOLOGICAL ANALYSIS Gross Alpha/Beta Smears were counted on a low-background gas proportional system for gross alpha and beta activity.
The MDCs of the procedure were 11 dpm/100 cm 2 and 14 dpm/100 cm 2 for a 2-minute count time for gross alpha and gross beta, respectively.
DETECTION LIMITS Detection limits, referred to as minimum detectable concentrations, were based on 3 plus 4.65 times the standard deviation of the background count [3 + (4.65 (BKG)1 / 2)]. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
Rancho Seco Nuclear Generating Station D-6 1695-SR-04-DRAFT
Task MNttbev.
1695 SITE: Rancho Seco I
Data Instrument:
2221 #6 Detector:
43-68 #6 (0.8 mg/en0 Window)
Site BKG Avg (epm)i 250 Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)'
Energy (keV)1 Efficiency C-14 49.47 156.5 0.36 Tc-99 84.6 293.5 0.39 TI-204 244.03 763.4 0.57 St/Y-902 564.75 1413.05 0.64 43-68 Instrument Efficiency (0.8 mg/cm2 window)
U C.2 tw SE aS 0.70 0.60 0.50 0.40 0.30 0.20 0.10 0.00
_012381n(x) - 0 13431-R' = 0.9745 L-..-.*
=0.
1 369tn(x) - 0.3528 0
200 400 600 800 Beta Energy (keV) 1000 1200 1400 1600 I
Average Maximum Log (Average)
Log. (Mamum) I Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV)1 Energy (keV)1 Fraction3 Efficiencyi Efficiency Cs-137 187 550 0.87 0.51 0.50 0.22 Co-60 96 318 0.13 0-43 0.25 0.01 Toad lE'cieaac:
0.24 Saea MDC (dpmI/
cm 1):
258 thttp:
mvonewal.tgdovi sda+/-2/dcl s*eatb.*ti.
- Avreage and mom Sr! Y-90 beta enegies calanuated by adding the avezage and
ýmazo' enecpos of both radwowlides,
,epctiveIl. and dmdmg by tso Fracthon based on data pcovided by SMUD 4 Cielated %ung e1pooentil rtW
.e shown above f aveage beta ener-y Figure D-1: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #6 Rancho Seco Nuclear Generating Station D-7 1695-SR-04-DRAF-f
Task Numuber.
1695 SITE: Rancho Seco I DEty:
Instnrnentl 2221 #15 Detector:
43-68 #15 (0.8 mg/cmn wrndow)
Site BKG Avg (cpmx)I 271 Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)1 Energy (keV)1 Efficiency C-14 49.47 156.5 0.36 TC-99 84.6 293.5 0.40 TI-204 244.03 763.4 0.58 Sa/Y-902 564.75 1413.05 0.67 43-68 Instrument Efficiency (0.8 mgfcm2 window)
Ca ES 0.80 0.70 060 0.50 0.40 0.30 0.20 0.10 0.00 0
200 400 600 amO 1000 1200 1400 Beta Energy (key) 1600 1
Average U
Marnum Log.(Average)
Log. (
) I Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV)9 Energy (keV)'
Fraction3 Efficency4 Efficiency Efficiency Cs-137 187 550 0.87 0.53 0.50 0.23 Co-60 96 318 0.13 0.44 0.25 0.01 TotalE'ciiec.=
0.24 I
Six tic MDC (dpw/lo cm ) :
258 b Itt:, wwwm,rdc.bni~o'rwlatd2 cd*sueb.sp, Are.oi
=Wa inn St !Y.90 bmt naqpm.. eanls2t~d by.dding dl. to~
rwar md z
a.a..og of both,adxoondidas metwesdit~r and dwmalag by ftwo 3 FnctOO bsi~d on data gpv,&ds by SMULD Caltad aawg otofW s
sho -
abow for xrnt bo.a bo Figure D-2: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #15 Rancho Seco Nuclear Generating Station D-8 1695-SR-04-DRAF-'T
Task Number:
1695 SITEs Rancho SecoE I
Data Entry Instrument:
21#
Detector 43-68 #5 (0.8 mg/cm2 window)
Site BKG Avg (cpm):
232 Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)
Energy (keV)'
Efficiency C-14 49.47 156.5 0.34 Tc-99 84.6 293.5 0.39 Ti-204 244.03 763.4 0.53 Sr/Y-902 564.75 1413.05 0.60 43-68 Instrument Efficiency (0.8 mg/cm 2 window) 0.70 y = 0.1 1051n(x) - 0.0924 0.60 C 0.50 0.4 0
,,=
U.1.x 0
[
0.30 0.20 0.10 0.00 0
200 400 600 800 1000 1200 1400 1600 Beta Energy (WeV)
Average U Ma-u Log- (Average)
-Log (M-rmum)
Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionucide Energy (keV)1 Energy (keV)'
Fraction 3 Efficiency 4 Efficiency Efficiency Cs-137 187 550 0.87 0.49 050 0.21 Co-60 96 318 0.13 0-41 0.25 0.01 ToWESciency:
0.23 Static MDC (dpm/ZOVcm 2) 259 Shttp:i !ww.nnzcrdv.b,,dgovi ndt/dc..sezcb*.,sp
-Average and usxm Sx, Y-90 beta eougws caklc.,ked by adduxg the svexap and masum'u weneegws of both sadowanaLdas-sespecttaly. end dmdwng by two Fracn*o based on daft piov.ed bT SMUT) 4 Ca*lated msing exponentWa come show above fw werge baet eneqy Figure D-3: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #5 Rancho Seco Nuclear Generating Station D-9 1695-SR-04-DRAFT
Task Number:
1695 SITE: Rancho Seco I Dati E Instrument:
Detector:
Cal. BKG Avg (cpm):
[2221 #2 HP260 #
Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)1 Energy (keV)'
Efficiency C-14 49.47 156.5 0.09 Tc-99 84.6 293.5 0.29 T1-204 244.03 763.4 0.40 Sr/Y-90 2 564.75 1413.05 0.66 HP-260 Instrument Efficiency 0.7 y = 0.21331n(x) - 0.7155 R2 0.9527 I
0.6 0.5 S0.4
- 0.3 0.2 0.1 0
0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)
Average 0
Maximum Log. (Average)
Log. (Maximum)
Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy(keV)t Energy (keV)'
Fraction3 Efficiency4 Efficiency Efficiency Cs-137 187 550 0.87 0.40 0.50 0.17 Co-60 96 318 0.13 0.26 0.25 0.01 Total HE~cien cr.
0.18 Static MDC (dpm/1OO cm2) :
1.019 I http://www.*u.dc.biil.gov /nudht2/dec-wmseatchi.isp 2 Average and maximuma Sr/Y-90 beta energies calculated by adding the average and maximum eneigies of botb radionuclides. xespectively, and dividing by two 3 Fraction based on data provided by SMUD 4 Calculated using exponential curve shown above fox average beta energy Figure D-4: Multipoint Hand-Held Geiger-Mueller Detector Static MDC - Instrument #2 Rancho Seco Nuclear Generating Station D-10
! 695-SR-04-DRAFT
Task Number:
Instrument:
Detector:
Cal. BKG Avg (cpm):
1695 SITE: Rancho Seco Data Entrv 43-8 j
(0- Bmg/m2 window) oP =
1 sec Suvevor Eff.
0.5 b =
4.2 counts MDCR =
=
402 cpm Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)l Energy (keV)1 Efficiency 2 C-14 49.74 156.5 0.28 Tc-99 84.6 293.5 0.30 T1-204 244.03 763.4 0.46 S-/Y-90' 564.75 141105 0-46 43-68 Instrument Efficiency (0.8 mg/cm2 window) 0.60 Y = 0.0854in(x) - 0.055t R = 0.8855 0.50 y 7 07;971n(,) - 0.2124ý 0.40 R- 0.9D02 0.30 E
0.20 0.10 0.00 0
200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)
Average U
Maxmum Log. (Average) -----
Log. (Maximum)
Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclde Energys(keY)
Energy-(ke)3 Fraction Effieien1y3 Efficiency Efficiency Cs-137 18E r
550 0E87 0.39 0.50
- 0. 17 Co-60 96 318 0.13 0.33 0.25 0.01 ZoWENciency.
0.18 Seao MDC (da,/10o c
-2):
212M htr7, /,s-'..sde.bod~goi / n~d t2/ dee_.seewh.sp SDe-oom as,.o g Health Phyans, Table 9.3 tAraoce and maxumsm S/*Y-90 beta enege eailated byh adding the aveage and maimnm w
eaepngs of both riidoaohides. mespecti'e]., and di-dmg by two Pracon based o data ptro.ded by SIMLD CUkWlted nstag eaponeoatnd ron' shoan abo-v foe arae befta ýargy Figure D-5: Multipoint Hand-Held Gas Proportional Detector Scan MDC - Instrument #6 Rancho Seco Nuclear Generating Station D-11 1695-SR-04-D3RAFTr
Task Number:
Instrument:
Detector:
Cal. BKG Avg (cpm):
1695 SITE: Rancho Seco 2221 HP'#2 HP-26002 54 Date Entry Oi =
I see Surveyor
=
0.5 b.=
,=
187 cpm Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)l Energy (keV)l Efficienc 2 C-14 49.74 156.5 0.03 Tc-99 84.6 293.5 0.05 Ti-204 244.03 763.4 0.08 S,/Y-903 564.75 1413.05 0.09 43-68 Instrument Efficiency (0.8 mg/cm2 window)
C
.3 0.10 0.09 0.08 0.07 0.06 0.05 0.04 0.03 0.02 0.01 0.00 0
200 400 600 800 1000 1200 1400 Beta Energy (keV) 1600 i
0 Average U
Maximum Log. (Average)
-Log-(Maximum) i Radlonnelilde Mix Caleuhftion Average Beta Maximumn Beta Instrument Surface Weighted Radionuclide Energy (keV)1 Energy (keV)I Fraction 4 Efficiencys Efficiency Efficiency Cs-137 187 550 0.87 0.07 0_50 0.03 Co-60 96 318 0.13 0.05 0.25 0.00 ToWENcieac:7.
0.03
,Scan MDC (dpm/1L) cm 2 ):
5,822 htp:.,w.*odo.baljgoI ooda*C, d,-sw.e.biIsp
":l:)
H~~~smaI&
Pba**.m. Tabi. 9,1 Av',ip.od wana-sý. S/Y-90 bet. eogm ctaIo-ated bym.ddxog tha.,'.aag. and omua.onaz.gan of both =.dionodnidt. -pakevy, and dik.dog by tro 4 Fe-enoo bahd on data p-oorAd by SMULD s Csk,.awd.og woitW e-abovh fto.Wg bft. -Vr Figure D-6: Multipoint Hand-Held Geiger-Mueller Detector Scan MDC - Instrument #2 Rancho Seco Nuclear Generating Station D-12 1695-SR-04-DRLAFT
Task Number:
Instrument:
Detector:
Cal. BKG Avg (cpm):
1695 SITE: Rancho Seco 2221 FM#2 43-37 #9 (0-8 mig/cmn2-window) 1450 Data Entry o0=
I sec Surveyo Eff =
0,5-bi =
24.2 counts MA4R=
684 cpm XIDCR.u~rs 968 cpm Calibration Data Average Beta Maximum Beta Instrument Radionucide Energy (keV)1 Energy (keV)I Efficiency2 C-14 49.74 156.5 0.18 Tc-99 84.6 293.5 0.24 T1-204 244.03 763.4 0.39 SrX'Y-90ý 564.75 1413.05 0.42 43-37 Instrument Efficiency (0.8 mg/cm2 window)
C UA E
w 0.50 0.45 0.40 0.35 0-30 0.25 0.20 0.15 0.10 0.05 0.00 y = 01 1671n(x) - 0.411 I
R2 = 0.9731 I
4 W
[-Ty.031n(,)-0:2~
0 200 400 600 800 Beta Energy (keY) 1000 1200 1400 1600 Average N
Maxunm Log. (Average)
Radionuclide Mix Calculation Log. (Maxum)
I Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV)'
Energy (keV)l Fraction 4 Efficien Efficiency E
Cs-137 187 550 0.87 0.33 0.50 0.14 Co-60 96 318 0,13 0-26 0.25 0.01 TooJENciency 0.15
$can MDC (dpm/JO0 cm'):
6,367 hbtp I /www.nnde.bo1l.go a/xist2/dctac_seachilap
'Decommsaoning Health Phymie. Table 9.2 Avenge and maxlmumn SUiY-90 beta eoegmea caknated by adding the aerage and mrnimrn enrexpge of both radionulides, tespectirel, and diiding by two 4 Faction based on data provided by SIMUD 4Cailuvated iunng exponeiati cnrv shown above for average beta merge Figure D-7: Multipoint Floor Monitor Gas Proportional Detector Scan MDC - Instrument #2/#9 Rancho Seco Nuclear Generating Station D-13 1695-SR-04-DRAVF