ML091470103

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Confirmatory Survey Report for September and October 2008 at the Rancho Seco Nuclear Generation Station by Oak Ridge Institute for Science and Education (Orise)
ML091470103
Person / Time
Site: Rancho Seco
Issue date: 05/07/2009
From: Adams W
Oak Ridge Institute for Science & Education
To: John Hickman
NRC/FSME
References
1695-SR-04-0, RFTA 06-003
Download: ML091470103 (69)
v • d • e


Text

0Ri S ]E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION May 7, 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, MD 20852

SUBJECT:

CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA DCN 1695-SR-04-0 (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)i 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 GeneratingStation 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 final report, incorporating NRC comments on the draft report dated March 18, 2009, thai 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.

Sincerely, f Wade C. Adams ORISE Health Physicist/Project Leader Survey Projects WCA:km Enclosure T. Carter, NRC/FSME/DWMEP/DD/SPT-8F5 E. Abelquist, ORISE T. Patterson, NRC/FSME/TWFN 8A23 S. Roberts, ORISE T. Youngblood, NRC/FSME/DWMEP/TWFN 8 F5 T. Vitkus, ORISE R.'Evans, NRC/Region IV File 1695 P. .Bo17 oice:.865.576.0065 Fax: 865.241.3497 E-mail: Wade.AdamS@orau.org Oa Rig, N373

CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED INSEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA

~JRil Oak Ridge Institute for Science and Education

The Oak Ridge Institute for Science and Education (ORISE) is a U.S. Department of Energy facility focusing on scientific initiatives to research health risks from occupational hazards, assess environmental cleanup, respond to radiation medical emergencies, support national security and emergency preparedness, and educate the next generation of scientists. ORISE is managed by Oak Ridge Associated Universities. Established in 1946, ORAU is a consortium of 100 colleges and universities.

NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government. Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S.

Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Prepared by W. C. Adams U

ORISE Prepared for the U.S. Nuclear Regulatory Commission FINAL REPORT May 2009 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 by the 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-04-0

CONFIRMATORY SURVEY REPORT FOR ACTIVITIES PERFORMED IN SEPTEMBER AND OCTOBER 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Prepared by: Date: -

W. C. Adams, Project Leader, Independent Environmental Assessment and Verification Reviewed by: Date: 60.

Assessment and Verification Reviewed by: 9 E . OC-C9 ý R." D. Condra, Laboratory Manager Date:

Independent Environmental Assessment and Verification Reviewed by: Date:

A. T. Payne, Quality Mafager Independent Environmental Assessment and Verification+

Reviewed by: Date:

S. J. Roberts, Associate nirec s n d fa Independent Environmental Assessment and Verification Rancho SecoNuclear Gencratng Stafi6n 1695-SR-04-0

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-04-0

TABLE OF CONTENTS PAGE List of Figures ..................................................................................................................................................... ii List of Tables ...................................................................................................................................................... iv A bbreviations and A cronym s........................................................................................................................... v Introduction and Site History .......................................................................................................................... 1 Site D escription .................................................................................................................................................. 2 O bjective ............................................................................................................................................................. 2 D ocum ent Review ....................................................................................................................................... . 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 ................................................ 7.................................................................................... 6 D ocum ent Review ......................................................................................................................................... 6 Surface Scans .................................................................................................................................................. 6 Surface Activity 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 1695-SR-04-0

LIST OF FIGURES PAGE Figure A-I: 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: Survey Unit F8130731, Auxiliary Building, Room 51, Section 3 Wall - Direct M easurem ent and Sam pling Locations ...................................................................................................... A -3 Figure A-4: Survey Unit F8131211, Auxiliary Building, Room 132 -Direct Measurement and Sam p ling 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 L ocations ......................................................................................................... A -5 Figure A-6: Survey Unit F8131781, Auxiliary Building, Room 319 - Direct Measurement and S amp 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 L ocations ......................................................................................................... A -8 Figure A-9: Survey Unit F8260004, Turbine Building, Condensate Pump Pit - Direct M easurem ent and Sam ple L ocations ......................................................................................................... A -9 Figure A-10: Survey Unit F8260011, Turbine Building, Lube Oil Pit - Direct Measurement and Samp le Lo 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 -11 Figure A-12: Survey Unit F8260151, South Turbine Building - Direct Measurement and Sam ple L o catio n s ................................................................................................................................ A -12 Figure A-13: Survey Units F8261003 and F8261004, High Pressure Turbine Pedestals -

Direct M easurem ent and Sam ple Locations ........................................................................................... A -13 Figure A-14: Survey Unit F8121001, Fuel Storage Building +40' Elevation - Direct Measurem ent and Sam ple Locations ....................................................................................................... A -14 Figure A-15: Survey Unit F8120005, Spent Fuel Pool Floor - Direct Measurement and S am ple L o catio n s ........................................................................................................................................ A -15 Figure A-16: Survey Unit F8120003, Spent Fuel Pool, East Wall - Direct Measurement and Sam p le L o catio n s ................................................................................................................................ A -16 Figure A-17: Survey Unit F8120001, Spent Fuel Pool, West Wall - Direct Measurement and Sam p le L o catio n s ................................................................................................................................ A -17 Figure A-18: Survey Unit F8120004, Spent Fuel Pool, North Wall - Direct Measurement and Sam p le L o catio n s ................................................................................................................................ A -18 Rancho Sect Nuclear Generating Station ii 1695-SR-04-0

LIST OF FIGURES (continued)

PAGE Figure A-19: Survey Unit F8120121, Fuel Storage Building, West Exterior Wall - Direct M easurem ent and Sam ple Locations ....................................................................................................... A -19 Figure A-20: Survey Unit F8000104, Pump Alley Access Corridor - Direct Measurement and Sam p le L o catio n s ........................................................................................................................................ A -2 0 Figure A-21: Survey Unit F8340011, Industrial Area Railway - Direct Measurement L o catio n s ...................................................................................................................................................... A -2 1 Rancho Seco Nuclear Generating Station iii 1695-SR-04-0

LIST OF TABLES PAGE Table 1: ORISE Confirmatory Survey Areas ........................................................................................... 4 Table B-I: Derived Concentration Guideline Levels and Elevated Measurement Comparisons fo r Su rv eyed A reas ......................................................................................................................................... B -1 Table B-2: Survey Unit Classification and Scan Coverage ............................... B-3 Table B -3: Surface A ctivity Levels ............................................................................................................... B -5 Rancho Seco Nuclear Generating Station iv 1695-SR-04-0

ABBREVIATIONS AND ACRONYMS bi number of background counts in the interval d' index of sensitivity S. instrument efficiency surface efficiency etotal total efficiency BKG background cm centimeter 2

cm square centimeter Co-60 cobalt-60 COC contaminants of concern cpm counts per minute Cs-137 cesium-137 CsI(T1) cesium iodide (thallium-activated)

DCGL derived concentration guideline level DCGLMC DCGL elevated measurement comparison DP decommissioning plan dpm/100 cm 2 disintegrations per minute per 100 square centimeters DQOs data quality objectives DTBD decommissioning technical basis document FSS final status survey FSSP final status survey plan FSSR final status survey report GM Geiger-Mueller IEAV Independent Environmental Assessment and Verification ISFSI independent spent fuel storage installation ISM Integrated Safety Management ITP Intercomparison Testing Program JHA job hazard analysis keV kiloelectron volts LTP license termination plan mg milligram MAPEP Mixed Analyte Performance Evaluation Program MARSSIM Multi-Agency Radiation Survey and Site Assessment Manual MDC minimum detectable concentration MDCR minimum detectable count rate MeV million electron volts mrem/yr millirem per year msl mean sea level MWe megawatt electric NaI(T1) sodium iodide (thallium-activated)

NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission NRIP NIST Radiochemistry Intercomparison Program ORAU Oak Ridge Associated Universities Rancho Seco Nuclear Generating Station V 1695-SR-04-0

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 T1 -204 thallium-204 Rancho Seco Nuclear Generating Station vi 1695-SR-04-0

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-04-0

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.

Rancho Seco Nuclear Generating Station 2 1695-SR-04-0

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-Ageny Radiation Survey and Site Investigation Manual (MARSSIM) considerations (ORISE 2007a, SMUD 2006a and NRC 2000).

CONFIRMATORY SURVEY PROCEDURES To 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 survey 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:

Rancho Seco Nuclear Generating Station 3 1695-SR-04-0

TALE1

  • 5IS 0 FIMTOYSUR AES I J II Building/Area Surveyed Areas 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(T1)]

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.

Rancho Seco Nuclear Generating Station 4 1695-SR-04-0

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 acceptable 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 oh 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 mildirem per year (mrem/yr) total effective dose equivalent (TEDE) as presented in Section 6 of the LTP (SMUD 2006a and NRC 2007). The Rancho Seco Nuclear Generating Station 5 1695-SR-04-0

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 1695-SR-04-0

specific design DCGL elevated measurement comparison (DCGLEMc) 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 cm 2, 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 cm 2. Removable gross alpha activity for the concrete surfaces of the Pump Alley Access Corridor was 0 dpm/100 cm 2; 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 DCGLIMc values which are also provided in Table B-1. The fourteen confirmatory survey results that exceeded the structural surface DCGLs were less than 1 M2 . All confirmatory direct surface activity measurements on the structural surfaces in the evaluated SUs were within the site-specific SU DCGLFMc 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 1695-SR-04-0

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 i 2

) 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 DCGLFMc 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/100 cm 2 .

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.

Rancho Seco Nuclear Generating Station 169S-SR-04-0

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 [Docket 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-Ageng Radiation Survey and Site Investigation 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.

Rancho Seco Nuclear Generating Station 9 1695-SR-04-0

APPENDIX A FIGURES Rancho Seco Nuclear Generating Station 1695-SR-04-0

CAL.IF()RN IA N

NOT TO SCALE Figure A-i: Location of Rancho Seco Nuclear Generating Station, Herald, California Rancho Seco Nuclear Generating Station A-1 1695-SR-04-0

SPRAY PONDS 7

BUILDING

ý0 ISFSI CHLORINE BUILDING WATER TREATMENT PLANT AREE; SEWAGE TREATMENT AUXILIAR)

BUILDING n

ESWITCTHYAR:D BUILDING T & R BUILDING AL NOT TO SCALE Figure A-2: Plot Plan of the Industrial Area at Rancho Seco Nuclear Generating Station Rancho Seco Nuclear Generating Station A-2 1695-SR-04-0

D (T(Th rD"C- Ž¸- + -7 x

L~ _

J-Ea7 Wl,7)

West Wa I 'okr RX Wall East Wall S"-.

Figure provided by SMUD.

MEASUREMENT/SAMPLE LOCATION -L 0 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-04-0

044

-E) i (E--) -IK--- -- - ~~1 E (D E

-7_

0/ 9 _5(-1(;2 I

tE) rSm N

QOGjD000 e\T @i) @D@)TT 7ý)(i)eD( D Sý Figure provided by SMUD.

N MEASUREMENT/SAMPLEI LOCATION -L

  1. SINGLE POINT -

FLOOR AND LOWER WALLS 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-04-0

ý I 'I

. II U[ioqg RECC ' (Ii. I 8

1I 7i '0 cC*(2 ý c).

C)

)

wLJ

~  ;~~ -- 4.

CAlkrq Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION

    1. SINGLE POINT -

FLOOR AND LOWER WALLS A 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 Seco Nuclear Generating Station A-5 1695-SR-04-0

PLAN VIEW LEE. *'c,- :"

ELEVATION LOOKING NORTH

.- COL L'IE 9.7 Figure provided by SMUD.

MEASUREMENT/SAMPLE LOCATION

  1. 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-04-0

0' Elev Floor 2

744 ft 2

69.1 m Survey Unit F8132134 1

~1 55--

45 -

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  • N- Floor 10 -

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MEASUREMENT/SAMPLE LOCATION

  1. 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 1(9A-SR-04-0

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MEASUREMENT/SAMPLE LOCATION _

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-04-0

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-04-0

H lBS 29s 10BS g9a 1BS 1BS iBS 118S 12BS l3ES l4SNo 15ot Pump 208S 196S 18 1178 168S 2185 225S 2385 24B5 2585 H 3085 2955 2855 2703 Iij K J*(..

North Wal 3188 3255 3358 3453 3553 of Trwndh 7 4055 3953 3853

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-South Walt of Trench 4188 42BS 4355 4485 45BS 2

S 43Bs 48 4718 466S olPump' 0 A 4s Platform, SBS 52AS 53S 5485 5501 6088 5958 5853 5788 %a8s 618S H H Figure provided by SMUD.

N MEASUREMENT/SAMPLE 1 LOCATION JL

  1. SINGLE POINT -

FLOOR AND LOWER WALLS NOT TO SCALE Figure A-10: Survey Unit F8260011, Turbine Building, Lube Oil Pit -

Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-10 1695-SR-04-0

0 00 (D C)

Figure provided by SMUD.

N MEASUREMENT/SAMPLE i LOCATION 0 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-04-0

Figure provided by SMUD.

N MEASUREMENT/SAMPLE ,

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-04-0

5 "48 111M. VhM 0,' 44W',1 43as! 195

-up oa 0' E49 SOS gasI.,.

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Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION I

  1. SINGLE POINT - LOWER WALLS 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-1 3 1(Q95-cR-04.-0

i~j.I i~121 3~*

11~fl 4

I~ -

Mi AD Figure provided by SMUD.

N MEASUREMENT/SAMPLE1 LOCATION

  • SINGLE POINT - FLOOR NOT TO SCALE Figure A-14: Survey Unit F8121001, Fuel Storage Building +40' Elevation -

Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-14 1695-SR-04-0

Cl~stanee In meters from Norm Wall 50 7 85 rn 4196 mn 2 05M Distance in mnelera fron)

South 'Nal Figure provided by SMUD.

MEASUREMENT/SAMPLE I LOCATION 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-04-0

ý-25BD.

2!..... BO......

2.... .0. .

.....iiiii29iii~

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! I... .I . 1.

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I----- ----- 980 BD- ------------- --- 780

__. .. .. .. .. .. .. .. I I - ---------------- - I ----- ____

S3i ____4BD0 58D - _____ 0680 Ii

r-* I

-- m Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION A SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-16: Survey Unit F8120003, Spent Fuel Pool, East Wall -

Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-16 1695-SR-04-0

R, 410'O" Lines El. 15, U EL.0' 0' Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION I JL 0 SINGLE POINT - LOWER WALLS A SINGLE POINT - UPPER SURFACES NOT TO SCALE Figure A-17: Survey Unit F8120001, Spent Fuel Pool, West Wall -

Direct Measurement and Sample Locations Rancho Seco Nuclear Generating Station A-17 1695-SR-04-0

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-04-0

05 280 _ .06 rr 01t 3 3 2 33 3 3 3 Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION AL

  1. SINGLE POINT - LOWER WALLS A SINGLE POINT - UPPER SURFACES 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-04-0

Figure provided by SMUD.

N MEASUREMENT/SAMPLE LOCATION J

  1. 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-04-0

Figure provided by SMUD.

N MEASUREMENT LOCATION 1

  1. 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-04-0

APPENDIX B TABLES Rancho Seco Nuclear Generating Station 1695-SR-04-0

DESurvey Unit!ONC TI Gross Beta DCGLb Design DCGLEAC Liass Building/Rooma (dpm/100 cm 2) (dpm/100 cm 2)/Area Factor F8130731, Auxiliary 1 43,000 154,800/3.6 Building, Room 51 F8131211, Auxiliary 2 43,000 Class 2d/NA Building, Room 132 F8131371, Auxiliary Building Rooms 208 1 43,000 154,800/3.6 and 211 Floor F8131372, Auxiliary Building Rooms 208 2 43,000 Class 2d/NA and 211 Walls and Ceiling F8131781, Auxiliary 1 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 3,551,800e/82.6 Steam Support F8260010, 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 1 43,000 154,800/3.6 Building, Lube Oil Pit 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 1(69;-S'R-04.-n

TAL B -31 RANCH SC NUCEA GEEATN STTO HERLD CALIORNI SurveyUnit! Gross Beta DCGL b Design DGGLEmC Building/Room' ls (dpm/100 cm) '(dpm/,100 cm 2)/A~rea Factor F8261003 and F8261004, Turbine Building High 1 43,000 163,400/3.8 Pressure Turbine Pedestals F8121001, Spent Fuel 1 43,000 154,800/3.6 Building +40 F8120005, Spent Fuel 1 -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 43,000 154,800/3.6 Pool North Wall F8120121 West 1 43,000 Exterior Wall F8000105 Pump 2 NA' NA Alley Access Corridor F8340011 Industrial NA NA Area Railway

-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).

cDCGLIFMC 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.

eThe original survey unit (F8132132) 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 DCGLrmc 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-04-0

TABLE B - 2:

SURVEY UNIT CLASSIFICATION AND SCAN COVERAGE RANCHO SECO NUCLEAR GENERATING STATION L HERALD, CALIFORNIA I

Building, Class Survey Unit/Rooma I Auxiliary Building F8130731 Room NAb/75 NA 75 51Reactor. Wall-F8131211 Room 132 2 100/--- 75 75 F8131212 Room 132 1 100/--- 100 75 ---

F8131371 Rooms 208 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 ---

F8132133Sta1upot Auxiliary - 100/NA 75 NA NA Steam Supports F8132134 Auxiliary 1 100/NA 100 NA NA' Steam Supports Turbine Building F8260010 North 1 100/--- 90 75 Condensate Pit F8260004 Condensate 1 100/--- 75 75 Pump Pit*

F8260011 Lube Oil Pit 1 100/--- 90 75 ---

F8260032 Mairi Feed.

Pump Aai 2 100/--- 75 25 Pump Area NA F8260171 North Central 1 100/NA 100 NA NA Floor F8260151 Grade Level 1 100/NA 100 NA NA South F8261003 and F8261004 High Pressure Turbine 1 NA/--- NA 75 5 Pedestals Rancho Seco Nuclear Generating Station B-3 1695-SR-04-0

TAL BS2 I IISUVE L'lUNhITIKCLASIFICAIO [SCAN61W~ AN CUIOVERAGE HERLD CALIFORNI I I I I . -ercent Building Survey Unit/Room' Class I

Turbine Building - continued F8260161 North Turbine .

Building 0' Elevation 1 T 100/--- 100 ......

Fuel Storage Building "_.. _ ... ,,__._,

F8121001 +40 Level Floor 1 100/--- 75 NA NA F8121003 +40 Level NA/--- NA 75 NA

  • Lower Walls F8120005 Spent Fuel 1lo 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 T 100/NA 90 NA NA Access Corridor 1 ____ __ NA 4A F8340011 Industrial Area 1 100/NA 5 NA NA Railway _ _ _ _ _ _

'Refer to Figures A-3 through A-21.

bNot Applicable.

ýScans not performed.

Rancho Seco Nuclear Generating Station B-4 1695-SR-04-0

1 48,00 ooo o 3 NO/YES 2 LW 19,000 0 J 4 YES/YES' 1 FL _ _2,800 _ _0 1__ YES/NAc 2 LW 15,000 2 15 YES/NA Fý84343~1, AM ja BuI Ros2

-5 m,=n208 idt 2441_______________

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 5 LW 13,000 2 74 YES/NA 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 1 LW 39,000 0 10 YES/YES 2 LW 4,700 0 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 i ] FL 1,700 0 _ 2 YES/YES 1 l FL 12,000 0 5 YES/YES Rancho Seco Nuclear Generating Station B-5 1695-SR-04-0

a Surfaceb -AICfivity--

'ftiine-'Biiilding, N6 ",C6ndims ,at 1 1 22,000 0 1 -4 1 YES/YES 2 [ FL 3,200 0 -3 YES/YES 3_ LW "8,800 0 1 YES/YES 1 FL 5,700 0 2 YES/YES 2

_ LW 6,500 0 3 YES/YES 3 FL 280 0 -4 YES/YES F826001!; TurbineBuilding, Lube Oil Pit _ _ _______._____ __:_.__________

1 FL 9,900 0 -2 YES/YES 2 FL 6,000 0 1 YES/YES 3 LW 360 0 -2 YES/YES

, F826017,. ,Turbine ýBuilding, North Centr' Floor-1 FL 4,300 0-5 YE S/YES F8,26611 ubn ulig iaeLvlS~t 1 FL 4,400 2 2 YES/YES F826.100,3.anF 0* jHigh ý_-__Pressu____e___._T___rbie___t__,.

-8261004, -. .

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 F2101;- hFuelýStrage Bidn 4 _______ -

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-04-0

I~TAL - B 3:~~1 Survey Sl"otal, beta (dp'emovaole icUVmty Activity.Meets i*

,:(dpm/100 cm 2 )

Unit/ Surfaceb i Activity Gross Beta .

Locationa (dpm/100 cm 2)e Alpha Beta DCGL/DCGLEMCd 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, Spent 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 19,000 0 -1 YES/YES 2 US -170 0 3 YES/YES Rancho Seco Nuclear Generating Station BR-7 165;-1,R-04-0

RACH 0CNUCEA GEEATN STTO Survey II Ttal Beta I - Removable Activity I Atvt et Unit/ Surfaceb -,Activity (dpm/100 cm 2) Gross Beta Location' (dpm/100 cm 2) Alpha j Beta' DCGL/DCGLEMC0 F8000105, Pump Alley Access Corridor ._....._ _

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 120 -- -- NA 2 FL -40 NA 3 FL 88 ... NA

-Refer 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.

'Not Applicable.

fFor the Spent Fuel Pool Walls, with the exception of location #1 on the East Wall, all direct measurement locations were less than 500 cm 2 which calculates to an Area Factor of 28.1 and DCGLE,,Ic of - 1,210,000 dpm/100 cm 2. Location #1 on the East Wall had a measurement area of less than 300 cm 2 which calculates to an Area Factor of 47.1 and a DCGLE,,mc of- 2,000,000 dpm/100 cm 2.

gMeasurement not performed.

Rancho Seco Nuclear Generating Station B-8 1695-SR-04-0

APPENDIX C MAJOR INSTRUMENTATION Rancho Seco Nuclear Generating Station 1695-SR-04-0

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 2 Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm (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 Miomedical NaI(T1) 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 2

Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm (Ludlum Measurements, Inc., Sweetwater, TX)

Rancho Seco Nuclear Generating Station C-1 1695-SR-04-0

DIRECT MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS (CONTINUED)

Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to Eberline Geiger-Mueller Detector Model HP-260, Physical Area: 20 cm 2 (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-04-0

APPENDIX D SURVEY AND ANALYTICAL PROCEDURES Rancho Seco Nuclear Generating Station 1695-SR-04-0

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 GHA). 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 procedures 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, Qualiy Assurance Requirements, Department of Energy Order 414.1 C Qualihy Assurance, and the U.S. Nuclear Regulatory Commission Qualioy Assurance Manualforthe Office of NuclearMaterial Safeo 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-04-0

" 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 (*tota) was determined for the instrument/detector combination used for all surface activity measurements and consisted of the product of the 27r instrument efficiency (F) and surface efficiency (F5): E, = 9 X 8s. 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 radionuclide 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), thallium-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. Theý 2i interpolated sj 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 , of 0.25 for beta emitters with a maximum energy of less than 0.4 MeV and an E, of 0.5 for maximum beta energies greater than 0.4 MeV. The ORISE calculated multi-point calibration total weighted static

&,ota, 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 Etc, 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 1699-SR-04-0

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:

SMUD Site Release Criteria (SRC): 43,000 dpm/100 cm 2 43-68 multipoint total efficiency (, totaD: 0.24 Background (BKG): 250cpm Time (T): 1 minute count time

  • G = geometry- Physical Detector Area cm 100 Determine Action Level
  • Action Level (cpm) = (SRC
  • eto,
  • G
  • T) + (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-04-0

a qualitative means to identify elevated gamma activity where further investigation would be required. MDCs for radionucides.in the concrete would approximate those contained in NUREG-1507.

Beta surface scanMDCs 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 95% 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 etotal 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 Eto*l 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'(bD)1/2 MDCR = si * (60/i); and 1/ 2 MDCRsu...yor =MDCR/(P)

Where:

s5 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 2

NUREG-1507. 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-04-0

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)V'A [(60 s/min)/(1 s)] = 284 cpm, MDCRs,,eyor = 284/(0.5)= 402 cpm The scan MDC is calculated assuming a total efficiency (EtotaD of 0.18:

ScanDC = l)CRsuveyor dpm / 100 cm2 (total)

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 cm 2 , 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 (Ei x6) 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 in determining surface activity levels.

The MDC for surface activity measurements was calculated using the following equation:

)-B-

+ (4.65 S=B3 T

  • Total G Where:

B = background (total counts) in time interval, T T = count time (min) used for field instruments aToI = total efficiency = xi x F, Rancho Seco Nuclear Generating Station D-5 1695-SR-04-0

Fi = instrument efficiency F, = 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 cm 2 .

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)"/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 169S-SR-04-0

Task Number- 1695 SITE: Rancho Seco I Data Entry Instrument: 2221 #6 Detector: 43-68 #6 (0.8 mg/cm 2 window)

Site BKG Avg (cpm): 250 Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV) Energy (keV) Effciency C-14 49.47 156.5 0.36 Tc-99 84.6 293.5 0.39 TI-204 244.03 763-4 0.57 Sr/Y-90 2 564.75 1413.05 0.64 43-68 Instrument Efficiency (0.8 mg/cm 2 window) 0.70 ___Ty-7-0 ý12381n(x)ý01 - 343ý 1 R' = 0.9745 0.60 C 0.50 y = 0. 13691n(x) - 0.3528 0.40 0.30 E

0.20 0.10 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keY)

I* Average 0 Maxmum - Log- (Average) - Log. (Maximum) I Radionuclide Mvix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV)' Energy (keY)t Fraction 3 Efficiency4 Efficiency 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 Totz]Eficieacr: 0-24 2

StaticMDC (dpm/llO cm ): 258 Shttp:/ia-.-a nde blgov./ndat2/dec.._sathrbiap Avt'eagp and o ,m= Sx/Y-90 beta eneqes calilated by adding the awVage and oraýaool eoerpes of both tadionnchdes, xespectweky, and dmdig by two 3Pcactro based on data provrded by SM.UD 4Cak.ated *snrg exponentrWi one thoam abo-e fo- -Viagebeta energy Figure D-1: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #6 Rancho Seco Nuclear Generating Station D-7 1695-SR-04-0

Task Ntumber- 1695 SITE: Rancho Seco I Data Entry Instrument: 2221 #15 Detector: 43-68 #15 (0.8 mg/cm 2 window)

Site BKG Avg (cpm). 271 Calibration Data Average Beta MI'aximum Beta Instrument Radionuclide Energy (keV)' 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 Sr/Y-902 564.75 1413.05 0.67 43-68 Instrument Efficiency (0.8 mglcm 2 window) 0.80 y 0 134ixx -0.1 4

8 0.70 0.60 0.50 y= R-n.-

0.40 E 0.30 2 0.20 A

0.10 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (KeW)

I Average M Maximum - Log (Average) - Log. (Maximum) I Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV) Energy (keV)' Fraction 3 Efficiency 4 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 Totl AEBciencr.- 0.24 Sttic MDC (dpm/IO cm 2 ) : 258 http://ý.nnde.bnigovi/.dt2/dee_s*ebpLIsp A-ee and o.aomý S/Y-90 beta eepgs cal-kluted by addiog the axmtge -od ama.a ensg~s of both eadioow,,id- , eýspmetyvy.,a.d dmidmg by tav 3

PFttio based on data pro-dod by SMUD CFieolated .peatip Mulag coi nthoan abo- foem eng berm e r cu n Figure D-2: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #15 Rancho Seco Nuclear Generating Station D-8 169S-SR-04-0

Task Nwnmber: 1695 SITE: Rancho Seco I Data F,ý Instrument: 2221 #5 Detector- 43-68 #5 (0.8 mg/cm2 window)

Site BKG Avg (cpm). 232 Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV)1 Energy (keV)l 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-90 2 564.75 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 Pq i .50 y= 0-12261n(x)-O0.291 C0.50 i 0.40 0.30 E

0.20 0.10 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)

S Average U Mamum Log. (Average) - Log. (Maximum) ]

Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keV)I Energy (keV)1 Fraction 3 Efficiency4 Efficiency Efficiency Cs-137 187 550 0.87 0.49 0.50 0.21 Co-60 96 318 0.13 0.41 0.25 0,01 rot,11Efficienc3r.- 0.23 Static MDC (dpm/O0 cm 2.): 259 1'.ttp:/--&*sdoo b.Lgo-/andat2/dec s-ch.sp Are.ag and ammosoa S./Y-90 bft. en.gws eaklcated by adding the a.x-ago and maua e-gis of both -a&.od1d-s, oopotavely, and dmding by týo Fractoo based 00 data prvided by SMUD 4 Cakrlaterd listg expononial an- shaown aboe fo avexage beta energr Figure D-3: Multipoint Hand-Held Gas Proportional Detector Static MDC - Instrument #5 Rancho Seco Nuclear Generating Station D-9 1695-SR-04-0

Task Number: 1695 SITE: Rancho Seco I Data En Instrument: 221 #2 Detector: HP260 #2 Cal. BKG Avg (cpm): 54i Calibration Data Average Beta Maximum Beta Instrument Radionucide Energy (key) Energy (keV) Efficiency C-14 49.47 156.5 0.09 Tc-99 84.6 293.5 0.29 Tl-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 R1 0.9527 **

i 0.6 .........- -- --

S0.5 t 0.4 S0.3 E

0.2 0.1 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keC)

  • Average U Maximum -Log. (Average) -Log. (Maximum)

Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted 3 4 Radionuclide Energy (keY)' Energy (keV)' Fraction Efficiency Efficiency I Efficiency Cs-137 187 550 0.87 0.40 0.30 0.17 Co-60 96 318 0.13 0.26 0.25 0.01 Total Elfciency: 0.18 Static MDC (dpm/1OO cm2): 1.019 http:i/www.nudc.bnl.gov/tndat2/dec seacri.isp 2 Average mid maximum Sr/Y-90 beta energies calculated by adding the average and maximnun energies of both radionuclides, respectively. mid dividing by two Fraction based on data provided by SMWD 4 Calculated using exponential curve shown above for average beta energy Figure D-4: Multipoint Hand-Held Geiger-Mueller Detector Static MDC - Instrument #2 Rancho Seco Nuclear Generating Station D-10 1695-SR-04-0

Task Number: 1695 SITE: Rancho Seco Data Entrv Oi 1 sec Instrument; 2221 #6 Survrvor Eff. = 0.5 -

Detector: 43-68#6 (0.8 mg/cm 2 window) bi = 4.2 counts Cal. BKG Avg (cpm): 250 MDCR = 284 eIM MDCRý.V, = 402 cprn Calibration Data Average Beta Maximum Beta Instrument 1 2 Radionuclide Energy (keV) Energy (keV)1 Efficiency C-14 49.74 156.5 0.28 Tc-99 84.6 293.5 030 TI-204 244.03 763.4 0.46 Sr/Y-90s 564.75 1413.05 0.46 43-68 Instrument Efficiency (0.8 mglcm 2 window) 0.60 -- y = 0.0854[n(x) - 0.05561 R==0.8855L I 0.50

- y 0.09541n(x) - 0.2124 2

2 0.40 R :0.9002 0.30 E 0.20

- 0.10 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)

  • Average a Maximum - Log. (Average) .....- Log. (Maximum)

Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy3(keV)7 Energy7(keNT Fraction4 Efficiencys Efficiency Efficiency 87 Cs-137 187 550 0. 0.39 0.50 0.17 Co-60 96 318 0.13 0.33 0.25 1 0.01 7'orAl EMciancy: 0.18 Scan MDC (dpm,,/O cm 2): 2,228 Shttp:/i/*l.a**ndc~b aLgý/oti idat2 / deiseardii.i sp Deeoasu nionmg Heafth Phwses, Table 9.3

,As-eg' anadmmuwi - S,/Y-90 beta -egew "dehted by addin the -ge*ra*d nm.

  • -sndm ene~ es of botha diowwlides, mspectively. and dividing by to 4 Foaeoan bas.d on &t2 provxded by SMLD C.a.ilated -g e.ponemal -ose,ho~a abo-e fo- - beta ere-gy Figure D-5: Multipoint Hand-Held Gas Proportional Detector Scan MDC - Instrument #6 Rancho Seci, Nuclear Generating Station D-11 1695-SR-04-0

1695 Data Entry Task Number: SITE: Rancho Seco 0,=I sec Instrument: Survevor Eff. = 0.5 -

Detector: HP-260#2 bi = 0.9 counts Cal. BKG Avg (cpin): MDCR = 132 cpm MDCR_, = 187 cpm Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV) Energy (keV)1 Efficiency 2 C-14 49.74 156.5 0.03 Tc-99 84.6 293.5 0.05 T1-204 244.03 763.4 0.08 S'/Y-903 564.75 1413.05 0.09 43-68 Instrument Efficiency (0.8 mg/cm2 window) 00--y= 0.02451nx) -0.0621I 0.10R2 = 0.9217 0.09 L'

, 0.08 - 0 1093 g 0.07 09 0.05 0.04 20.03

_ 0.02 0.01 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)

  • Average
  • Maximum - Log. (Average) .....- Log. (Maximum)

R ndmnnirl;de Mx C2lri~lat1nfl Average Beta Maximum Beta Instrument Surface Weighted 4 5 Radionucide Energy (keV)1 Energy (keV)1 Fraction Efficiency Efficiency Efficiency Cs-137 187 550 0.87 j 007 0.50 0.03 Co-60 96 318 0.13 0.05 025 0.00 Total Eiffrziency. 0-03 Scan MDC (dpm=/10oc 2): 5,822 http:/ m nndc.bnlgo /t sdat2/ des*--ct.,.sp SDe-o.--oarg He.Ith Ph-,ss Table 9.1 A-etage -od m--a-o, S,/Y-90 beta .eV-es c.1oslated by add-ng the .- erage -od - -a.m'so eoegres of both sespeotly.

-adton,,ohde, -d dridg by tw' 4Fmuoto based o- dat. jp*oided by. SMUD 5Calolated -rgeapo-eot.] asrse sh abo-ee for -e-Vge beta eo.-V Figure D-6: Multipoint Hand-Held Geiger-Mueller Detector Scan MDC - Instrument #2 Rancho Seco Nuclear Generating Station D-12 1695-SR-04-0

Task Number: 1695 SITE: Rancho Seco Data EntLT oi= 1 sec Instrument: Surveyor Eff. = 0.5 -

Detector: 2221 43-37FX1{#2[

  1. 9 (0.8 mg/cm2 window) bi = 24.2 counts Cal. BKG Avg (cpm): 1450 MDCR = 684 cpm MIDCRýý,., = 968 cpm Calibration Data Average Beta Maximum Beta Instrument Radionuclide Energy (keV) Energy (keV)i Efficiency2 C-14 49.74 156.5 0.18 Tc-99 84.6 293.5 0.24 TI-204 244.03 763-4 0.39 Sr/Y-903 564.75 1413-05 0.42 43-37 Instrument Efficiency (0.8 mg/cm 2 window) 0.50 - 02185 0-1031n(x) 0.45 0.40 y = 0.1 1671n(x) - 0.411 0.35 R =0-9731 LU 0.30 09!!O-I 0.25 0.20 E

0.15 0.10 0.05 0.00 0 200 400 600 800 1000 1200 1400 1600 Beta Energy (keV)

.....- Log. (MaximumIn)

I

  • Average m Maximum -Log. (Average)

Radionuclide Mix Calculation Average Beta Maximum Beta Instrument Surface Weighted Radionuclide Energy (keY)t Energy (keV) Fraction4 Efficiencys Efficiency Efficiency Cs-137 187 550 0.87 033 0.50 0-14 Co-60 96 318 0.13 0.26 0.25 0.01 Toad Hfflciency.- 0.15

ýcan MDC (dpm/1WO cm "): 6,367 Ihttp://www.nndebbnLgov/cnxat2/dec.-seaichijsp 2Decommissioning Health Physics, Table 9.2 Average and maxim- m Si/Y-90 beta energies caloilated by adding the average and maximim energies of both radionnlides, respectively, and dividing by two 4Fraction based on data provided by SMUD

" Calvulated nsing exponential ciuve showm above for average beta energy Figure D-7: Multipoint Floor Monitor Gas Proportional Detector Scan MDC - Instrument #2/#9 Rancho Seco Nuclear Generating Station D-13 1695-SR-04-0

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