ML20056H510
| ML20056H510 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/31/1993 |
| From: | Beck W, Landis M, Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | |
| Shared Package | |
| ML20056H484 | List: |
| References | |
| ORISE-93-G-46, NUDOCS 9309090459 | |
| Download: ML20056H510 (89) | |
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l CONFIRMATORY SURVEY. - OFTHE l TURBINE INTERNAL COMPONENTS SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK l T.J.VITKUS I Prepared forthe Division of Low-Level Waste Management and Decommissioning Headquarters Office l U. S. Nuclear Regulatory Commission e s l l ; -- l v i i
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I I ~ I: I l g f I I i Il i The Oak Ridge Institute for Science and Education (ORISE) was established by the U.S. Department of Energy to , undertake national and international programs in science and engineering education, training and management systems, l energy and environment systems, and medical sciences. ORISE and its programs are operated by Oak Ridge Associated Universities (ORAU) through a management and operating contract with the U.S. Department of Energy. Established ; in 1946, ORAU is a consortium of 65 colleges and universities. =' NOTICES i 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, l E apparatus, product, or process disclosed, or represents tat 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 g otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government g 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. I I-
ORISE 93/G-46 CONFIRMATORY SURVEY l OF THE TURBINE INTERNAL COMPONENTS ,g SIIOREHAM NUCLEAR POWER STATION iE BROOKilAVEN, NEW YORK Prepared by T. J. Vitkus
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I l Environmental Survey and Site Assessment Program Energy / Environment System Division Oak Ridge Institute for Science and Education l Oak Ridge, Tennessee 37831-0117 i Prepared for the l Division of Low-Level Waste Management and Decommissioning Headquarters Office U.S. Nuclear Regulatory Commission l l I FINAL REPORT l 1 JULY 1993 I I I l j This report is based on work performed under an Interagency Agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract l number DE-AC-05-760R00033 with the U.S. Department of Energy. I Shoreham Naker Power Siet as June 19.1993
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CONFIRMATORY SURVEY OF TIIE TURBINE INTERNAL COMPOhENTS SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK Prepared by: / Y Date: 7/M[23 T. J. Vitkuf Pfoject Leader / /
, Environmental Survey and Site Assessment Program i
l Reviewed by: / Date: // # W. L. Beck, Aciing Laboratory Manager 7 ' Environmental Survey and Site Assessment Program Reviewed by: e - Date: Jo/% hl. R. Landis, Project Manager ' Environmental Survey and Site Assessment Program f Reviewed by: vvtm Ac4vuL Date: 7/dD)f3 A. T. Payne, Quality Assurancf Officer Environmental Survey and Site Assessment Program . Reviewed by: # M Date: 7 //93 J. J"I. Berger, ProgranfDirector / Ii6vironmental Survey and Site Assessment Program Shareham Nuclear Power Stariaa . Juns 12. 1993
ACKNOWLEDGEMENTS The author would like to acknowledge the significant contributions of the following staff [ members: [ FIELD STAFF D. A. Gibson
, LABORATORY STAFF R. D. Condra
[ J. S. Cox , M. J. Laudeman l l CLERICAL STAFF T. T. Claiborne D. A. Cox M. A. Perry K. E. Waters ILLUSTRATOR E. A. Powell J Shasebass Nincomms W Sessian . Jims 19,1993
1 t TABLE OF CONTENTS i PAGE a l t I List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- . . . . . . . . . . . . . . . i1 l List of Tables ...............................................vi T k Abbreviations and Acronyms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vn l ! Introduction and Site History . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 [ Site Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ; Obj ectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l t I Document Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ? ; 6 l Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 _i i f l Findings and Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 j I Comparison of Resu!ts with Guideline' ,............................. 5 f l S u m mary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 I [ . References ...............................................64 , l Appendices: Appendix A: Major Instrumentation ; Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86 Termination of Operating Licenses for Nuclear Reactors i e l 1 i l O p 1
i LIST OF FIGURES PAGE FIGURE 1: Iacation of the Shoreham Nuclear Power Station . . . . . . . . . . . . . . 7 FIGURE 2: Plot Plan of the Shoreham Nuclear Power Station . . . . . . . . . . . . . . 8 FIGURE 3: Main Turbine - High Fessure Section with Upper i Casmg Removed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 FIGURE 4: Main Turbine, Diaphragm #2G - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 FIGURE 5: Main Turbine, Diaphragm #2T - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 FIGURE 6: Main Turbine, Diaphragm #4G - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 FIGURE 7: Main Turbine, Diaphragm #4T - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 i FIGURE 8: Main Turbine, Diaphragm ,l6G - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 FIGURE 9: Main Turbine, Diaphragm #6T - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 FIGURE 10: Main Turbine, Diaphragm #7G - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 FIGURE 11: Main Turbine, Diaphragm #7T - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 FIGURE 12: Main Turbine, Northeast Diffuser - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 l FIGURE 13: Main Turbine, Southwest Diffuser - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 l FIGURE 14: Main Turbine, Northwest Diffuser - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 FIGURE 15: Main Turbine, Upper Casing Interior, First Inset (East) - l Measurement and Sampling Location ....................21 r l sw u a e ,s ; .s 39. i,93 ii L
LIST OF FIGURES (continued) PAGE FIGURE 16: Main Turbine, Upper Casing Interior, Second Inset (East) - Measurement and Sampling Location ....................22 FIGURE 17: Main Turbine, Upper Casing Interior, Third Inset (East) - Measurement and Sampling Location ....................23 FIGURE 18: Main Turbine, Upper Casing Interior, Fourth Inset (East) - Measurement and Sampling Location ....................24 f FIGURE 19: Main Turbine, Upper Casing Interior, Fifth Inset (East) - Measurement and Sampling Location ....................25 FIGURE 20: Main Turbine, Upper Casing Interior, Sixth Inset (East) - Measurement and Sampling Location ....................26 FIGURE 21: Main Turbine, Upper Casing Interior, Seventh Inset (East) - Measurement and Sampling Location ....................27 FIGURE 22: Main Turbine, Upper Casing Interior, Eighth Inset (East) - Measurement and Sampling Location ....................28 FIGURE 23: Main Turbine, Upper Casing Interior, Tenth Inset (East) - Measurement and Sampling Location ....................29 FIGURE 24: Main Turbine, Upper Casing Interior, First Inset OVest) - Measurement and Sampling Location ....................30 FIGURE 25: Main Turbine, Upper Casing Interior, Second Inset OVest) - Measurement and Sampling Location ....................31 FIGURE 26: Main Turbine, Upper Casing Interior, Third Inset OVest) - l Measurement and Sampling Location ....................32 FIGURE 27: Main Turbine, Upper Casing Interior, Fourth Inset OVest) - Measurement and Sampling Location ....................33 FIGURE 28: Main Turbine, Upper Casing Interior, Fifth Inset OVest) - Measurement and Sampling Location ....................34 FIGURE 29: Main Turbine, Upper Casing Interior, Sixth Inset OVest) - Measurement and Sampling Location ....................35 s m ma.-ro.,swa. 2 i,.i9,s iii
LIST OF FIGURES (continued) PAGE FIGURE 30: Main Turbine, Upper Casing Interior, Seventh Inset OVest) - Measurement and Sampling Location ..................... 36 FIGURE 31: Main Turbine, Upper Casing Interior, Eighth Inset OVest) - Measurement and Sampling Locations . . . . . . . . . . . . . . . . . . . . 37 FIGURE 32: Main Tmbine, Upper Casing Interior, Tenth Inset OVest) - Measurement and Sampling Location ..................... 38 FIGURE 33: Main Turbine, Upper Casing, Steam Inlet - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 FIGURE 34: Main Turbine, First Stage East (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 FIGURE 35: Main Turbine, First Stage East OVest Face) - Measurement and Sampling I4 cation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 FIGURE 36: Main Turbine, Fourth Stage East (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 FIGURE 37: Main Turbine, Fourth Stage East OVest Face) - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 FIGURE 38: Main Turbine, Fifth Stage East (East Face) - Measurement and Sampling I4 cation . . . . . . . . . . .................44 FIGURE 39: Main Turbine, Fifth Stage East OVest Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 FIGURE 40: Main Turbine, Sixth Stage East (East Face) - Measurement and Sampli:ig Iacation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 i FIGURE 41: Main Turbine, Sixth Stage East OVest Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 FIGURE 42: Main Turbine, Seventh Stage East (East Face) - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 FIGURE 43: 14ain Turbine, Seventh Stage East OVest Face) - Measurement i and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 l Shosebman Needmar Power Sesamm . June 19,1993 iV
LIST OF FIGURES (continued) , PAGE FIGURE 44: Main Turbine, Second Stage West (East Face) - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 FIGURE 45: Main Turbine, Second Stage West (West Face) - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 FIGURE 46: Main Turbine, Third Stage East (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 FIGURE 47: Main Turbine, Third Stage West (West Face) - Measurement
, and Sampling Iocation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 FIGURE 48: Main Turbine, Fifth Stage West (West Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 l
( FIGURE 49: Main Turbine, Sixth Stage West (East Face) - Measurement I and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 FIGURE 50: Main Turbine, Sixth Stage West (West Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 FIGURE 51: Main Turbine, Seventh Stage West (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 FIGURE 52: Main Turbine, Seventh Stage West (West Face) - Measurement and Sampling locations ............................58 FIGURE 53: Main Turbine, North Main Steam Piping - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 FIGURE 54: Main Turbine, South Main Steam Piping - Measurement and Sampling location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Shoremma Nuchar Pouw Sairaan . Jm19.1993 V I - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i l l l l LIST OF TABLES PAGE TABLE 1: Surface Acdvity Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61
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Shanbase Nuciant Power sensium. Juss 19,1993 Vi \ - _ _ _ _ . _ _ - - - - _ _ _ _ - _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ _ - _ _ - _ _ _ _ - _ _ _ - . - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .
ABBREVIATIONS AND ACRONYMS ac acre ASME American Society of Mechanical Engineers em2 square centimeter epm counts per minute dpm/100 cm2 disintegrations per minute per 100 square centimeters EML Environmental Measurements Laboratory EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program ha hectare GM Geiger-Mueller km kilometer l LILCO Iong Island Lighting Company LIPA long Island Power Authori+y ; m2 square meter MDA Minimum Detectable Activity mi mile NaI Sodium Iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commist.on i ORISE Oak Ridge Institute for Science and Education QA Quality Assurance , SU Survey Unit l SNPS Shoreham Nuclear Power Station i m u.a , % w .1 1,.i es vii
CONFIRMATORY SURVEY OF THE TURBINE INTERNAL COMPONENTS SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK INTRODUCTION AND SITE HISTORY Shoreham Nuclear Power Station (SNPS), constructed by Long Island Lighting Company (LILCO) was a boiling water reactor, designed to provide a gross electrical output of 849 Megawatts. The plant achieved initial criticality in February 1985; the U.S. Nuclear Regulatory Commission (NRC) license (NRC Docket File No. 50-322) allowed reactor operations at power levels not to exceed 5% of full power. I.ow-power testing in accordance with the license commenced in July 1985 and continued intermittently until January 1989, at which time power generating operations were terminated. The total reactor operatir.3 history was equivalent to 2.03 effective full-power days of fuel exposure. Before reaching design >ower levels, a decision was made to decommission the facility, and the irradiated fue' was subsequently removed from the reactor vessel and placed into the spent fuel pool in August 1989. Various reactor components, piping systems, and other equipment became radiologically contaminated as a result of the reactor low-power testing operations. The primary contaminants which have been identified during characterization studies include iron-55 (Fe-55), cobalt-60 (Co-60), which constituted 97% of the contamination present and smaller quantities of nickel-63, tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152.' The long Island Power Authority (LIPA) was established to decommission the facility and plans to release the site for unrestricted use. The LIPA decommissioning plan was approved for implementation by the NRC in June 1992 and will include decontamination or removal of contaminated portions of the reactor and other plant systems and equipment.' One of the objectives of the decommissioning is to maintain the integrity and salability of structures and process systems, to the extent possible, to enable the future use of the facility in other capacities, such as conventional power generation. The decommissioning will be conducted in several
$hosubasa Nudmar Power Sesssas . Juns 19.1993
phases, terminating in the removal of the irradiated fuel. Phase I involved radiological surveys of the interior components of the main steam turbine's high pressure stage. At the request of the NRC Headquarter's Division of Low-Level Waste Management and Decommissioning, the Environmental Survey and Site Assessinent Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed a confirmatory radiological survey of the SNPS main steam turbine components. This report describes the procedures and results , of that survey. SITE DESCRIPTION The SNPS is located in the Town of Brookhaven, New York, on the north shore of Long Island, approximately 80 km (50 mi) east of the confluence of the East River and Long Island Sound (Figure 1). The SNPS r.ite is a 32.4 ha (80 ac) portion of a larger [202 ha (499 ac)] parcel of land owned by LILCO. The site is bounded on the north by Long Island Sound, on the east by the Wading River Marshland, on the west by other LILCO property, and on the south by Route 25A. A fence encloses the site secured areas. Within this boundary are the buildings and grounds, classified as the Restricted Area (also known as the power block) where radiological , controls were necessary (Figure 2). The turbine is located at elevation 63 feet of the Turbine Building. LIPA has approached termination surveys'in accordance with draft NUREG-5849.' The portions of the facility which will be addressed during the decommissioning have been designated as either affected or unaffected survey units. Survey units have been further categorized as either structures, systems, or embedded piping. The internal components of the main steam turbine have been designated as an affected system with the LIPA Survey Unit (SU) identifier of SUO29. The turbine is a General Electric 1800 tandem compound turbine with one high pressure and two , low pressure sections. Only the high pressure section was addressed by the licensee based on t contamination potential and NRC concurrence. At the time of this survey, the high pressure side of the turbine had been partially disassembled l j to facilitate the survey. The upper half of the turbine cover had been removed and staged l l w w r -w . 2 19. im 2 l
separately, as had the upper diaphragms, which when assembled fit into recesses that are found in the turbine cover, and the diffusers. The remainder of the turbine remained assembled, with the primary components being the east and west stage wheels, the rotor, labrynth seals, steam exhaust ports, and steam inlet piping (Figure 3). OBJECTIVES The objectives of the confirmatory survey were to provide independent document reviews and comparative radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's termination survey report, relative to the established guidelines. DOCUMENT REVIEW ESSAP reviewed the licensee's facility termination survey plan and termination final survey report prepared for the steam turbine system, for adequacy, appropriateness, and consistency between the documents." The termination survey data were also reviewed for accuracy, completeness, and compliance with the guidelines. PROCEDURES ESSAP conducted a confirmatory survey of the internal components of the main turbine on February 23 and 24,1993. The survey was in accordance with a February 8,1993 site-specific survey plan which was submitted to and approved by the NRC.' Additional information regarding instrumentation and procedures may be found in Appendices A and B. REFERENCE SYSTEM LIPA-prepared field drawings were used by ESSAP for referencing measurement and sampling locations on individual turbine components. The turbine stages, shown on Figure 3, were referenced as the upper 180' and lower 180', according to their orientatic . within the casing. m x.a.- %. m . s no. im 3
I / The main shaft had been rotated prior to this survey where the lower 180' portion was accessible during ESSAP's survey. SURFACE SCANS Surface scans for gamma and beta activity were performed on representative and accessible portions of the various turbine components. Scans were performed using Nal and GM detectors, coupled to ratemeters or ratemeter-scalers with audible indicators. SURFACE ACTIVITY MEASUREMENTS ESSAP performed direct measurements to determine total beta surface activity levels at 55 of the 1091 LIPA direct measurement locations. Measurements were performed using GM detectors coupled to ratemeter-scalers. The survey unit was not classified as an alpha-affected ' area; therefore, direct measurements for total alpha activity were not performed. A smear sample was collected from each direct measurement location to determine removable activity levels. Figures 4 through 54 indicate measurement locations. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to ESSAP's Oak Ridge laboratory for analysis and integretation. Smears were analyzed for gross alpha and gross beta activity using a low background proportional counter. Analytical data and direct measurement data were conve".ed to units of disintegrations per minute per 100 cm' (dpm/100 cm'). The results were compared to the NRC guidelines, which are provided in Appendix C. Sharmbem Nedser Power sannan - ha 19. I993 4
FINDINGS Ah3 RESULTS DOCUMENT REVIEW ESSAP's review of the termination survey plan indicated that the document provided an adequate description of survey methodologies and general approaches. Comments identified were provided to the NRC in a January 12, 1993 correspondence.2 ESSAP's review of the termination survey final report, which was conducted concurrent with the confirmatory survey, identified several additional issues which were discussed during a February 23,1993 site meeting. , SURFACE SCANS l 1 Surface scans did not identify any areas of elevated direct radiation on the turbine components. SURFACE ACTIVITY LEVELS i The results of total and removable activity are summarized in Table 1. All total beta activity 2 levels were below the minimum detectable activity of 990 dpm/100 cm . Removable activity i was less than 12 dpm/100 cm2 and less than 17 dpm/100 cm2 for gross alpha and gross beta, respectively. COMPARISON OF RESULTS WITII GUIDELINES { Regulatory Guide 1.86 provides the guidelines for acceptable surface contamination levels which are used by the NRC to determine whether a licensed facility may be released to unrestricted ; use. These guidelines are presented in Appendix C. The applicable guidelines are those for beta-gamma emitters, of which Co-60 and Fe-55 are the primary contaminants at SNPS. The residual surface activity guidelines are: Sharuban Nudser Power sannan - Jums 19, im 5 t - _ - _ - _ _ _ _ _ _ . - _ _ _ _ _ _ - - - _ - - - - _ - _ - _ _ _ - - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _
Total Activity 5,000 #-y dpm/100 cm 2, averaged over 1 m 2 15,000 #-y dpm/100 cm2 , maximum in 100 cm2 l Removable Activity 1,000 #-y dpm/100 cm 2 All total and removable activity levels were well within these guidelines. Because Fe-55 cannot be measured at the guideline levels by direct measurement techniques, using commercially ) available field instrumentation, surface activity measurements, which exceed the minimum detectable activity level (MDA), require a correction factor that will acco'u nt for the Co-60 to Fe-55 activity ratio. Surface activity measurements, which exceed the MDA of the instrumentation, are therefore adjusted by a factor of 1.2 to account for the Fe-55 contribution. This correction factor was derived from the Co-60 to Fe-55 activity ratio identified in characterization samples. There were no surface activity levels exceeding MDA identified on the turbine components and therefore, the data provided in this report has not been adjusted. All total and removable activity levels are well within the guidelines. - f
SUMMARY
In February 1993 ESSAP performed a confirmatory survey of the main turbine components at the Shoreham Nuclear Power Station in Brookhaven, New York. Confirmatory activities included document reviews, surface scans, direct surface actiGy measurements, and removable activity sampling. The ESSAP survey results indicate that surface activity levels were within the NRC surface contamination guidelines.' These findings support the results of the termination survey which LIPA performed. Sharuham Nalner Pe=st Smium - Jos 19. IM 6 l
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$boreham Nedent Power Sassun - Juns19,1995 31
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i SHRO3 LOWER 180* i - N l l W t ___ _ _ _ r % v A d x- } g WEASUREMENT AND SAMPUNG LOCATION NOT TO SCALE FIGURE 36: Main Turbine, Fourth Stage East (East Face) - Measurement and Sampling Location m w r.--si.s 1 ie. ines 42
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SHRS2 i LOWER 180 0
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i FIGURE 53: Main Turbine, North Main Steam Piping - Measurement and Sampling Location Sharubem Edser Psmr Sheiam . Jew 19, 3m $9
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TABLE 1 SURFACE ACTIVITY LEVELS HIGH PRESSURE SECTION TURBIhT COMPONENTS SHOREELGI NUCLEAR POWER STATION i BROOKHAVEN, NEW YORK Surface Activity Levels (dpm/100 cm') Component
- Total Beta Removable Activity Activity Alpha Beta Diaphragms
#2G < 990 < 12 < 17
#2T < 990 < 12 < 17
#4G < 990 < 12 < 17
#4T
< 990 < 12 < 17
#6G < 990 < 12 ' < 17
#6T < 990 < 12 < 17
#7G < 990 < 12 < 17
#7f < 990 < 12 < 17 Diffusers Northeast Diffuser < 990 < 12 < 17 Southwest Diffuser < 990 < 12 < 17 Northwest Diffuser < 990 < 12 < 17 Upper Casing, Interior 1st Inset East < 990 < 12 < 17 2nd Inset East < 990 < 12 < 17 l 3rd Inset East < 990 < 12 < 17 4th Inset East < 990 < 12 < 17 5th Inset East < 990 < 12 < 17 6th Inset East < 990 < 12 < 17 1
Sannhasa Nudent Power Sena am . Juns 19, IW3 61
TABLE 1 (Continued) f SURFACE ACTIVITY LEVELS HIGH PRESSURE SECTION TURBIhT COMPONEN'I'S SIIOREIIAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK Surface Activity Levels (dpm/100 cm') Component
- Total Beta Removable Activity Activity Alpha Beta Upper Casing, Interior 7th Inset East < 990 < 12 < 17 f 8th Inset East < 990 < 12 < 17 10th Inset East < 990 < 12 < 17 1st Inset West < 990 < 12 < 17 2nd Inset West < 990 < 12 < 17 3rd Inset West < 990 < 12 < 17 4th Inset West < 990 < 12 < 17 5th Inset West < 990 < 12 < 17 6th Inset West < 990 < 12 < 17 7th Inset West < 990 < 12 < 17 8th Inset West < 990 < 12 < 17 l
10th Inset West < 990 < 12 < 17 i Upper Casing N. Main Steam Inlet Piping Turbine Stages 1st Stage East (EFf < 990 < 12 < 17 1st Stage East OVF)- < 990 < 12 < 17 I 4th Stage East (EF) < 990 < 12 < 17 4th Stage East OVF) < 990 < 12 < 17 , 5th Stage East (EF) < 990 < 12 < 17 s m s.a.-r ,s- -) 29,im 62
) TABLE 1 (Continued) - SURFACE ACTIVITY LEVELS IIIGH PRESSURE SECTION TURBINE COMPONENTS SIIOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK Surface Activity IAvels (dpm/100 cm') Componentt Total Beta Removable Activity Activity Alpha Beta Upper Casing N. Main Steam Inlet Piping 5th Stage East (WF) <990 < 12 < 17 6th Stage East (EF) < 990 < 12 < 17 6th Stage East (WF) < 990 < 12 < 17 7th Stage East (Top) < 990 < 12 < 17 7th Stage East (WF) < 990 < 12 < 17 2nd Stage West (EF) < 990 < 12 < 17 2nd Stage West (WF) < 990 f < 12 < 17 3rd Stage West (EF) < 990 < 12 < 17 3rd Stage West (WF) < 990 < 12 < 17 Sth Stage West (WF) < 990 < 12 < 17 6th Stage West (EF) < 990 < 12 < 17 6th Stage West (WF) < 990 < 12 < 17 7th Stage West (EF) < 990 < 12 < 17 7th Stage West (WF) < 990 < 12 < 17 Main Inlet Steam Piping North Pipe < 990 < 12 < 17 South Pipe < 990 < 12 < 17 Sharuhmsa New.imer Powar Sessian - Juns I9.199: 63
I REFERENCES
- 1. Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990, (with addendum; June and October 1990).
I 2. Ieng Island Power Authority, "Shoreham Nuclear Power Station Decommissioning Plan," NRC Docket No. 50-322, December 1990. I 3. J.D. Berger, " Manual for Conducting Radiological Surveys in Support of License Termination", .NUREG/CR-5849 Draft, June 1992. I 4. Long Island Power Authority, "The Shoreham Nuclear Power Station Decommissioning Project Termination Survey for the Steam Turbine System (N31)," February 1993. I 5. Long Island Power Authority, "Shoreham Decommissioning Project, Termination Survey Plan," Revision 0, October 1992.
- 6. ORISE, letter from T.J. Vitkus to Dave Fauver, U.S. Nuclear Regulatory Commission, g " Proposed Confirmatory Survey Plan for the Turbine Internal Components, Shoreham l Nuclear Power Station, Brookhaven, New York," February 8,1993.
lp 7. ORISE, letter from M.R. Landis to Dave Fauver, U.S. Nuclear Regulatory Commission, "Shoreham Decommissioning Project, Termination Survey Plan, Revision 0, Shoreham Nuclear Power Station, October 1992", January 1993. I I I I l l l r l 1 Shoeubass Nudser Power Saaraus - June 19. IW3 64 l t - - _ - _ - - _ - _ _ - _ - _ _ - - _ _ _ - - _
{ APPENDIX A MAJOR INSTRUMENTATION ) 2
$banham Nadaar Power Sinaian - Juss19,1993 J
APPENDIX A MAJOR INSTRUMENTATION The display of a product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. DIRECT RADIATION MEASUREMENT Instruments Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NhD l Eberline " Rascal" Patemeter-Scaler
) Model PRS-1 I (Eberline, Santa Fe, NM)
Detectors I I
, Eberline GM Detector Model HP-260 Effective Area,15.5 cm2 (Eberline, Santa Fe, NhD Victorcen NaI Scintillation Detector Model 489-55 3.2 cm x 3.8 cm Crystal (Victoreen, Cleveland, OH)
LABORATORY ANALYTICAL INSTRUMENTATION Low Background Gas Proponional Counter Model LB-5110
) (Tennelec, Oak Ridge, TN) m w r.-- w w. n. im A-1 ,
V APPENDIX B SURVEY AND ANALYTICAL PROCEDURES Shanaam Nucleme Power sesion . June 19,1993 L . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ .
APPENDIX B SURVEY AND ANALYTICAL PROCEDURES , SURVEY PROCEDURES Surface Senns Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum - nominally about I cm. Surfaces were scanned using small area hand-held detectors. Identification of elevated radiation levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinations of detectors and instruments used for the scans were: Beta - pancake GM detector with ratemeter-scaler Gamma - NaI scintillation detector with ratemeter Surface Wivity Measurements Measurements of total beta activity levels were performed using detectors with portable rate-meter-scalers. Count rates (cpm), which were integrated over 1 minute in a static position, were converted to f activity levels (dpm/100 cm') by dividing the net rate by the 4 x efficiency and correcting for the active area of the detector. The beta activity background count rates for the GM detector averaged 22 cpm inside the Turbine Building on component steel. The beta efficiency factor was 0.16 for the GM detector. The effective window for the GM detectors was 15.5 cm'. Shmham Nucisar Power Statias . June 19,1993 B-1 f l
Removable Activity Measurements Removable activity levels were determined using numbered filter paper disks, 47 mm in diameter. Moderate pressure was applied to the smear and approximately 100 cnf of the surface was wiped. Smears were placed in labeled envelopes with the location and other pertinent information recorded. ANALYTICAL PROCEDURES Radiological Analyses Removable Activity Smears were counted on a low background gas proportional system for gross alpha and gross beta activity. UNCERTAINTIES AND DETECTION LBUTS The uncertainties associated with the analytical data presented in the tables of this report represent the 95% confidence level for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection limit of the measurement procedures. 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. Additional uncertainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this report. w w x.a % %.w re. im B-2
CALIBRATION AND QUALITY ASSURANCE Analytical and field survey activities were conducted in acc6rdance with procedures from the following documents:
- Survey Procedures Manual Revision 7 (May 1992)
- Laboratory Procedums Manual Revision 7 (April 1992)
- Quality Assurance Manual Revision 5 (May 1992)
The procedures contained in these manuals were developed to meet the requirements of DOE Order 5700.6C and ASME NQA-1 for Quality Assurance and contain measures to assess processes during their performance. Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to NIST, when such standards / sources were available. Quality control procedures include:
- Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations,
- Participation in EPA and EML Quality Assurance Programs, f
- Training and certification of all individuals performing procedures, and
- Periodic internal and external audits.
i f j Slumbem Nuclear Power Sannon - ha 19. Im B-3
APPENDIX C REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS i Shorehens Nucnner Power Sinnom - Jae 19, 1993 m_ .
U.S. ATOMIC ENERGY COMMISSION Junn 1974 REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES . FOR NUCLEAR REACTORS . A. INTRODUCTION A licensee having a possession-only license must retaza, with the Part 50 license, authorization for Section 50.51, " Duration oflicense, renewal," of 10 special nuclear material (10 CFR Part, 70, *Special CFR Part 50, *I. ice . sing of Production and Utilization Nuclear Material"), byproduct material (10 CFR Part i Facilities," requires that each license to operate a 30, " Rules of General Applicability to Licenung of , production and utihrntion facility be issued for a Byproduct Material"), and source material (10 CFR specified duration. Upon expiration of the specified Part 40, " Licensing of Source Material"), until the period, the license may be either renewed or termmated fuel, radioactive components, and sources are removed by the Commission. Section 50.82, " Applications for from the facility. Appropriate adminktrative controls termmation of ficenses,* specifies the requirements that and facility requirements are imposed by the Part 50 must be satisfied to termm=ta an operstmg license, license and the technical specifications to assure that including the reqmrement that the dismantlement of the proper surveillance is performed and that the reactor % facility and disposal of the component parts not be facility is mamtamed in a safe condition and not inimical to the cornmnn defensa and security or to the operated. heahh and safety of the public. This guide describes methods and procedures considered acceptable by the A possession-only license permits various options Regulatory staff for the termmntion of operating and procedures for decommissioning, such as licenses for nuclear reactors. The advisory Committee mothh!!ing, entombment, or dismantling. The on Reactor Safeguards has been consulted concerning requirements imposed depend on the option selected. this guide and has concurred in the regulatory position. Section 50.82 provides that the licensee may B. DISCUSSION dismantle and dispose of the component parts of a nuclear reactor in accordance with existing regulations. When a licensee decides to termmate his nuclear For research reactors and critical facilities, this has reactor operstmg license, he may, as a first step in the usually meant the disassembly of a reactor and its process, request that his operating license be amended shipment organization for further use. The site from to restrict him to possess but not operate the facility. which a reactor has been removed must be The advantage to the licensee of converting to such a decontammated, as necessary, and inspected by the possession-only license is reduced surveillance Commission to determine whether unrestricted access requirements in that periodic surveillance of equipment can be approved. In the case of nuclear power important to the safety of reactor operation is no longer reactors, dismantling has usually been accomplished by required. Once this possession-only license is issued, shipping fuel offsite, mahng the reactor inoperable, reactor operation is not permitted. Other activities and disposing of some of the radioactive components. from the reactor and placing it in storage (either onsite or offsite) may be continued. US AEC REGULATORY GUIDES g,,,,,, , , hosr.ory o e- ne ea ure. nw mane .an w e. m *****8 " es u.s. Atomie 5.n-o, comm ws w *wei-6 o.c. 2cras. mettmas acomptano se e Arc gawer, mare er- cers pas ^"*'** D'**' er neesmer, starearea. comai. rue are esop nere e , inf the C _ - e gdat re, to regar sms tecerW4was named by the staff an arnN M pedes are me0.d W M h nt te ve
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Radioactive compnnents may be either shipped Four alternativec for retitement of nuclear reactor off-site for burial at an authorized burial ground or facilities are considered acceptable by the secured on the site. nose radioactive materials Regulatory staff. These are: remn nmg on the site must be isolated from the public by physical barriers or other menne to prevent public a. Mothballing. Mo:hballing of a nuclear reactor access to hazardous levels of radiation. Surveillance is facility consists of putting the facility in a state of necessary to assure the long term integrity of the protective storage. In general, the facility may be barriers. De amount of surveillance required depends left intact except that all fuel assemblies and the upon (1) the potential hazard to the health and safety of radioactive fluids and waste should be removed the public from radioactive matenal remammg on the from the site. Adequate radiation monitoring, site and (2) the integrity of the physical barriers. envtrnnmentai surveillance, and appropriate security Before areas may be released for unrestricted use, they procedures should be established under a must have been A mnt mino~_i or the radioactivity posmeinn-only license to ensure that the health and must have decayed to less than prescribed limits safety of the public is not endangered. (Table 1).
- b. In-Place Entombment. In-place entombment ne ha:ard ac=~4 t~t with the returned facility is enn cices of sealing all the remammg highly evaluated by considering the a. mount and type of radioactive or contaminat~i components (e.g., the rmammg mn+-inneinn. the degree of confinement of pressure vessel and reactor intemals) within a the remammg radioective materials, the physical structure integ al with the biological shield after security provided by the conhament, the susceptibility having all fuel assemblies, radioactive fluids and to release of radiation as a result of natural phenomena, wastes, and cenam selected components shipped and the duration of required surveillance. offsite. He structure should provide integrity over the period of time in which significant quantities C. REGULATORY POSITION (greater than Table I levels) of radioactivity remain with the material in the entombment An
- 1. APPUCATION FOR A UCENSE TO POSSESS appropriate and continuing surveillance program BUT NOT OPERATE (POSSESSION-ONLY should be established under a pacteuion-only LICENSE) license.
A request to amend an operating license to a c. Removal of Radioactive. Components and poueuion-only license should be made to the Director Dismantling. All fuel assemblies, sadioactive fluids of Ucensmg, U.S. Atomic Energy Commission, and waste, and other materials having activities Wadington, D.C. 20545. He request should include above accepted unrestricted activity levels (Table 1) the following information: should be rerr.aved from the site. The facility owner may then have unrestricted use of the site
- a. A description of the current status of the facility. with no requirement for a license. If the facility owner so desires, the remainder of the reactor
- b. A description of measures that will be taken to facility may be dismantled and all vestiges removed prevent criticality or reactivity changes and to and disposed of.
minimize releases of radioactivity from the facility.
- d. Conversion to a New Nuclear System or a
- c. Any proposed changes to the technical Fossil Fuel System. This attemative, which applies specifications that reflect the possession-only facility only to nuclear power plants, utilizes the existing status and the necessary disassembly / retirement turbine system with a new steam supply system.
activities to be performed. na original nuclear steam supply system should be
, separated from the electric generating system and
- d. A safety analysis of both the activities to be disposed of in accordance with one of the previous accomplished and the proposed changes to the three retirement alternatives.
technical specifications.
- 3. SURVEILLANCF AND SECURITY FOR TIIE
- e. An inventory of activat uterials and their RETIREMEST ~ i.TERNATIVES WilOSE location in the facility. FIN A L STA 1S REQUIRES A POSSESSION-OSL > LICENSE
- 2. ALTERNATIVES FOR REACTOR RETIREMENT A facility which has been licensed under a possession-only license may contain a significant amount of radioactivity in the form of activated and Note: Section electronically reproduced from photocopy. C-2
contaminntM hardware and structural matenals. g. He following reports should be made: Surveillance and commensurate security should be provided to assure that the public health and safety are (1) An annual report to the Director of not endangered. Licensmg, U.S. Atemic Erargy Commmsion,
- a. Physical security to prevent inadvenent exposure Washing %n, D.C. 20545, describing the results of the of personnel should be provided by multiple locked envimnmental and facility radiation surveys, the status baniers., h presence of these barriers should make of the facility, and an evaluation of the performance of it extremely difficult for an unauthorized person to gain .ecurity and surveillance measures access to areas where gudiatinn or contsmmation levels exceed those specified in Regulatory Position C.4. To (2) An abnormal occurrence report to the prevent inadvertent exposure, radiation areas above Regulatory Operations Regional Office by telephone 5 mR/hr, such as near the activated primary system of within 24 hours of discovery of an abnormal a power plant, should be appropriately marked and occurrence. The abnormal occurrence will also be should not be ere==ible except by cutting of welded reponed in the annual report described in the preceding closures or the ^==-mhly and removal of =he=_nti=1 item.
, structures and/or shielding material. Means such as a remote-readout mtrusion alarm system should be h. Records or logs relative to the following items provided to indicate to designmi personnel when a should be kept and retamed until the license is physical barrier is panatentM Secuity personnel that termmateM, after which they must be stored with other provide access control to the facirty may be used plant records: metrad of the physical barriers and the intrusion alarm systems. (1) Environmental surveys,
- b. He physical barriers to unauthorized entrance (2) Facility radiation surveys, into the facility, e.g., fences, buildings, welded doors, and access openmgs, should be mspected at least (3) Inspections of the physical barriers, and quarterly to assure that these barriers have not deteriorated and that locks and locking apparatus are (4) Abnormal occurrences.
intact.
- c. A facihty rudsation survey should be performed 4. DECONTAMINATION FOR RELEASE FOR at least quarterly to verify that no radioactive material UNRESTRICTED USE is escaping or being transported through the contamment barriers in the facility. Sampling should If it is desired to termmate a license and to be done along the most probable path by which eliminate any further surveillance requirements, the radioactive material such as that stored in the inner facility should be sufficiently decontamin*A to prevent contamment regions could be transported to the outer risk to the public health and safety. After the regions of the facility and ultimately to the environs. decontammation is satisfactorily accomplished and the site inspected by the Commission, the Commission msy
- d. An environmental radiation survey should be authorize the license to be terminated and the facility performed at least semiannually to verify that no abandoned or released for unrestricted use. h significant smoimts of radiation have been released to licensee should perform the decontammation using the the environmant from the facility. Samples such as 'ollowing guidelines:
soil, vegetstmn, and water should be taken at locations for which e=tteir=1 data has been established during a. h licensee should make a reasonable effort to ; reactor operations. eliminate residual contammation. '
- e. A site representative should be designated to be 1,. No covering should be applied to radioactive responsible for controlling authorized access into and surfaces of equipment of structures by paint, plating, or movement within the facility. other covering material until it is known that ,
contammation leveis (determined by a survey and l
- f. Administrative procedures should be established documented) are below the limits specified in Table 1.
for the notification and reponing of abnormal In addition, a reasonable effort should be made (and occurrences such as (1) the entrance of an unauthorized documented) to further minimize contammation prior to person or persons into the facility and (2) a significant any such covering. change 12 the rnAintion or contammation levels in the facility or the offsite environment. c. b radioactivity of the interior surfaces of pipes, drain lines, or ductwork should be determined Chte: Section electrorscaDy reproduced from photocopy. C-3
by mnbng meast.rements at all traps and other After review cf the repod, the Commission may [ appropriate access points, provided contammation at mspect the facilities to confirm the survey prior to these locations is libly to be representative of granting approval for abandonment. 2conenmmation on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contammated but are of 5. REACTOR RETIREMENT PROCEDURES such size, construction, or location as to make the surface maccessible for purposes of measurement As indicated in Regulatory Position C.2, several should be assumed to be contaminated in excess of the alternatives are acceptable for reactor facility permissible rnMintion limita. retirement. If minor dienecembly or *mothballing" is planned, this could be done by the e.xisting operatmg
- d. Upon request, the Commission may authorize a and maintenance procedures under the license in effect.
licenses to rehnquish possession or control of premises, Any planned actions involving an unreviewed safety equipment, or scrap having surfaces contamin eu in question or a change in the technical specifications excess of the limits specified. This may include, but is should be reviewed and approved in accordance with not limited to, special circumstances such as the the requirements of 10 CFR I 50.59. transfer of premises to another licensed orgemntion r that will continue to work with radioactive materials. If major structural changes to radiontive ( Requests for such authorization sho M provide: components of the facility are planned, such as removal of the pressure vessel or major components of the (1) Detailed, specific information describing the primary systern. a dismantlement plan including the pre uises, equipment, scrap, and radioactive information required by 9 50.82 should be submitted to contammants and the nature, extent, and degree of the Commission. A dismantlement plan should be residual surface contammation. submitted for all the alternstives of Regulatory Position C.2 except mothballing. However, minor disassembly (2) A detailed health and safety analysis it;dicating activities may still be performed in the absence of such that the residual amounts of materials on surface areas, a plan, provided they are permitted by existing together with other considerations such as the operating and maintmanm procedures. A f prospective use of the premises, equipment, or a: rap, dismantlement plan should include the following: are unhkely to result in an unreasonable risk to the health and safety of the public. a. A description of the ultimate status of the facility
- e. Prior to release of the premises for unrestricted b. A description of the dicmantling activities and use, the licensee should make a comprehensive the precautions to be taken.
radiation survey establishing that contammation is within the limits specified in Table 1. A survey report c. A safety analysis of the dismantling activities should be filed with the Director of Licensing, U.S. including any effluents which may be released. Atomic Energy Commission, Washington, D.C. 20545, with a copy to the Director of the Regulatory d. A safety analysis of the facility in its ultimate Operations regional Office having jurisdiction. The status. report should be filed at least 30 days prior to the plarmed date of abandonment. 'Ibe survey report Upon satisfactory review and appmval of the should: dismr.2tling plan, a dismantling order is issued by the Commmion in accordance with 9 50.82. When (1) Identify the premises; dismantling is completed and the Commmion has been notified by letter, the appropriate Regulatory (2) Show that reasonable effort has been made to Operations Regional Office inspects the facility and reduce residual contammation to as low as practicable verifies completion in accordance with the levels; dismantlement plan. If residual radiation levels do not exceed the values in Table 1, the Commission may (3) Describe the scope of the survey and the general ternunate the license. If possession.only license under procedures followed; and which the dismantling activitie- have been conducted [ or, as an altemative, may make application to the State (4) State the finding of the survey in units specified (if an Agreement State) for a byproduct materials in Table 1. license. Nite: Section electronically reproduced from photocopy. C-4 e _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ - _ _ _ - _ - _ _ _ - - _ _ _ - - - - _ _ _ _ - - _ - _ _ _ _ _ _ - _ _ _ - _ - _ - - _ - _ _ _ - - _ _ - - - - _ _ _ - _ _ _ .
TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclidea Average" Maximum" Removable" U-nat, U-235, U-238, and
=@M decay products - 5,000 dpm a/100 cm 2 15,000 dpm a/100 cm2 1,000 dpm a/100 cm' Transuranica, Ra-226, Pa-228, Th-230, n-228, Pa-231, Ac-227, I-125, F 129 100 dpm/100 cm 2 300 dpm/100 cm* 20 dpm/100 cm2 h-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232,1-126, I-131, I-133 1,000 dpm/100 cm' 3,000 dpm/100 cm' 200 dpm/100 cm' Beta-gamma emitters (nuchdes with f decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above. /
5,000 dpm #7100 cm2 / 15,000 dpm #7100 cm' 1,000 dpm Sy/100 cm2
*Where surface contammation by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta- gamma-emitting nuclides should apply independently.
'As used in this table, dpm (druntegrations per minute) means the rate of emission by radioactive material as determmed by correctmg the counts per minute observed by an appropriate detector for backgmund, efficiency, and geometric factors
= =v-i = 'u with the instrum-ntation.
'Measurementa of sverage enntammant should not be aversged over more than 1 square meter. For objects of less surface f area, the average should be derived for each such object.
'Ite maximum contammation level applies to an area of not more than 100 cm8.
[ 'I'he amount of removable radioactive matenal per 100 cm2 of surface area shou'd be determined by wiping that area with l dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioac@e material on the wipe with an appropriate mstrument of known efficiency. When removable contammation on objer,ts of less surface area is determined, the pertment levels should be reduced proportionally and the entire surface should i e wiped. [ [ ( ( -.......,...-,.-.t,-..- c.s L __-_
Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil On October 23,1981, the Nuclear Regulatory Commission published in the Federal register a notice of Branch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations." This document established guidelines for concentrations of uranium and thorium in soil, that will limit maximum radiation received by the public under various conditions of future land usage. These concentrations are as follows: [ c - Maxhnum Concentrations. (pCi/g) gg, for various options l' 2' 3' 4' Natural Thorium (Th-232 + Th-228) 10 50 - 500 with daughters present and in equilibrium Natural Uranium (U-238 + U-234) 10 - 40 200 with daughters present and in f equilibrium Depleted Uranium: Soluble 35 100 - 1,000 Insoluble 35 300 -- 3,000 Enriched Uranium: Soluble 30 100 - 1,000 Insoluble 30 250 - 2,500 ( ' Based on EPA cleanup standards which limit radiation to 1 mradlyr to lung and 3 mradlyr to bone from ingestion and inhalation and 10 R/h above background from direct external exposure.
- Based on limiting individual dose to 170 mrem /yr.
' Based on limiting equivalent exposure to 0.02 working level or less.
' Based on limiting individual dose to 500 mrem /yr and in case of natural uranium, limiting exposure to 0.02 working level or less.
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