ML20046B364
| ML20046B364 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/31/1993 |
| From: | Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20046B360 | List: |
| References | |
| ZAR-930531, NUDOCS 9308040118 | |
| Download: ML20046B364 (83) | |
Text
4 DRAFT REPORT CONFIRMATORY SURVEY '
t OFTHE TURBINE INTERNAL COMPONENTS' SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK ,
T.J. VITKUS Prepared for the Division of Low-Level Waste Management and Decommissioning ,
Headquarters Office f l U. S.. Nuclear Regulatory Commission ' ' N._
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CONFIRMATORY SURVEY *
! OF TIIE TURBINE INTERNAL COMPONENTS SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK Prepared by ;
T. J. Vitkus ' !
i Environmental Survey and Site Assessment Program l Energy / Environment System Division l Oak Ridge Institute for Science and Education !
Oak Ridge, Tennessee 37831-0117 j l
T l Prepared for the l
! Division of Low-Level Waste Management and Decommissioning Headquarters Office l
U.S. Nuclear Regulatory Commission .
t 1
l DRAFT REPORT ,
i i !
MAY 1993 !
i This draft report has not been given full review and patent clearance, and the dissemination of ' ,
l its information is only for official use. No release to the public shall be made without the l approval of the Office of Information Services, Oak Ridge Institute for Science and Education, l
~
This report is based on work performed under an Interagency Agreement (NRC Fin. No. A- 1 l 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. ,
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( Shoreham Nuclear Power Station. May 6,1993 h:\essap\ reports \shortham\shoreham.002 l
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- i ACKNOWLEDGEMENTS '
l .
The author would like to acknowledge the rignificant contributions of the following staff .
members: !
i FIELD STAFF ,
D. A. Gibson LABORATORY STAFF R. D. Condra J. S. Cox M. A. Laudeman CLERICAL STAFF T. T. Claiborne D. A. Cox M. A. Perry K. E. Waters ILLUSTRATOR E. A. Powell l
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Shoretam Nuclear Power Station - May 6,1993 h:\emap\reporininhorcham\nhorcham.002 i
TABLE OF CONTENTS PAGE List o f Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii List of Tables .............................................vi Abbreviations and Acronyms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii Introduction and Site History . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Site Description ........................................... 2 Obj ec tives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Document Review . . . ...................................... 3 Procedures .............................................. 3 Findings and Results ......................................... 5 Comparison of Results with Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 S u m mary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 References ..............................................64 Appendices: Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86 Termination of Operating Licenses for Nuclear Reactors l
Shoreham Nuclear Power Station . May 6,1993 i b: kesap\ reports \shoreham\shoreham,002
LIST OF FIGURES PAGE l FIGURE 1: Location of the Shoreham Nuclear Power Station . . . . . . . . . . . . . . 7 FIGURE 2: Plot Plan of the Shoreham Nuclear Power Station . . . . . . . . . . . . . . 8 l
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l FIGURE 3: Main Turbine - High Pressure Section with Upper I
Casing Removed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 FIGURE 4: Main Turbine, Diaphragm #2G - Measurement and Sampling Imcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 FIGURE 5: Main Turbine, Diaphragm #2T - Measurement and Sampling Ixcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 FIGURE 6: Main Turbine, Diaphragm #4G - Measurement and Sampling Ixcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 FIGURE 7: Main Turbine, Diaphragm #4T - Measurement and Sampling Ixcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 FIGURE 8: Main Turbine, Diaphragm #6G - Measurement and '
Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 FIGURE 9: Main Turbine, Diaphragm #6T - Measurement and ,
Sampling Imcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 Samp1ing Imcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 FIGURE 13: Mair. Turbine, Southwest Diffuser - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 FIGURE 14: Main Turbine, Northwest Diffuser - Measurement and Sampling Imcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 FIGURE 15: Main Turbine, Upper Casing Interior, First Inset (East) -
Measurement and Sampling Location ....................21 Sharrban Nuclear Power Stanon - May 6.1993 55 h:\esnap\reportswrcham\shoreham.002
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 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) -
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 Shoreham Nucker Power Station . Wy 6,1993 kii h%ap\reportskhoreham%)mreham.002
4 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 Turbine, 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 Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 FIGURE 39: Main Turbine, Fifth Stage East (West Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 FIGURE 40: Main Turbine, Sixth Stage East (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 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: Main Turbine, Seventh Stage East OVest Face) - Measurement and Sampling IAcation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 Shoreham Nudcar Power Station May 6.1993 iv h:ksaapireportsinhoreharnishorcham.002 I
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l LIST OF FIGURES (continued)
PAGE FIGURE 44: Main Turbine, Second Stage West (East Face) - Measurement ,
and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 '
i FIGURE 45: Main Turbine, Second Stage West OVest Face) - Measurement l and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 FIGURE 46: Main Turbine, Third Stage East (East Face) - Measurement i and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 ,
FIGURE 47: Main Turbine, Third Stage West OVest Face) - Measurement [
and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 FIGURE 48: Main Turbine, Fifth Stage West OVest Face) - Measurement l and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 FIGURE 49: Main Turbine, Sixth Stage West (East Face) - Measurement and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 i
FIGURE 50: Main Turbine, Sixth Stage West OVest 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 i and Sampling Locations ............................58 FIGURE 53: Main Turbine, North Main Steam Piping - Measurement i and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 ;
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FIGURE 54: Main Turbine, South Main Steam Piping - Measurement '
and Sampling Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Shoreharn Eclear Power $tanor. - May 6.1993 V h:kensp\ reports \shoreham\shorrham.002 I
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' LIST OF TABLES i
PAGE j TABLE 1: Summary of Surface Activity Ixvels . . . . . . . . . . . . . . . . . . . . . 61 l !
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Shorcharn Neckar Power Sinnon . May 6,1993 Vi b:\cesap\ report \nhornhamwhercham.002 h
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l ABBREVIATIONS AND ACRONYMS. l i
t ac acre ASME American Society of Mechanical Engineers cm2 square centimeter cpm counts per minute dpm/100 cm2 disintegrations per minute per 100 square centimeters i EML Environmental Measurements Laboratory i EPA Environmental Protection' Agency . l ESSAP Environmental Survey and Site Assessment 'l Program !
ha hectare l GM Geiger-Mueller i km kilometer LILCO Ieng Island Lighting Company LIPA Ieng Island Power Authority !
2 m square meter. ,
mi mile !
NaI Sodium Iodide - i NIST National Institute of Standards and ;
Technology !
NRC Nuclear Regulatory Commission l ORISE Oak Ridge Institute for Science and Education .
QA -Quality Assurance ,
SU Survey Unit !
SNPS Shoreham Nuclear Power Station i 1
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Shorcham Nuclear Power Station - May 6.1993 . vii b:\essap\nportshhorehambhoreham.002 j
CONFIRMATORY SURVEY OF TIIE TURBINE INTERNAL COMPONENTS SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK INTRODUCTION AND SITE IIISTORY Shoreham Nuclear Power Station (SNPS), constructed by Long Island Lighting Company l (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 .3 Regulatory Commission (NRC) license (NRC Docket File No. 50-322) allowed reactor l.
operations at power levels not to exceed 5% of full power. Low-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 operating history was equivalent to 2.03 effective full-power days of fuel exposure. Before reaching design power j levels, a decision was made to decommission the facility, and the irradiated fuel 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.'
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! 1 l The Long Island Power Authority (LIPA) was established to decommission the facility and plans !
l 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.2 One of the 1 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, I such as conventional power generation. The decommissioning will be conducted in several Shoreham Nucker Power Stanon - May 6.1993 h4eansp\ reports \sho.charn\shortimm.002 -
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phases, terminating in the removal of the irradiated fuel. Phase I involved radiological surveys l ,
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 Assessment 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 site 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 viith 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 l
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 SU029.
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 contamination potential and NRC concurrence.
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At the time of this survey, the high pressure side of the turbine had been partially disassembled to facilitate the survey. The upper half of the turbine cover had been removed and staged Shoreharn Nndear Power St. tion - May 6, im 2 sa ps,c,<.s.ho,ch.ms.ho, 6 .oc2
separately, as had the upper diaphragms, which when assembled fit into recesses that are found in the turbine cover, and the diffusers. The :emainder 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.O 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 orientation within the casing.
Shorcham Nuclear Power Station May 6,1993 3 hww.ron wh-h wn-6-m2
4 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 3 portions of the various turbine components. Scans were performed using NaI and GM detectors, coupled to ratemeters or ratemeter-scalers with audible indicators.
i SURFACE ACTIVITY MEASUREMENTS I i
ESSAP performed direct measurements to determine total beta surface activity levels at 55 of- l the 1091 LIPA direct measurement locations. Measurements were performed- using GM l
detectors coupled to ratemeter-scalers. The survey unit was not classified as an alpha-affected l area; therefore, direct measurements for total alpha activity were not performed. A smear l sample was collected from each direct measurement location to determine removable activity levels. Figures 4 through 54 indicate measurement locations. l l
1 SAMPLE ANALYSIS AND DATA. INTERPRETATION ;
Samples and data were returned to ESSAP's Oak Ridge laboratory for analysis and- [
interpretation. Smears were analyzed for gross alpha and gross beta activity using a low ;
background proportional counter. Analytical data and direct measurement data were converted to units of disintegrations per minute per 100 cm2 (dpm/100 cm2). The results were compared to the NRC guidelines, which are provided in Appendix C. ;
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$boreham Nucicer Power Sintion - May 6.1993 4 haessap\reporiauhorehamkhorchmen.002
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h FINDINGS AND RESULTS i
DOCUMENT REVIEW l I
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.7 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. f SURFACE SCANS f Surface scans did not identify any areas of elevated direct radiation on the turbine components. I i
SURFACE ACTIVITY LEVELS The results of total and removable activity are summarized in Table 1. All total beta activity !
levels were below the minimum detectable activity of 990 dpm/100 cm2 . Removable activity was less than 12 dpm/100 cm2 and less than 17 dpm/100 cm2 for gross alpha and gross beta, respectively. :
i 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:
I Shoreham Nuclear Power Station - May 6.1993 5 6:s ps,erori.who,ch who,ch .o02-
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f Total Activity 5,000 #-y dpm/100 cm 2, averaged over 1 m2 15,000 #-y dpm/100 cm2 , maximum in 100 cm 2 i
Removable Activity l 2
1,000 #-y dpm/100 cm l All total and removable activity levelt 4. ;m ell 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 will require a correction factor that will be based on the Co-60 to Fe-55 activity ratio. The ratio that will be used has not been !
finalized at this time and the data provided in this report therefore has not been adjusted.
SUMMARY
In February 1993 ESSAP performed a confirmatory survey of the main turbine components at the Shorehar,n Nuclear Power Station in Brookhaven. New York. Confirmatory activities i included document reviews, surface scans, direct surface activity measurements, and removable activity sampling. -
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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.
l Shoreham Nucicar Power Stahon - May 6,1993 6 hhpWponswrchamWrchmM2 I
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TABLE 1
! SURFACE ACTIVITY LEVELS IIIGII PRESSURE SECTION TURBINE COMPONENTS SIIOREIIAM NUCLEAR POWER STATION
! BROOKIIAVEN, NEW YORK 1
Surface Activity Levels (dpm/100 cm')
Component
- Total Beta Removable Activity Activity Alpha Beta Diaphragms j r
! #2G < 990 < 12 < 17 :
l l
- #2T < 990 < 12 < 17 i l '
- 4G < 990 < 12 < 17 l
- 4T < 990 < 12 < 17
- 6G < 990 < 12 < 17 t
- 6T < 990 < 12 < 17
- 7G < 990 < 12 < 17 ;
!- #7T < 990 < 12 < 17 )
Diffusers i i
! Northeast Diffuser < 990 < 12 < 17 1
i Southwest Diffuser < 990 < 12 < 17 -
i Northwest Diffuser <990 < 12 < 17 l
Upper Casing, Interior l l l l 1st Inset East < 990 < 12 < 17 j 2nd Inset East < 990 < 12 < 17 3rd Inset East < 990 < 12 < 17 .
1 4th Inset East < 990 < 12 < 17 5th Inset East < 990 < 12 < 17 ;
6th Inset East < 990 < 12 < 17 Shoreharn Nuclear Power Station - May 6,1993 61 W apheponewnhaniWrden.WQ
l TABLE 1 (Continued) i SURFACE ACTIVITY LEVELS IIIGII PRESSURE SECTION TURBINE COMPONENTS SIIOREIIAM NUCLEAR POWER STATION l BROOKIIAVEN, NEW YORK [
2 Surface Activity Levels (dpm/100 cm )
Component' Total Beta Removable Activity i Activity Alpha Beta Upper Casing, Interior }
7th Inset East < 990 < 12 < 17 8th Inset East < 990 < 12 < 17 10th Inset East < 990 < 12 < 17 :
1st Inset West < 990 < 12 < 17 l 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 -l 7th Inset West < 990 < 12 < 17 8th Inset West < 990 < 12 < 17 l l
10th Inset West < 990 < 12 < 17 Upper Casing N. Main Steam Inlet Piping Turbine Stages 1st Stage East (EF)* < 990 < 12 < 17 1st Stage East (WF)* < 990 < 12 < 17 4th Stage East (EF) < 990 < 12 < 17 4th Stage East (WF) < 990 < 12 < 17 ;
5th Stage East (EF) < 990 < 12 < 17 Shoreham Nucker Power Sission . May 6,1993 62 6:s ps,epori.s.horch.ms. hor w.m.co2
. l i
1 I
i TABLE 1 (Continued) l SURFACE ACTIVITY LEVEIS IIIGII PRESSURE SECTION TURBINE COMPONENTS :
l SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK - .
Surface Activity I2vels (dpm/100 cm') ;
l !
Components' Total Beta Removable Activity
.l l Activity Alpha. Beta ;
Upper Casing N. Main Steam Inlet Piping ,
5th Stage East (WF) < 990 < 12 < 17 6th Stage East (EF) < 990 < 12 < 17 1
6th Stage East (WF) < 990 < 12 < 17 7th Stage East (Top) < 990 < 12 < 17 <
l 7th Stage East (WF) < 990 < 12 < 17 l f < 12 < 17 2nd Stage West (EF) < 990 2nd Stage West (WF) < 990 < 12 < 17 l 1
l l 3rd Stage West (EF) < 990 < 12 < 17 3rd Stage West (WF) < 990 < 12 < 17 5th Stage West (WF)- < 990 < 12 < 17 6th Stage West (EF) < 990 < 12 < 17 l
6th Stage West (WF) < 990 < 12 < 17 j 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 )
I ss-s.aa- r-. saw. u.y 6. i993 63 5 % ,w ro e w-sm m2
l .
REFERENCES ,
l
- 1. Ieng Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990, (with addendum; June and October 1990).
- 2. Long Island Power Authority, "Shoreham Nuclear Power Station Decommissioning Plan," NRC Docket No. 50-322, December 1990.
- 3. J.D. Berger, " Manual for Conducting Radiological Surveys in Support of License Termination", NUREG/CR-5849 Draft, June 1992.
l 4. Long Island Power Authority, "The Shoreham Nuclear Power Station Decommissioning l Project Termination Survey for the Steam Turbine System (N31)," February 1993. !
- 5. Long Island Power Authority, "Shoreham Decommissioning Project, Termination Survey Plan," Revision 0, October 1992.
t l 6. ORISE, letter from T.J. Vitkus to Dave Fauver, U.S. Nuclear Regulatory Commission,
{ " Proposed Confirmatory Survey Plan for the Turbine Internal Components, Shoreham i Nuclear Power Station, Brookhaven, New York," February 8,1993.
- 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. t i
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i APPENDIX A MAJOR INSTRUMENTATION .
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APPENDIX A MAJOR INSTRUMENTATION The display of a product is not to be construed um sement 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, NM) l t 1 Eberline " Rascal" Ratemeter-Scaler Model PRS-1 (Eberline, Santa Fe, NM) {
1 Detectors
- Eberline GM Detector j Model HP-260 Effective Area,15.5 cm 2 ,
(Eberline, Santa Fe, NM) i I
Victoreen NaI Scintillation Detector l Model 489-55 j 3.2 cm x 3.8 cm Crystal (Victoreen, Cleveland, OH)
LABORATORY ANALYTICAL INSTRUMEN" RATION l
Low Background Gas Proportional Counter l Model LB-5110 l (Tennelec, Oak Ridge, TN) l l
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l APPENDIX B SURVEY AND ANALYTICAL PROCEDURES I
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i APPENDIX B i
SURVEY AND ANALYTICAL PROCEDURTS SURVEY PROCEDURES j Surface Scans 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 1 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:
l Beta - pancake GM detector with ratemeter-scaler Gamma - Nal scintillation detector with ratemeter Surfnce Activity Mensurements l
l Measurements of total beta activity levels were performed using detectors with portable rate-l l meter-scalers.
l Count rates (cpm), which were integrated over 1 minute in a static position, were converted to
! activity levels (dpm/100 cm2 ) by dividing the net rate by the 4 r 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 l !
2 was 0.16 for the GM detector. The effective window for the GM detectors was 15.5 cm . !
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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 l
information recorded.
Shorthman Eckar Power Sianos . May 6.19M 3-1 h:\ennap\reportswrehamWrcharn.002 l
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l ANALYTICAL PROCEDURES Radiolonical Analyses Removable Activity Smears were counted on a low background gas proportional system for gross alpha and gross beta activity.
UNCERTAINTIES AND DETECTION LD1ITS f The uncertainties associated with the analytical data presented in the tables of this report i 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.
l Because of variations in background levels, measurement efficiencies, and contributions from l
l 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. )
i CALIBRATION AND QUALITY ASSURANCE Analytical and field survey activities were conducted in accordance with procedures from the following documents:
- Survey Procedures Manual Revision 7 (May 1992) )
- 12boratory Procedures Manual Revision 7 (April 1992) l - Quality Assurance Manual Revision 5 (May 1992)
Shortharn Nuclear Power Sistion - May 6,1993 B-2 h w .r + raso,h.e.ho u m2 l
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,
- Training and certification of all individuals performing procedures, and
- Periodic internal and external audits.
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1 APPENDIX C !
REGULATORY GUIDE 1.86 i TERMINATION OF OPERATING LICENSES l FOR NUCLEAR REACTORS :
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l REGULATORY GUIDE 1.86 I
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l TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS 1 l A. !NTRODUCTION A licensee having a possession-only license must l retain, with the Part 50 license, authorintion for special Section 50.51, " Duration of license, renewal," of 10 nudear material (10 CFR Part 70, "Special Nudear ,
CFR Part 50, " Licensing of Production and Utilization Materia!"), byproduct material (10 CFR Part 30," Rules l Facilities," requires that each license to operate a of General Applicability to Licensing of Byproduct production and utilization facility be issued for a Material"), and source material (10 CFR Part 40, f specified duration. Upon expiration of the specified ** Licensing of Source Material"), until the fuel, radio.
period, the license may be either renewed or terminated active components, and sources are removed from the by the Commission. Section 50.82, " Applications for facility. Appropriate administrative controls and facility tennination oflicenses," specifies the requirements that requirements are imposed by the Part 50 license and the must be satisfied to terminan an operating license, technical specifications to assure that proper surveillance including the requirement that the dismantlement of the is performed and that the reactor facility is maintained facility and disposal of the component parts not be in a safe condition and not operated.
inimical to the common defense and security or to the health and safety of the public. This guide describes A possession-only license permits various options and methods and procedures considered acceptable by the procedures for decommissioning, such as mothballing,
= Regulatory staff for the termination of operating entombment, or dismantling. The requirements imposed licenses for nuclear reactors. The Advisory Committee depend on the option selected.
on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position. Section 50.82 provides that the licensee may dis-mantle and dispose of the component park da nudear B. DISCUSSION reactor in accordance with existing regu.Mns. For research reactors and critical facilities, this has usually When a licensee decides to terminate his nuclear meant the disassembiy of a reactor and its shipment ;
reactor operating license, he may, as a first step in the offsite, sometimes to another appropriately licensed ,
process, request that his operating license be amended to organization for further use. The site from which a restrict him to possess but not operate the facility. The reactor has been removed must be decontaminated, as advantage to the licensee of converting to such a
- necessary, and inspected by the Commission to deter.
possession.only license is reduced surveillance require. mine whether unrestricted access can be approved. In ments in that periodic surveillance of equipment im. the case of nudear power reactors, dismantling has
. portant to the safety of reactor operation is no longer usually been accomplished by shipping fuel offsite, required. Once this possession-only license is issued, ' making the reactor inoperable, and disposing of some of reactor operation is not permitted. Other activities the radioactive components.
related to cessation of operations such as unloading fuel .
from the reactor and placing it in storage (either onsite Radioactive components may be either shipped off.
of offsite) may be continued.
site for burial at an authorized burial, ground or secured i
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TABLEI EE=-
ACCEPTABLE SURFACE CONTAMINATION LEVEL.S NUCLIDEa AVERAGEb c MAXIMUM.b d REMOVABLEb e U-nat, U-235, U-238, and 5,000 dpm n/100 cm2 15.000 dpm n/l00 cm2 1,000 dpm all00 cm2 associated decay products Transuranics, Ra-226, Ra-228, 100 dpm/100 cm2- 300 dpm/100 cm2 20 dpm/100 cm 2 Th-230, Th 228, Pa-231, Ac-227,1-125,1-129 Th-nat, Th-2'32, Sr 90, 1000 dpm/100 cm2 3000 dpm/100 cm2 200 dpm/100 cm2 Ra 223, Ra-224, U 232, 1-126,1-131,1 133 Beta gamma emitters (nuclides , 5000 dpm #1/100 cm 2 15,000 dpm Sq/100 cm2 1000 dpm $9/100 cm2 with decay modes other than alpha emission or spontaneous fission) except Sr 90 and others noted above.
- Where surface contamination by both a!pha and beta-gamma-emitting nuclides exists, the hmits established for alpha- and beta-gamrna-emitting nuclides should apply independently.
l b
As used in this table, dpm (disintepations per minute) means the rate of emission by radioactrve material as determined by correcting ;
the counts per minute observed by an appropriate detector for backpound, efficiency, and geometric factors associated with the !
instrumentation. ,
C Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the i average should be denved for each such object. ;
d
=., The maximum contamination level appbes to an area of not more than 100 cm2, j
'The amount of removable radicactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter er l*
soft absorbent paper, applying moderate pressure, and assessing the amount of radioactrve material on the wipe w..a an apprepnate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertment leveh '
should be reduced proportionally and the entire surface should be wiped.
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