ML20064C142
| ML20064C142 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/28/1994 |
| From: | Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC |
| Shared Package | |
| ML20064C113 | List: |
| References | |
| CON-FIN-A-9076 NUDOCS 9403090160 | |
| Download: ML20064C142 (76) | |
Text
I DRAFT REPORT i
CONFIRMATORY SURVEY OF THE TURBINE BUILDING, ,
1 SITE GROUNDS, AND SITE EXTERIORS SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK T. J. VITKUS Prepared for the Division of Low-Level Waste Management and Decommissioning s-Headquarters Office _
U.S. Nuclear Regulatory Commission y
, ;.4 4 s e
/^
~
u~ _.,
~ ^y
. ume j u
Y ,
I
, \
4
. % .i
, %-*'I St
- s
-%s ,
, g -d
^
9403090160 940203 22 ~
ty; PDR ADOCK 0500 " * '
s.P. . _ . ,
" ' D; U[. , -[.;
ORKSE s O AK RIDGE INSTITtJI'E. FOIC: SCIENCE 'ANI); EDUCATION:-. -
! Environmental.Suriey and Site A.sse'ssme;rit Pr;ogram ;
x Energy / Environ'ment SpstemsLDivisioni: I
?m m. new l
- . , ~ > . , , ,
CONFIRMATORY SURVEY OF TIIE TURBINE BUILDING, SITE GROUNDS, AND SITE EXTERIORS SIIOREllAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK Prepared by T. J. Vitkms Environmental Survey and Site Assessment Program ,
Energy / Environment Systems Division 1 Oak. Ridge Institute for Science and Education j Oak Ridge, Tennessee 37831-0117 l Prepared for the U.S. Nuclear Regulatory Commission Headquarters Office Sponsored by the Division of Low-Level Waste Management I and Decommissioning DRAFT REPORT ITBRUARY 1994 This draft report has not been given full review and patent clearance, and the. dissemination of its information is only for official use. No release to the public shall be made without the approval of the Office of Information Services, Oak Ridge Institute for Science and Education, i 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 number DE-AC05-760R00033 with the U.S. Department of Energy.
Shoreham Nudear Power Statim - rebnery 3, t994 h:\emap\ reports \shoreham\nhoreham 001
ACKNOWLEDGEMEfffS The author wou d like to acknowledge the significant contributior:s of the following staff member.':
FIELD STAFF S. F. Barnett M. A. Henke E. H. Montalvo J. R. Morton D. M. Nugent J. L. Payne LABORATORY STAFF R. D. Condra J. S. Cox M. J. 12udeman CLERICAL STAFF T. T. Claiborne D. A. Cox ,
R. D. Ellis K. E. Waters ILLUSTRATORS M. A. Henke T. ' D. Herrera 1
l Shoreham Nuclear Power Statkm . Februsq 3.1994 b:\emap\reportm\sboreham%orcham.001 i
l i
i TABLE OF CONTENTS PAGE !
Li st o f Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i1 List .of Tables ......... .................. ................. iv Abbreviations and Acronyms . . . . . . . . . . . . . . . . . . . ..................y introduction and Site History . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Site Description ............................................. 2 Obj ec ti ves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Document Review and LIPA Procedure Surveillance . . . . . . . . . . . . . . . . . . . . . . . 4 Procedures ................................................ 4 Findings and Results ..........................................10 Comparison of Results with Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 13 S u m m ary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 References ...............................................53 Appendices:
Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86 Termination of Operating Licenses l
for Nuclear Reactors i
$boretam Nwicar Power statma February 3,1994 i b:\eamap\ reports \shoreham' horeham 001 I i
l i
. ~ .
1
{
LIST OF FIGURES
.PhDE FIGURE 1:
Location of the Shoreham Nuclear Power Station . . . . . . . .. .. .. . 16 FIGURE 2:
Plot Plan of the Shoreham Nuclear Power Station . . . . . . . .. .. .. . 17 FIGURE 3:
Turbine Building, Elevation 15'-Floor Plan and Areas Surveyed . . . . . 18 FIGURE 4:
Turbine Building, Elevation 37'6"-Floor Plan and Areas Surveyed . . . . 19 FIGURE 5:
Turbine Building, Elevation 63'-Floor Plan and Areas Surveyed . . . . . 20 FIGURE 6: Shoreham Nuclear Power Station, Restricted Area-Exterior Areas Surveyed ....
............... . . . . . . . . 21 FIGURE 7: Turbine Building, North Condenser Hallway (TB016)-Measurement and Sampling Locations . .. .. ...... .......... . . 22 FIGURE 8: Turbine Building, West Condenser Bay (TB017)-Measurement and Sampling Locations . . . . . . ........ .....
. . . . . . . . . . . . 23 FIGURE 9: Turbine Building, Steam Seal Evaporator Room (TB031)-Measurement and Sampling Locations .....
............. . . . . . . . . . . 24 FIGURE 10: Turbine Building, Truck Bay (TB035)-Measurement and Sampling Locations ................ ..... . . . . . . 25 FIGURE 11: Turbine Building, Chemistry Laboratory (TB060)-Measurement and Sampling Locations .... ..
{
. .. .. . . . . . . 26 j
FIGURE 12: Turbine Building, Re-Heater Area, East (TB081)-Measurement and l
Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 FIGURE 13: Turbine Building Re-Heater Area, West (TB082)-Measurement and Sampling Locations . . . , . . . . . . . . . . . .
................28 FIGURE 14: Turbine Building, Black Battery Charger Room (TB089)-Measurement and Sampling Locations
........................... . . . 29 FIGURE 15: Colt Emergency Diesel Generator Buildin Measurement Locations . . . . . . . . . . .g-Background
....................30 FIGURE 16: Turbine Building, Feedwater Control (SUOO5)-Measurement and Sampling locations . . . . . . . .. ...... ...... . . . . . . . 31 I
Shortham Nudene Power Station - rebevary 3.1994 ik hTc4.api reportss ahorchamwsehain.001 S
LIST OF FIGURES (Continued)
IMGE FIGURE 17: Turbine Buildirig, Radwaste Interior Drain Pipe System Tank 12 (SUO14x03)-Measurement and Sampling Locations ............32 FIGURE 18: Turbine Building, Main Steam Components (SUO24)-Measurement and Sampling Locations ..... ..........................33 FIGURE 19: Turbine Building,15' Elevation, Condensate and Feedwater, Main Condenser, (SUO25 x02)-Measurement and Sampling Locations . . . . . 34 FIGURE 20: Turbine Building, Lube Oil Sump Tank 91 (SUO32)-Measurement and Sampling Locations ..............................35 FIGURE 21: Turbine Building, Extraction Steam, Valve 035C (SUO34)-
Measurement and Sampling Locations . . . . . . . . . . . . . . . . . . . . . . 36 FIGURE 22: Condensate Transfer and Storage, Condensate Storage Tank, (SUO46x02)-Measurement and Sampling Locations ............37 FIGURE 23: Turbine Building, Influent Drain System, Low Conductivity and Salt Water Drains, Tank-186B (SUO54 x03)-Measurement and Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 FIGURE 24: Secondary Access Facility, Ventilation System (SUO71)-Measurement and Sampling Locations ..............................39 FIGURE 25: Turbine Building,15' and 37' 6" Elevations, Drains (SUO14) and Vents-Measurement and Sampling Locations ..............40 o FIGURE 26: Secured Area, Colt Emergency Diesel Generator Building Exterior (SE002)-Measurement and Sampling Locations , , . . . . . , . . 41 FIGURE 27: Secured Area, Chlorine Pumphouse Exterior (SE002)-Measurement and Sampling Locations .............................. 42-FIGURE 28: Secured Area West (SG003)-Measurement and Sampling Locations . . . 43 FIGURE 29: Background Soil Sampling and Exposure Rate Measurement Locations . . 44 -
shoreham Nuclear Power Sutson - February 3.19M iii b:\c sp\reportstehoreharn\nhoreham.001
1 i
1 LIST OF TABLES PAGE ;
TABLE 1: Summary of Surface Activity Levels . . . . . . . . . . . . . . . . . . . . . . . 45 TABLE 2: Interior Exposure Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 TABLE 3: Exterior Exposure Rates and Co-60 Concentration in Surface ,
Soil Samples .....................................48 TABLE 4: Radiological Summary-Structures, Site Grounds, and Site Exteriors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 TABLE 5: Radiological Summary-Systems . . . . . . . . . . . . . . . . . . . . . . . . . 51 l
J l
1 l
l l
I l
l Shoreham Nuclear Power $ts6on - February 3.1944 iV h. te. asp \re porisuhor ehambhor chem. 001 l
l w v
- m -ry- --
.. _ ~_ - _- . . .- ._. . - ..
ABBREVIATIONS AND ACRONYAIS l
l ac acre !
ASME American Society of Mechanical Engineers em2 square centimeter cpm counts per minute dpm/100 cm2 disintegrations per minute per 100 square centimeters EML Environmental Measurements Laboratory EPA Environmental Protection Agency j ESSAP Environmental Survey and Site Assessment i Program i ft2 square feet ha hectare GM Geiger-Mueller k.m kilometer LILCO Long Island Lighting Company LIPA Long Island Power Authority m2 square meter MDA minimum detectable activity mi mile Nal sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ORISE Oak Ridge Institute for Science and Education QA Quality Assurance SNPS Shoreham Nuclear Power Station SE# site exterior survey unit designation ;
SG# site grounds survey unit designation SU# system survey unit designation ,
TB# Turbine Building structural survey unit .]
designation i
i I
shoreham Nudear Power Station. I4bruary 3,19N V h:\ensap\ reports \shorchain\ahoreham.001
1 i
I CONFIRMATORY SURVEY j OF TIIE l TURBINE BUILDING, SITE GROUNDS AND SITE EXTERIORS !
SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK i
INTRODUCTION AND SITE IIISTORY The Long Island Lighting Company (LILCO) constructed a boiling water reactor, known as the Shoreham Nuclear Power Station (SNPS), which was designed to provide a gross electrical output of 849 Megawatts. Reactor criticality was achieved in February 1985. Low power testing, in accordance with U.S. Nuclear Regulatory Commission (NRC) License No. NPF-82 (NRC Docket File No. 50-322), which permitted reactor operations at levels not to exceed 5%
of full power, commenced in July 1985. ' Reactor operations continued intermittently until January 1989, at which time power generating operations were terminated. The total operating history was equivalent to 2.03 effective full power days of fuel exposure. Irradiated fuel, which was a standard low enrichment (2 to 3% uranium-235) uranium 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 reactor operation. The primary contaminants which have_ been identified during characterization studies include iron-55, cobalt-60, nickel-63, and smaller quantities of tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152.8 The Long Island Power Authority (LIPA) was established to decommission the facility and release the site for unrestricted use. LIPA's decommissioning plan was approved for implementation by the NRC in June 1992 and will include decontamination or removal of j contaminated portions of the reactor and other ' plant systems and equipment. A ma,ict l
consideration of the decommissioning plan is to maintain the integrity when possible, of plant l structures and systems. Activities involved with the decommissioning and termination surveys will be conducted over an approximate eighteen month period with the final phase being removal of the spent fuel from the site. The initial phase involved the termination survey of the internal components of the main turbine; which has since been followed by termination surveys of the Shorehain % clear Power Statwa February 3,1994 hAesesp\ reports;shoreham\shoreham 001
l l
l remainder of the structures and systems located within the Turbine Building as well as the site grounds and building exteriors. I It is the policy of the NRC to perform confirmatory surveys of facilities that have undergone decommissioning and have requested NRC license termination. The NRC Headquarters' j Division of Low-Level Waste Management and Decommissioning has requested that the-Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct confirmatory radiological surveys and related activities for the SNPS decommissioning project as the various decommissioning milestones are completed. The results of the confirmatory survey of the turbine internal components are the-subject of a separate report.2 This report describes the results of the confirmatory process which has been completed for the Turbine Building, site grounds, and building exteriors.
SITE DESCRIIYI' ION SNPS is located in the Town of Brookhaven, New York on the north shore of Long Island, approximately 80 km (50 mi) east of La Guardia Airport and the confluence of the East River and Iang Island Sound (Figure 1). Reactor and supporting operations were conducted within a 32.4 ha (80 ac) portion of a larger 202 ha LILCO owned parcel ofland that 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 cyclone fence encloses the 8 ha site secured area. 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). Each of the buildings that are to be addressed during the confirmatory surveys are located here and are shown on Figure 2 as the Turbine Building, the Reactor Building, and the Rad Waste Building.
Turbine Building construction is predominately of concrete and structural steel with a total floor space of 13,500 m2 (145,000 ft 2) that is divided between three levels at elevations 15', 37' 6",
and 63' (Figures 3 through 5). Surfaces and components within the building remain essentially intact following decommissioning' activities. The systems and equipment housed include the turbine generator, main condenser, condensate system, feed water system, extraction heaters, part of the off-gas rad waste system, and drain sumps. Site grounds and site exteriors Shoreham hirar Power Station - February 1,1994 2 hicasap\ reports \nhoreham\shoreham.001
1 encompass those land areas and building exteriors and roof tops contained within the secured area.
Termination surveys have been performed in accordance with Draft NUREG/CR-5849.2 LIPA has classified plant systems, building surfaces, and outside areas into two categories for survey, .
which are based on the potential for residual contamination. The two categories, referred to as l affected or unaffected, are defined as follows: "affected areas are those areas which are potentially contaminated or have known contamination, or a system which circulated, stored or processed radioactive materials such that they could become contaminated, or experience, neutron activation, or where records indicated spills or other occurrences may have resulted in contamination; unaffected areas are those portions of the SNPS that are not expected to contain residual radioactivity." Area classification was determined by radiological use history, environmental monitoring activities, and the results of the previous characterization survey.
Affected and unaffected areas are further subdivided into survey units. Survey units are categorrad as structures (floors, walls, ceilings, and exterior surfaces of piping and equipment),
plant systems (equipment and piping internals), and exterior areas (grounds and building exteriors). In addition, affected survey units also have sub-classifications as suspect or non-suspect, and may also be classified as alpha affected if involved with fuel handling or storage.
For the Turbine Building, site grounds, and site exteriors, there were a total of 191 survey units addressed, of which,135 were structures (including building exteriors),48 were systems, and 8 were site grounds. Twenty-four of these survey units were classified by the licensee as affected.
OBJECTIVES The objectives of the confirmatory activities were to provide independent document reviews, review and perform field observations of the LIPA procedures for embedded piping surveys, and develop radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and termination survey results.
1 Shoreham Nudear Power Statkm . February 3,1994 3 h:s ps,co,s.s.ho h ms.ho..h ooi
DOCUMENT REVIEW AND LIPA PROCEDURE SURVEILLANCE ESSAP reviewed LIPA's termination survey procedures and the termination survey release records for those survey units selected for confirmatory survey.O Documents were reviewed for adequacy, accuracy, completeness, and consistency. In addition, ESSAP reviewed and initiated observational surveillance of the embedded piping procedures for appropriateness and consistency in field application.
PROCEDURFS During the period November 8 through 12, 1993, an ESSAP team visited the SNPS and performed independent visualinspections, measurements, and sampling of the Turbine Building, site grounds, and site exteriors. Surveys were performed in accordance with a survey plan submitted to and approved by the NRC.* ESSAP randomly selected 8 of the Turbine Building structural survey units,3 of the system survey units and 1 each of the site ground and building exterior survey units for confirmatory surveys. In addition, the NRC site representatives, selected portions of 6 additional system survey units for confirmatory surveys. Survey unit designators are alpha-numeric with the first Ogures designating the type of unit, structural (building specific), system, grounds, or exteriors, followed by a three digit numeric reference.
Subunits are given an additional two digit designation preceeded by X. The survey units selected and the respective classification for each were:
Anected(A)/ Stmetum/ System /
Survey Unit Survey Unit Name Unaffected (U) Building Grounds TB016 North Condenser Hallway U structure TB017 West Condenser Bay U structure TB031 Steam Seal Evaporator Room A structure TB035 Truck Bay A structure TB060 Chemistry Laboratory A structure TB081 Re-Heater Area-East A structure TB082 Re-Heater Area-West A structure Shortham Nuclear Power Swion . Febmary 3,1994 4 h:\essap\reporta%oreham\ horeham.001
Affected(A)/ Structure / System /
Survey Unit Survey Unit Name l Unaffected (U) Building Grounds !
TB089 Black Battery Charger Room U structure SU005 Feed Water Control A system l SUO14 Radwaste-Turbine Building A system !
Drain Piping System SU014X03 Radwaste-Turbine Building A system Drain Piping System, Tank 12 SUO24 Main Steam A system SUO25X2 Condensate and Feedwater, A system 15' Elevation Main Condenser SUO32 Lube Oil Sump Tank 91 U system SUO34 Extraction Steam Valve 035C A system SUO46 Condensate Transfer and A system Storage SUO54X03 Low Conductivity and Salt A system Water Drains Influent Drain System Tank 186 SUO71 Secondary Access Facility U system Ventilation System ,
SE002 Secured Area-North U structure Buildings SG003 Secured Area West U bldg. grounds Figures 3 through 6 indicate the structural and exterior survey units surveyed.
I l
i l
i
)
l Shoreham Nw%ar 1%er St.txm . February 3. Im 5 h:se c s,erori.s. sores. s.hores. ooi
SURVEY PROCEDURES: INTERIOR l
l The following procedures apply to interior structural and system survey units. )
Reference Systern LIPA established the grid system used by ESSAP for referencing measurement and sampling locations. The grid size or reference interval established by LIPA for a given survey unit was dependent upon the survey unit classification (affected vs. unaffected) and surface (floor, lower wall, upper wall, ceiling, or equipment). Typically, floor and lower wall grid blocks were 1 m x 1 m. Upper surfaces, ceiling and equipment were either. referenced to these grids or other prominent building features. Systems were referenced by a distance from a specific point, by drawings, or prominent components.
Surfnce StimS-Structural Units Surface scans for alpha, beta, and gamma activity, were performed over 100% of floor, and lower wall surfaces and up to 50% of equipment surfaces, within each structural survey unit.
Additional scans were performed over portions of upper wall, ceiling, and/or system surfaces as well as locations, such as drains, where material .may have settled or accumulated. Locations of elevated direct radiation detected by scans were marked for further investigation. Scans were performed using gas proportional, GM, and/or NaI detectors coupled to ratemeters or ratemeter-scalers with audible indicators.
Surface Activity Measurements For each structural survey unit, ESSAP performed a minimum of thirty direct measurements for total beta surface activity at randomly selected locations. ESSAP also performed additional direct measurements at locations of elevated direct radiation detected by surface scans. At measurement locations where the average NRC surface contamination guideline was exceeded, the size of the contaminated area and the average activity in the contiguous 1 m2 area was hreham Nuclear Power Stethm . Ichruary 3, im 6 hnessap\ reports \shortham\shorehamAX)1
l determined. Alpha surface ' activity measurements were not required as the selected survey units were not classified as alpha affected and there was no alpha contamination identified by surface scans. Figures 7 through 14 show structural survey unit measurement locations. Measurements were performed using GM and/or gas proportional detectors coupled to ratemeter-scalers. A smear sample for determining removable activity level was collected from each direct measurement location.
Exoosure Ride Measurements Background exposure rate measurements were made at 10 locations within the Colt Building, which is of similar construction to the Turbine Building but did not have a history of radiological ;
usage (Figure 15). Exposure rate measurements were performed at several direct measurement locations within structural survey units (Figures 7 through 14). All exposure rates were measured at I m above surfaces using a pressurized ionization chamber (PIC).
Systems For multicomponent systems, ESSAP requested up to 5 randomly selected access points be opened to each of the system suivey units selected for confirmatory survey. Beta and gamma surface scans were then performed within the accessible portions of the system followed by direct measurements and smear samples. Scans and direct measurements were performed using gas proportional, GM, and/or NaI detectors coupled to ratemeters or ratemeter-scalers. The ;
total number of direct measurements performed was-dependent upon component size and :
accessibility and ranged from 3 to 30 measurements (Figures 16 through 24).
L Embedded Piping
' Confirmation of the radiological status of embedded piping was accomplished primarily through surveillance of the methodologies and review of the procedures utilized. In addition, independent measurements were made within drain openings throughout the Turbine Building (Figure 25).
Shoreham Nmicar Power Stetaon - February 3,1994 7 h:Weap\reposts\ahorcham\nhoreham.001
. a Comparative Meatu. remen1s LIPA was requested to perform direct measurements at 30 ESSAP direct measurement and exposure rate measurement locations. ESSAP instrumentation included GM and gas proportional !
detectors coupled to ratemeter-scalers for direct measurements and a PIC for exposure rate measurements. The LIPA instrumentation used, which ESSAP selected randomly, included HP-260 and 126 cm 2GM detectors coupled to ratemeter-scalers for direct measurements and a micro-rem meter for exposure rate measurements. The LIPA micro-rem readings were converted to R/h using the LIPA developed correlation factor of 3.06 + 1.07 ( rem).
SURVEY PROCEDURES: EXTERIOR The following procedures apply to exterior site grounds and building exteriors.
Reference System 1 The grid systems established by LIPA on the site grounds and exterior building surfaces were used by ESSAP for reference.
Surface Scans Site grounds, paved areas, and building exteriors were scanned for gamma activity, while paved -
areas and exterior building surfaces were also scanned for alpha and beta activity. Scans were performed using NaI, gas proportional, and/or GM detectors coupled to ratemeters or ratemeter-scalers with audible indicators.
Surface Activity Measurements ESSAP performed 30 direct measurements for total beta activity on both the paved portions of :
SG003 and the surfaces of SE002 (Figures 26 through 28). Alpha direct measurements were not required. Direct measurements were made using gas proportional and/or GM detectors Shorcham Nuclear Power Statkm . rebruary 3,1994 8 ht_-.,h, ,ebhorehambhoreham.001
. coupled to ratemeter-scalers. A smear sample for determining removable activity was collected from each direct measurement location.
Exposiire Rate Measurements Background exposure rate measurements were performed at 6 locations within 0.5 to 10 km of the site (Figure 29). Exposure rate measurements were also performed at each soil sampling location within SG003 (Figure 28). Exposure rates were measured at 1 m using a PIC.
i Soil Samulin_g Background soil samples were collected from 6 locations within 0.5 to 10 km of the SNPS (Figure 29). There were five soil samples collected from randomly selected locations within SG003 (Figure 28).
fanfirmatory Analysis
)
Four soil samples and 1 septic tank sludge sample, collected by LIPA, were obtained for
]
confirmatory analysis.
l 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. Soil and sludge samples were analyzed by solid state gamma-spectrometry. The spectra were reviewed for Co-60 as well as any other identifiable photopeaks. Soil and sludge sample results were reported in units of pCi/g. Smear and direct measurement data were converted to units of dpm/100 cm 2. . Direct measurements which exceeded background levels were corrected for Fe-55 contribution, which can not be adequately detected with field instrumentation. A correction factor of 1.2 was therefore applied to those i
surface activity measurements that exceeded background distribution levels. LIPA developed, Shoreham Nalear Power Stabon - rebruary 3, im 9 sa ps,erori.t.6 ores.ms.hores .ooi
and the NRC approved, the use of this correction factor based on the observed Co-60 to Fe-55 activity ratio identified in characterization samples.d7 Exposure rates were reported in pR/h.
The 95% confidence level was calculated for surface activity and exposure rates for each survey unit selected for confirmation. A direct comparison of the ESSAP and LIPA survey unit results and individual soil sample results was performed. Additional information concerning major instrumentation, sampling equipment, and survey and analytical procedures is provided in Appendices A and B.
1 i
FINDINGS AND RESULTS DOCUMENT REVIEW ESSAP's review of the termination survey plan indicated that the document provided an adeqeate description of survey methodologies and general approaches. Comments were provided to the NRC in a January 12,1993 correspondence.' ESSAP's review of the termination survey final report, and release records for those survey units selected for confirmatory survey, indicated that the survey plan had been appropriately followed with no significant deviations. Data was appropriately converted, tested, and presented. Comments which were identified may be summarized as follows: )
i Several direct measurements exceeded the average activity guideline. There was no 1
explanation of additional data provided in the report that would demonstrate compliance !
l at these locations with the 1 m2 average activity guideline. l l
The report would benefit from the incorporation of maps which provide an overall (assembled) system view indicating components, rather than only maps of individual components.
l l
l breham Nudeer Power St.ta - February 3, tW4 10 6:se ps,ero,s.s. sores.ms.so,es mi
. . ~ -- . . .- . , - , . , ,
INTERIOR SURVEY UNITS The results of the confirmatory survey of the interior survey units are discussed below.
Surface Scans Alpha, beta, and gamma surface scans identified one small area of elevated direct beta radiation, 2
measuring less than 15 cm in area, on the floor of the Main Condensate Storage Tank (SUO46)
(Figure 22). A second, small area of elevated direct beta radiation was detected on the eleventh !
panel of the west wall, west outboard, B side of the Main Condenser (SUO25) (Figure 19). All l other surface scans were comparable to background levels.
l Surface Activity Levels 4 l
l The results of total and removable surface activity levels are summarized in Table 1. Total beta activity levels for the structural survey units ranged from -800 to 2,100 dpm/100 cm 2.
Removable activity levels ranged from -1 to 6 dpm/100 cm2 for alpha and -7 to 16 dpm/100 cm2 ,
for beta. Structural survey unit means ranged from -290 to 370 dpm/100 cm2 and -1 to j 2
i dpm/100 cm for total and removable beta activity respectively. !
l Total beta activity levels in the surveyed systems ranged from -910 to 5,800 dpm/100 cm2 . The 9 removable activity levels were -1 to 4 dpm/100 cm2 fr>r alpha and -7 to 16 dpm/100 cm2 for beta. The mean beta activity levels for systems ranged from -340 to 300 dpm/100 cm2 for total activity and -1.0 to 1.8 dpm/100 cm2 for removable activity.
Exposure Rates e.l Interior background exposure rates ranged from 4 to 5 R/h and averaged 5 R/h. Individual gross exposure rates within the Turbine Building ranged from 3 to 7 pR/h. The average gross exposure rates for all survey units ranged from 4 to 7 R/h . Table 2 provides a summary of L
the interior exposure rates.
Shoreham hleer Power Station rebruary 3.1994 h:\eenap\reportswrehamWrcham.001
( EXTERIOR SURVEY RESULTS The following are the results of the confirmatory surveys of the exterior grounds and building exteriors. Surface Scans Surface scans of the exterior grounds, paved areas, and building exteriors did not identify any locations of elevated direct radiation. Surface Activity Ixvels Surface activity levels for the paved portions of SG003 and the building exteriors of SE002 are , 2 summarized in Table 1. Total beta activity levels ranged from -760 to 1300 dpm/100 cm and 2 2 removable activity ranged from -1 to 10 dpm/100 cm for alpha and -7 to 7 dpm/100 cm for beta. The mean beta' activities were 4 dpm/100 cm2 total and -1 dpm/100 cm2 removable for-SG003 and -T20 dpm/100 cm2 total and 0.8 dpm/100 cm2 removable for SE002. Exposure Rates Background exposure rates ranged from 6 to 9 R/h and averaged 8 R/h. The gross exposure , rates within SG003 ranged from 8 to 9 R/h and averaged 8 R/h. Table 3 provides a summary of exposure rate measurements. Radionuclide Concentrations in Soils Background soil sample concentration levels were less than 0.1 pCi/g of Co-60. The Co-60 concentration levels in the five samples collected from SG003 were less than or equal to 0.1 pCi/g. There were no other radionuclides identified, other than those occurring in nature. Shorebatn Nakar Power Station . Febnaary 3,19H 12 h:\canap\rqmrts\shoreharnwhorehant 001
ESSAP AND LIPA DATA COMPARISON Comparative field measurements for surface activity and exposure rates were made in one survey unit using the various ESSAP and LIPA instrumentation. Most of the measurements collected from this unit were comparable to background; therefore, a meaningful statistical evaluation could not be performed. ESSAP intended to collect an additional 30 measurements from areas where positive residual activity, that is survey locations where the reported surface activity levels exceed both the background distribution and the minimum detectable activity of the instrumentation, was identified by LIPA. However, a sufficient quantity of these areas could not be located to provide a statistically significant number of measurement locations. . i F The Co-60 concentrations determined by ESSAP in each of the samples obtained for confirmatory analysis were less than 0.1 pCi/g as were the results of the LIPA analysis. COMPARISON OF RESULTS WITII GUIDELINES The confirmatory survey results were compared with both the data provided by LIPA and the
- generic and site-specific NRC guidelines for release to unrestricted use. The NRC's Regulatory Guide 1.86 provides the guidelines for acceptable surface contamination levels used to determine whether a licensed facility may be released to unrestricted use. These guidelines are summarized in Appendix C. The applicable guidelines are those for beta-gamma emitters of which Co-60 ;
i and Fe-55 are the primary contaminants at SNPS. The residual surface activity guidelines are: ; I Total Activity { i 1 5,000 dpm #-y/100 cm 2, averaged over 1 m 2 15,000 dpm #-7/100 cm2, maximum in 100 cm2 i i Removable Activity 1,000 dpm #-y/100 cm 2 Shoreham Wdear Power Stenon - February 3.1N 13 h w wn.whom6moshoma.m.mi ;
l l As previously discussed, the detection sensitivities of the field instruments are such that the , residual Fe-55 activity can not be detected. Therefore, surface activity measurements were l l corrected for Fe-55 when appropriate. The mean surface activity level for each survey unit was
)
calculated and the survey unit data tested at the 95 % confidence level, relative to 'he guidelines, in accordance with Draft NUREG/CR-5849. These results are provided in Table 4 and 5. A comparison of the ESSAP mean activity levels to the LIPA mean activity level showed that in each instance the ESSAP mean was statistically less than or equal to the respective mean determined by LIPA for 16 out of the 19 confirmatory survey units. The ESSAP mean was greater than the LIPA mean for survey units TB017, TB089, and SUO54X03. For TB017 and SUO54X3, the activity levels were indistinguishable from background and the differences are [ therefore not considered significant. The differences in means observed for TB089 were the
~
result of a higher background' level associated with this room. LIPA established a separate background,189 cpm versus the 129 cpm background used in data conversions for other survey units, for this room svhile ESSAP did not. The ESSAP decision was based on there being no . indications of contamination (surface scans did not identify any locations of direct radiation and : all measurements were less than MDA) and the effect of using a different background was' , inconsequential, relative to the overall status of the survey unit. Surface activity levels within each survey unit satisfied the guidelines at the 95% confidence level. There were no measurements which exceeded the maximum activity guideline. Two direct measurements 2 exceeded the 5,000 dpm/100 cm average guideline, both of which were identified within affected systems. An activity level of 5,100 dpm/100 cm2was detected at one location within the Main Condenser (SUO25). The elevated activity was confined to an area of approximately 100 cm2 . The average activity within the contiguous 1 m2 area was 2,800 dpm/100 cm2 . The 2 second location measured 5,800 dpm/100 cm and was confined to an area ofless than 15 cm2 on the floor of the Main Condensate Transfer and Storage Tank (SUO46). The average activity in the surrounding 1 m2 area was 1,300 dpm/100 cm2 . All remaining total and removable activity levels were below guideline values. ' l Shoreham % dent Power Statma . February 3.1994 }4 h:\eansp\reponsJmrcham\nhoreham 001
. , - . . . ~ . _ , _- - . - - .
. . I 1
I Exposure rates were compared with those obtained by LIPA, and tested at the 95% confidence level, relative to the 5 pR/h above background guideline currently being used by the NRC (Table 4)'. The interior and exterior exposure rates were both comparable to the respective background exposure rate level and confirmed the findings presented by LIPA. . l Soil concentrations in the samples collected by ESSAP and the LIPA samples, obtained for confirmatory analysis, were compared with the 8 pCi/g site-specific limit for SNPS produced radionuclides.O The Co-60 level in all samples was less than or equal to 0.1 pCi/g. l
SUMMARY
i ESSAP performed confirmatory activities of the Turbine Building, site grounds, and site exteriors at the Shoreham Nuclear Power Station in Brookhaven, New York. Confirmatory activities included document reviews, and during the period November 8 through 12, 1993, independent surface scans, surface activity measurements, exposure rate measurements, and soil sampling, were performed. The survey results confirm the results of the LIPA termination surveys. These findings indicate that surface activity levels, exposure rates, and soil concentration levels were below the NRC q and site-specific guidelines for release to unrestricted use. Statistical tests of data sets further support the conclusion that each survey unit satisfies the guidelines at the 95% confidence level. i l l l l Shoreham Nudear Power Stancm . February 3. W ' 15 h w ,* w ns wh-ham.mi
)
- SHR15 1EW YORK
-m 4
l
/
/
~
esecu om. ciy;..
- SNPS .
;. ; . . . . . ::sfu.
. - SHorq$ -
. . . -l 2
, . [, '
^ M p [.
25 l 9' 2S 2'
' lN '
,, 2,
~
/,[
27 - YORK ' CITY y - l
)^ \
N:- 5k&Nd:h$U?-l. N U l l
'h i
]\
KILOMETERS 0 20 MILES RGURE 1: Location of the Shorehorn Nuclear Power Fiction s%.uw rm, saw . ran-y 3. m I6 aw,% %a,%%w
SHR31 e ,O o v INTAKE v __..._# ga a u 3 O, ] g-9 ' (41 - l I
!!"she i CD oT
., atx-*;d" 0Y $ ', [
~
D B"n ggy .
\ [ U ll II l v v v 1 -[ / x Mi
'} 44
(
^
k
- r \ Il 5 0 $ -$
tx ( y 3 m s l nr 5
] WATER v v g_ SECURED AREA gc
~ "
BOUNDARY FENCE 5p POWER BLOCK BUILDINGS TO _ BE ADDRESSED BY CONFlRMATORY N SURVEYS NOT TO SCALE FIGURE 2: Plot Plan of the Shoreham Nuclear Power Station Shonham Nmaar Power statum . February 3. Im 17 h:\e p\repor4.\ horehams.horchsm 001
SHR81 l l l 1 o
- I i
1 l 1 1 l l TB017 TB016 TB031 T8035 l
.. . .-h "
JM!:, ' T!!!
.N l
c d *~ i 'h l' 'l ' If3 j ' '" j Oj <'> b
, ,, ,, , !!K, f
, , ,, , i:;.in ,,,,n n , n , ,,i L
, , . ig: @, , pyj ,,
il.. . A . . . : . : . . . .. . . '.. %.tg g!g-' -- g g ;!!' - L .: :%.
"I ) _
I ', j i L'
~
[- !# d . l cn
,l' c'
, l' 6 p r" ' a s,
~
N A SURVEYED AREA h n FIGURE 3: Turbine Building, Elevation 15' - Floor Plan and Areas Surveyed 1
$hofthern Noclear Power Stanon February 3.19w I8 hhp \reporubhorchambhorcham 001
SHR80 TBOSO
^
f
-4 __j_- _J l
[. ' u p . F __ l _ n
~
ag D l l f I
/] i
- -- - m ID l
l 1 l i i l l N 1 h !
] SURVEYED AREA i
il I 1 FIGURE 4: Turbine Building, Elevation 37'6" - Floor Plan and Areas Surveyed sut=m %r rmr saw . Febw 3, wu 19 g _ ,,. y ,,, ,,
SHR79 i i i b ] l ACCES3 FROM ELEVATION 37'6"l TBOS9 l N ' j
%lY
~
1 b 1
' l L
-a
, , ,, , 4 ,
It- I II I I I I I Af' 1 I $ r1 1I I EI F II
. ,'i
- i:2:.
;g
.;!'4 thy ,, .i : ,o,,
H TB082 78081 1 i l l e N JL d.' SURVEYED AREA W N 1 1 1 RCURE 5: Turbino Building, Elevation 63' - Floor Plan and Areas Surveyed i Shorchar, Nmleet Power Semnon . I ebruary 3.1sm 20 h:se a*P\ reportadorcham%orehamR3 l 1 I
SHR78 BUILDING EXTERIORS SURVEYED SE002 COLT EMERGENCY CHLORINE GENERATOR BLDG. PUMPHOUSE x_. p U ' i k: '
.. r- :
SG002 l:: 8
/
/ l SG001 '* r- -
-- , l l s
,,j!]
l OFFICE F l a l A NE f}Lg SCOO7 5
,l l~ I f"'l - i s {J TURBINE ~~~~ k
. .-1 -
BLDG. l rn SG003' d RAD
'y-o WASTE a i
8 bd ._ _ , , _ , , _ BLDG.
~
/ .
N 8 SG004 hs! sM8 1 $ Q ', . '8 EACTOf} BLDG. SG006 1
)'
S s f **
\ . -- /
i
~,SG005 ;
p.- N ! l
- - - - SURVEY U NIT y BOUNDARY A
39 g SITE GROUND SURVEY UNIT , SURVEYED AREA JL
" T DESIGNATION SE # BUILDING EXTERIOR SURVEY UNIT DESIGNATION j(
FIGURE 6: Shoreham Nuclear Power Station, Restricted Area - Exterior Areas Surveyed Nrshern Nwleer Power St.6on - February 3,19* 21 6:se ,s, ego,s.s. sores 1.aores .coi
SHR63
.)
l l NORTH WALL FACE )1 3, + g A j
...y...__....y...._7...,... ,
8-.
. i_ . . I Ai i
, e i : ; i i j j i ! i ! !Al i
...! .. . ;l . .A. ... .... j .
_. i.. g . .. i .. . i. .. .. 4 ._.L.. 4 . .;... ?...,4... 4 . ; ..L.. .1'...L.. .; .. .. ; . .L. ...i . . i.. 1 I wl ' - i ! ! ! lAi
- 3 i ! i i i ! ! ! I i i ! l i
' .. 4.. . !. ,.. .l . LA.. i .. . 4.. . ...i . ...l.......i. A.' 4 . 4. _4 ..i. .. .i' ....j. . { . ..i; 4.. ..i.. _ }. . j I ; e i. i 4; i. ', ,' I, !
l t i
! e i, ,!
i _4.A...i.. I i o .. . p.
. 2
.;.... . .. p . . 7. . 4. . .. j .. ..) . ..j!. .. .j ...... j .
. 4 . ,i . . . j .. _. ..j .... . ,.4.. 4.. ..p... q ;
5l l . l : :
! i ! * !. ....i. . %. 4 ...
.. . .p.
.i p, .
.. .it i O
.. i .. l y l
. 4. ,..;.,
--.. g +....q. ' . 9. - . ...;
. .. p._ .
- .. 9. . , m i
j -
! I ! ! ! ! . ? :e ! ! I m U;
o J ..~.g.._... ;_1 L._.4 p , . o.. i.... ',. , . . L. ..
, ,. q...{. , . 4..l g H
I .. .;'
! *..!.. . ..;.. . w l s ei y,. ._.!,
i
. . . . . .. e I i 3.._. 3 .J.. ,! !
_3.. ..i.t !.. I e FE D i #: i i O I i 1! I l l l,
, , , , , , , , , , , i i i a i i i i I i iAi
...,...4.- . a... . 4. .- . . . . ;...,... 4...4...._; ..+3 . . 4.. . 4 .+! ..
. i i ! I i l i i i I i g i i _i i i i i i i i }' i i M s * -
i w
, y y v I
WEST y SOUTH WALL l y! , WALL FACE D FACE (WEST) ; 3 !
! "?,
A !
. </, EAST-
<? ' a" WALL FACE I i4 E i~' B H""~i ' ,
j... , d C i !' ') F lll ! # i I l 1 i 1 l 1 N \ MEASUREMENT / SAMPLING . i U ! LOCATIONS I JL SURFACE ACTMTY AND T g EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - g FLOOR AND LOWER WALLS O 12
~
$ SURFACE ACTMTY ONLY - '
UPPER SURFACES AND EQUIPMENT 6 4 -! METERS I FIGURE 7: Turbine Building, North Condenser Hallway (T8016) - Measurement and Sarnpling Locations shoreham Nuclear Powr.r Statma - February 3, im 22 h:s ptrer,xi.w, h. w cham. con
SHhS8 NORTH WALL FACE (WEST) it l l l EAST WALL
, ~i FACE (NORTH)
, l NORTH WALL b ,s FACE (EAST)
WEST WALL ss FACE (NORTH) ; i
- p. ..+.._
. AEC..I - v- r-- - - - -
I !
- i . . . . . . . . . . . . _
i
- 3. . . . _
.j . ;
, , A!!
l A i
- 7
_.+.. _ _
,1) l '
- l , i
.,.. ... _, i.
; .. ._7.._...
I e
'e A
., i l.
'_4 , .. ._ ..
I - l
+ je ^
[-
' i
. ..j . _ . .. i .
.4 .... . . . _ . . . . +
TO TB018 I e; , ; , l n
, _..p... _ _. ,_
g __ - . . .
! A i
_ . . . . - ..I. . _ .ig . _ . . . . . . .
, ; e , _
l t t . i A WEST WALL I-- -'- * ~ " FACE (SOUlH)
.4..,_
l {o . , _ j , hw)Ajp_ _ i j ,
.7. ,
EAST WALL FAC{:
; * ' i
.e..,....i._
+ l A
..... .a .. ..-+- SOUTH WALL
,e , l ! ! FACE (EAST) 70 '
A
- A A l l l
7_ t
! A A
~ ~
~
EAST WALL (~
~
SCUTH WALL FACE . .
'i"~ - [~ FACE (SOUTH)
V Y !. !. N MEASUREMENT / SAMPLING 3 LOCATIONS
.E.
SURFACE ACTMTY AND 7f' g EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - g FLOOR AND LOWER WALL.S O p 4 SURFACE ACTMTY ONLY - UPPER SURFACES AND EQUIPMENT O' 2 METERS FIGURE 8: Turbine Building. West Condenser Bay (T9017) - Mecsurement and Sompting Locations shoreham Nmicer Power Statwa - February 3. Im 23 h:1e- pterven.s. seres.ms.sercham.ooi
SHR$9
% 4 '
NORTH WALL FACE
, , , i ,
.4 . . .p . . . 4 . . - _ .4 _ - .g . 4.
i NORTH ! , l l WEST WALL WALL FACE o FACE DOORWAY WEST N ' k ' WALL -
~~4"~~~
FACE [- - - - ,j
. f' ._ j j
. , . . . - . . ... ,-...;...- ; 4... --
i i i
+ i
' l
, .. - l l !# '
g 4- _ ,
, e
_ll '$ ' ' _ /p! H $ i l ! ! i
. ,i
//
. . 9. - -
S l g i.. -.t.
,' -,... . .. j . .
, .1..- _ i.. _. 4 . i -.; 4. -
' ' ' 3
; i , , ; , ! !
O ! A 4 - - . . . . - - .
......-.r--
N i ! j
' ' ,O i
$ y. .
f
, 4
_ . i . .. _
. l g .. . . - .l..- _...i...-.... .- . ; ,-
, , , , e e
l l # ! j # l > l' 4i ,'/,,,, YvEST WALL FACE , , i , , , , EAST WALL i : ; l SOUTH - --. - - i -- 4.. . - r - - --,- -- . ..- - ..- -l - - .+. - . .. j FACE . WALL = i = i > i i FACE l m. l
..d.........;..
lA l l
.d. .
l
^ 1, -
.1-O -.. Ck 4 ,
k i t t t i : 1
.{ -
,_,4. ,..,,_,,,t,
, , , l A . . . i WEST FACE OF SOUTH FACE OF WING WALL y,mG WA1 i NORTH FACE OF WING WALL MEASUREMENT / SAMPLING LOCATIONS fA JL g SURFACE ACTMTY AND T EXPOSURE RATE - FLOOR SURFACE ACTMTY ONLY -
A FLOOR AND LOYER WALLS N
$ SURFACE ACTMTY ONLY - 0 6 UPPER SURFACES AND EQUIPMENT ; ',
O 2 METERS l FIGURE 9: Turbine Building, Steam Seal Evaporator Roorn (TB031) - Measurement and Sampling Locations
$borcham Nuckar Power Statmn . February 3.15m 24 haes.aphrortswrchamWrcham.001
- ~ - - _ . _ . . . .-. . . - _. ._.
l SHR64 i l l 1
), 1
..i .
.L. i
..h,.. l .
.! .I h 1
i r7, : ; , ... . ... , , I .,-.. 7 ., ,
.; i ..*i i : : .
[....... .. ... g. q. . 4.. . 9... .l l . ! l 1 i
- l. 4 .. L. ..,...:..........i......;...... .l
- j. .!.. .pl . l ...!. .+!..I . l: 3..
4 e
.l
!. i
..+...;..u...
i i - i
..+..
- l. ....
..l i
- i i .
- j. p !. ...i..._:...>...4..... . . . ..l l
.. ; i 4
...l,...
l ...!
.y. .l i
l...L. a .. 4 .. .I t ..ip.
.1.a.. i i..p..
p.. t .. 4.. . .. .I . . .
.! : ;*' A I. ;: .. 7 . . . . ..j .. . . .;. ; .l _
i i i !
.... I ...a... .
-3.
. . y.._. .... .; .
] ,
<a. _
, . . ..,i . . . .! . - !
.. l !
.+. ..;_.4.... ...I. .....a.....J,... .
]
- i ; i .
. . 4 .. . 4..- t .
. 4.. .
.l Ai : .
a._ . . _ . .
..,..1.._......,.. . . . .
.I
. .i .,. ..,....4.... . . ,i.... +i..*.. i l
l l l !9 I
... .;.. . ..t . ... t 4. .. . p. ..,
..+.. .
.l
.l
.4 .....;., . ..
.i
. g ..
i ! t i ! . i. . . . . . l. - p,. . +. .
! l l ' l -
l
-- N ;
I ! l 4..+....+. Ai -4 4 Al. (
. . . . . . . . . .h.......
y 3 N d 1 i MEASUREMENT / SAMPLING - LOCATIONS : g
- FLOOR TRENCH SURFACE ACTMTY AND -. WITH GRATING ,
9- EXPOSURE RATE - N SURFACE ACTMTY ONLY - FEET A LOWER SURFACES : o 12 9) 0 METERS RGURE 10: Turbine Building Truck Bay (T8035) - Measurement and Sampling Locations Shoreham Nclear Power Statma . February 3. Im 25 6 se
. ps,epo,s.s. seres.ms.ao,,s ooi
1 SHR70 l 1 i e e
)
l
<D /l' xr--~ ,-
, .g... ,- 1 p.. 4 i i l
,N S I let - -
i N j.. . . . i ... j_ . . . . 7,_.' .-{
. .j.. . ..] (g g i- l ! ! l0 ....! ._ !.. _
.!.. . . 4. . . 7.. ....p..,. _
; . . .g .
N r : ,
.- i. <
s ._i....
, ..g .. j. . ...p. .; ;
b ' _ .i i. a . .s. . . ..
. . 4 . . . i. .*._'t .!.....!-p .. 4...
y ' - , _, ,e . c -
*\ ' ' '
, i wu ' C " ! l
.1 ._ h . ..b
@ , i. . . ;.; j.:. . . . . . . j +i an c.
r, l t
- - F-r ,
, 4
, , . . _ . .. 4 . _ . , - _ .i 1
- , l. ,
(\ # l l....'.. , . . .
- 9. _
.. 9 , ,
l
' ! 8 l l
... . .. . y. . . . . .p .
.y (I_ . ., . . ;_.h._..,. I
.q .
- c. .;
_..y. . 9.. l 4
! l
?
i p
. 9..
[ _ j .*.j. _ ..j._ .-}... j ...4.[ .
**
- L *
- i ,
i ; : . A !
- 3. _ . . .4.- ..+., ..t.. .!
i i i ! t I ! j... . ;.. i. . .4, _ _ .. p. .. q. ,
.. i._s ei ! ! !
-..._.. p , .. j . . 4. .... . . . . . . .
, ir i : ,
.. ; _. . .. j... . 7 . i._ .ip ..... ... j..
l i l i ;
,....4..... ........_+..e... '
..4....
i i i ! ! [ -
-1.
c::
.i Q
L_ ..j.
...i..
A
)
Y,' k -.. , s
..1 4 'h N
MEASUREMENT / SAMPLING A LOCATIONS 46 v SURFACE ACTMTY AND O EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - A FLOOR AND LOWER WALLS 0' 12 4 SURFACE ACTMTY ONLY - ' UPPER SURFACES AND EQUIPMENT 6 4 METERS FIGURE 11: Turbine Building, Chemistry Laboratory (TB060) - Meocurement and Sampling Locations shorcham Nudcar Power Stauon Icbruary 3, im 26 W apryr h uhniW rdam.M1
. . . . . . ._ - . .. - - . . . . ~ _ . - _
' SHR62 EAST WALL FACE J-
. t .J'
.;.... .. 7,
....,...p...v....p....,.-
, ! , i i .
! ! ! ! i i i, .; ...
I I IA l ! i To SOUTH WALL TB078 FACE (EAST) I
! !' I !$j i i i i i i' r
. . . , . ..j... .L ..L l .j... j ...j. . . . . .
. .d j, j;
I
?
l t _ '..- . . . . .. ; 9 A l.. . C A !
' I
.a... % . ..._. i.. . . l' ...
e
- j. ~ '
i 2... i TO e e; jgl .{g l l !
;A ; ;
- -4 - - . , . - - . .. ; .. . .L. . 9 . - - -- --
A TB080[..4.. : i. >
- l. . . . . .. .. .. .
. . . , .. i . . 2. . . . . . . ..l.... 1_ . ,
e- {. : : :
; : : l 1
..4.....
. . .y ..: , . . .
.q.- . . . . ..a.
j, j; l l
,. .._.j......,, . . .i,. 4
, , , i i i l !
..j .
' . .l ..,L. .j. . .
AjA
...j . .
- -j-f"-
t i
! j i e . .L..
_ ..; . . . j .. . - .j . q
. , , s
! t ! !
.j..- .;- ...j...... . . . . .
..g .o
! ! $11- A!
i
.3 i ! ! .#3- lA l i
j jA l
- g. A, j
. 4. .
j SOUTH WALL FACE
-l
..y. . j. ._4 . ...q. ..; . .
_ 7 .. 7. 3.. l I i
..a..
i
.4...
i
. ' . . .g!'
i _ ...,. . ...,i..... JAI , I g . . ... q... .;. . ;
. . . . .. . _ ,.. 3
! i i A !
.x.w .- w.n . - ~ .
~3 To TB082 MEASUREMENT / SAMPLING LOCATIONS n
, SURFACE ACTMTY AND EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - N '
FLOOR AND LOWER WALLS FEET O f2
$ SURFACE ACTMTY ONLY -
UPPER SURFACES AND EQUIPMENT METERS FIGURE 12: Turbine Building, Reheater Area, East (T8081) - Measurement and Sompling Locations Shonham Nwicar Power Statum Fet.ruary 3,1994 27 h:\ensap\ report Morcham%ortham.001
- . . . .- .- . . ~ . . . - _ - - ~ . . . . . ~~ . .
SHR61 5 /- 5'> M 'A 4 A A ,O- N M
/ / /'
, s /
. , . . . . . . . . . . . . -..-+..a *- **
4..... . . . . . . . . . ,
! ! i i i A
..-......4..-i 4... .; . . .;.. .. y . .
+.. . ..
! ! , i l !A I D E F A B C
% b e ,-
; i , , l NORTH
_.4. j .+._..-..;-. WALL I j iAi l } FACE !
,s T8080 1
i -
- i :
3 2 ; 1 I
...I.4... f 3
. . f ... . I,. . ..,!. . f
. . ...!. i
..gl. . !.., !. !
- 4. . ....p.. . .{
b Ib i b i I
- l. . . . . . .
..7.. .g.... .. . . . . -
.p.........{.. . ., ........i....,,... ..
.)
I ' ! j ' ! *
! . 8 ,
- a. -,
.,..-.g.,.,l....3 ,
.,.....e 7 *....y... .;
e i i . I i I I
^
[
.. .j. - . . . _ _ -. ...!... _ .. 5p . ... q.. . .. i. -
5 7 .. 7.._ 5.. . .. ..} i i AI I TB081
.....p... - - p.. . _ ._ r. . J.,.....p.p... .i . .{ ... . ..J
. i ; 8A ! A > i i !. A tr i ;
I
. .i........
p .....j [ [... ; .... ..q. ....y.
.[ .. 4.... . ... 9
- 5. . i .
7
? - !...b.. . .... . . .
. . !. / i i i i i i ! [ ,
i .!
,,7 * *
. . _.. . . . . . .. ' '. ; f'. . .. .. . ..f . .f.-
... . .. . .. ..f.. . l WE5T B EE ']E EI I ED JD FI - ! ;--4! --lI WALL A +--t r!~ - ~
, , , -- t - i ,
J FACE i . ._ :,.. . . , . . FD . . . . . .. ! . . ..! ! I! ! ! #i * ~' i 1
, l ! l l l lo!.s^.Ei l i ...'T~s'"'"'l i ele" *l ""'"'I I i
- : ! l'
.4 ! .!... , .
I ! ! A l
.. . t . . ; . . . . . . . . .
SOUTH WALL h hNORTH 1 WALL FACE (WEST) FACE (EAST) 1 l 1 1 MEASUREMENT / SAMPLING ! LOCATIONS h , 1 g SURFACE ACTMTY AND h EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - g FLOOR AND LOWER WALLS 1 l FEET ' t SURFACE ACTMTY ONLY - 0 12 UPPER SURFACES AND EQUIPMENT g 4 ME1ERS 1 1 1 I FIGURE 13: Turbine Building, Reheater Area, West (T8082) - Measurement and Sampling Locations Shorcham Nw. lear Power $tadou - February 3,1994 M b \essap\reportninhoreharn\shoreham.001 r--'w-
SHHb0 e
- N NORTH WALL FACE
\} *
['/
,i .
i i l A DOOR TO TB022 3'N V, , , i ! A , . y! l l i i /[/ /
, ; , 4 , I 4g.
4 .. 4.. q - . . l. ..J _ { - DOOR i TO
! $# # i :
# [ TBO91 4
- t. .. , ;
- ! l l .! I hA - - . . . . . . . . .
- - - . . . . . . . - 3.- -
. !., ; A i ,
!.i !.
.L. -
.p . . . . . . . . , . . .
l ;
- l #
j ,. ;. . .. . .3... ....} .. . _ . 4...l --
. 4 l. . . - - . - -
,,4 ei -
iA i -
- i
- A
; 4 7/
WEST WALL FACE EAST WALL FACE Y DOOR TO TB090 l 'A
- b ... . . .. . . t I
.a
'a.. .2 . .. . . . - . -
,x #
\ /
SOUTH WALL FACE N MEASUREMENT / SAMPLING LOCATIONS U g SURFACE ACTMTY N1D h EXPOSURE RATE - FLOOR g SURFACE ACTMTY ONLY - M FLOOR AND LOWER WALLS
@ SURFACE ACTMTY ONLY - 0^
6 UPPER SURFACES AND EQUIPMENT b METERS FIGURE 14: Turbine Building. Bicek Bottery Charger Roorn (TBO89) - Moosurernent and Sampling Locations Shercharn Nate r Power statwn . February 3,15* 29 hw e recerie s horen -t horch =.oot
SHR82 .( ,
..[._ .1 i
r
- 1. 3 i
- . 4. ... ... j . _ . . .. L _ _ . . .: . - . . . L _ .
l l l l
- _ . . . , . - - . _ . _ _ y . .. .-
$j !
. i. i
_ .j .. , > .L... .. i i t ) i
' l 9- :
_ __ __ ._.._..a... 4. . . . ..p _ -.i . . .
, , I
_ _ _ _ _ _,-...+..__4..._.. l4 # r 3 M ! e
...s_. . . . _ . . . . .
1 1
,i . . .
u 1' . .
- _. 4 ... a .
i . :) ; i ii _ j l 1 1 N h JL 7r MEASUREMENT LOCATIONS
# EXPOSURE RATE N O. 2.4 6 s i METERS l 1
I FIGURE 15. Colt Emergency Diesel Generator Building - Background Measurement Locations Shercham Nwlear Power Station hbruary 3.1%8 30 h:se pireimt.t.horehams.horeham.001
SHR66 r -, e c > L , _J
'a c o C _a Mj
- e Id n *
( --) e I
---~ y _ , _ _ _
1
/
~ - ~ ._ / ( % .)^ (__
MEASUREMENT / SAMPLING LOCATIONS 9 SURFACE ACTMTY F10URE 16: Turbine Building, Feedwater Control (SU005) - l Measurement and Sarnpling Locations , 1 Shoresam Nuclear Power Statmn . February 3,1994 31 s:1c .,1,,po,,,1 s ,,s.ms.,,,,, sam.co: I l
_ .. . . _ . _ . . . _.. _ _ _ _ _ _ . - _ . . . . . ~ _ . . . . _ . ._ _ ... -. ..._. - _ - -. . . - . . _ SHR74 NORTH WALL p 9 ON LEDGE I 2 A WEST WALL g g EAST WALL g FLOOR i 4 SOUTH WALL , M EASUREM ENT/ SAMPLING LOCATIONS S SURFACE ACTMTY - NOT TO SCALE FLOOR AND WALLS A SURFACE ACTMTY - TOP GRATE l FIGURE 17: Turbine Building, Radwaste Interior Drain Pipe System, Tank 12 (SUO14X03) - Measurement and Sampling Locations
, Shoreham Nulear 14wer Stanon February 3. Im 32 h:\emp\reporWhoreham\shercham.001
SHR89 .. . \
\- .l
.D m
I ll I /
,L i \
l
)
** tJ Li v/., l V[- b
! [\, _ _ e/NIh ,/
,f ,
8d , _ _ ~. __ l
, _o
(- ,-r , - f', / f~ - f~' I \l 'j' \ I i yr >
\,I =
b 0' ' g / ~ ' f' ~ TERM CV2 e STENA BALANCE HEADER, f 3 MA!N STEAM LINE l
.x 25 N- 1 \
, veio l 2 ~
- Q l i .
, #1 CV DRAIN LINE FLANGE VALVE 1N11-084-012 e
e E f
,=
5 /
, .- - ( l
/ *
'/ ~~
./.
63' LEVEL, N11 MAIN STEAM SOUTHEAST CROSSUNDER PIPE l MEASUREMENT / SAMPLING LOCATIONS NOT TO SCALE 9 SURFACE ACTMTY FIGURE 18: Turbine Building, Main Steam Components (SUO24) - Measurement and Sampling Locations Shortham Nxtrar Power $'ation Febnary 3. Im 33 6:1 pstree,s.t. sores s.horcham.001 l l
SHR76 e . 8 SIDE
- t. oureomo L INDGARD W. OUTBOARD w reoAno l '
u 9__ U . 4 C
* --*- A SIDE A
3 . b l SUMP ROOM A B C D
. l PANEL 10 PANEL 11 PANEL 12 PANEL 2 N -.-- N -* - N -* - *-N l
l
)
l l l I 4 N j MEASUREMENT / SAMPLING n LOCATIONS _4k
~) r NOT TO SCALE g SURFACE ACTMTY -
FLOOR M4D WALLS .. A l FLOOR i FIGURE 19: Turbine Building,15' Elevation, Condensate and Feedwater, Main Condenser (SUO25XO2) - Measurement and Sarnpling Locations Shortham Nmlear Power Stenon - 1:ebruary 1, t994 3t 6: 1 es repori.s.soren.ms.wo,es...ooi
SHR72 e e hs N l *
/ I l 5 FEET
/ I
/ /
l ,
/
/
' 6 FEET f
/
/
/
- 6 FEET -
MEASUREMENT / SAMPLING LOCATIONS g SURFACE ACTMTY - WALLS AND FLOOR N 4 -h -: l g SURFACE ACTMTf - - CEluNG l l FIGURE 20: Turbine Building, Lube Oil Sump Tank 91 (SUO32) - Measurement and Sompling Locations ; Shorch m Nuclear Power $'. sten Febru ry 3, im 35 6w e terers.1.wo, s a.ms. sores .coi l
SHR73 l l l
"no O _o .o .S
*NfG" 0 _ yA N s__.
/
I \g 0-n
/} ~
0
. (\ 0 c _I- .o O
TEASUREMENT/ SAMPLING LOCATIONS NOT TO SCALE e SURFACE ACTMTY FlCURE 21: Turbine Building, Extraction Steam Volve 035C (SL1034) - Measurement and Sampling Locations Shorth ru Nudrar Power Statwn - Febru.ry 3, im 36 6* ps,ecort.s.imres.ms.ao cu.m.ooi
4 4 g 9 g
'N A
. . .\ ,JL
, e N e e y e u
- O ,
4 TANK FLOOR DOME LINE r_____________________________ _______, 1 I l l I i , 1 i I 1 l , I I I I i i' I I I I I MANWAY l l 3 *HY = + O Og ; I
- ei i
. li _. . c* 4o* y TANK WALL (ROLL OUT VIEW), I N
MEASUREMENT / SAMPLING 0 20 LOCATIONS O PIPE PENETRATION SINGLE-POINT 0 6 9- LOWER WALLS AND FLOOR METERS h FIVE-POINT l FIGURE 22:. Condensole Transfer and Storage. Condensate Storage Tank (SUO46X02) - i Measurement and Sampling Locations j 37 hw w r ort,. I Shorchem Nucirer Power Station February 3, im r sons.mwores.m.wi l l I
1 SHR75 I 1 l l i e
+
9 A # 4 9 e MEASUREMENT / SAMPLING y LOCATIONS h g SURFACE ACTMTY MEASUREMENTS 3g WALLS AND FLOOR 5p A SURFACE ACTMTY MEASUREMENTS CEILING , l\ 4 SURFACE ACTMTY MEASUREMENTS EQUIPMENT NOT TO SCALE FIGURE 23: Turbine Building, influent Drain System, Low Conductivity and Salt Water Drains, Tank 1868 (SUO54XO3) - Measurernent and Sampling Locations Shoreham kcicar Power Statum - I'ebruary 3,1** 38 6:1, ps,,po,1,s,so,,s.m1,no,,s .o03
SHR71 2 9 LOWER l 4 9 DUCT 49 LOUVER WEST 1206 2010 19 LOUdR
$ 29 LOUVER
[ 010 EAST 2 9 DUCT 2 9 DUCT 14 LOUVER a 29 DUCT n U:'.J e m 2408 2415 1206 2 9 DUCT C 19 LOWER h
- 3 9 INSIDE U4TME 19 LOUVER 2 9 DUCT 19 LOUVER El ROOF FAN INTAKE R
WEST If,08 1608 EAST 1 3 i d _ _ = , i h =, a a O O O 1 1 N H MEASUREMENT / SAMPLING JL LOCATIONS T E 9 SURFACE ACTMTf h NOT TO SCALE FIGURE 24: Secondary Access Facility, Ventilation System (SUO71) - Measurement and Sarnpling Locations s w h= Nwie.rrue,su6=.tchm.,ys. m 39 u ,wpo,.w,,,w.uso,umi
SHR83 L _{L. .jj N
- T*
_. I p 3d E F
'n
'll _
m _ 10 l ELEVATION 37'6" Jg C.1% [ [ w- ap I m .I o oo r
- u a
Sj , n_; . *n n'n n j 9E '
,*t L E :
aj
**r T i
,7 ,
~e Cf gI ~# 9
- _ ELEVATION 15'0' I l
MEASUREMENT /SAMPUNG LOCATIONS H
$ DRAIN MEASUREMENT E VENT MEASUREMENT h
FIGURE 25: Turbine Building,15'and 37'6" Elevations - Drains (SUO14) and Vents - Measurement and Sampling Locations Shorchern Wclear Power Station - February 3, Im 40 6:s ps,,,o,,,s,so,,s s.so,,s,,tooi
SHR68 L K E D A [ P h )r L C JL J Y H 0 I B h t F 1 N A WEST WALL FACE
-[ i[ ~ ~ ]-- 1
~~
-1 f-- ff 1 f-( p 1 H G E F D C B NORTH WALL FACE
, . _ .. __ _.__ _ . _ .___ .- _ . _ . _ _ _ l _. _ ._ _.
J K EAST WALL FACE
~ ~[~e! ~ ~ T-- kl[ e~
] ]
P O e l- ~ N M { L SOUTH WALL FACE i i l N H JL i MEASUREMENT / SAMPLING T ! LOCATIONS S SURFACE ACTMTY A FEET $g 0 ] m O METERS 6 s FIGURE 26: Secured Area, Colt Emergency Diesel Generator Building Exterior (SE002) -- Measurement and Sampling Locations 5hortham % clear Power $wm - retiruary 3.1994 4I h;\emap\reporu\shorehambhoreham.001
SHR69 4 a i l 8 E F
- h A '
A e C _ --- '~ ~ T *~ ' ' ~ ~'e~ M~~~~Q e ,_, 1 D WEST WALL FACE I i l i 1 __ B __
.---~~I-~ e .I--' - -- - - l - - - -~ ~ T -~' ~~ ~'- - -'~ r -~ ~~ ~~, 7 ~'~
~~~~ ~
~,-
i i i i -- l i SOUTH WALL FACE l i 1 C _.q__________ _ . _ _ . _ .___-____ __ t=3 t==p 9 *
- EAST WALL FACE D
_-.___,__--_m__--_7--...- oc- a t= = q t==4 F EET t-! 7 i.._..; i.--
.,7
.m'
_ - - - _ _ . ~ ~~~T*~''~~~~- SOUTH WALL FACE E F G H WEST FACE OF EAST FACE OF EAST FACE OF WEST FACE OF WEST WING WALL WEST WING WALL EAST WING WALL EAST WING WALL N 1 JL MEASUREMENT / SAMPLING T LOCATIONS 4 SURFACE ACTMTY j( FEET 0 18 0 METERS 6 FIGURE 27: Secured Arco, Chlorine Purnphouse Exterior (SEOO2) - Measurement and Sampling Locations j Shercharn Nudeur Power stanan . February 3.1994 42 b:\essapireports\shorehemishoreimm. 001
SHR67 BUILDING 29 - - . + - - - -
; i : - i,
;._ _ ,i.
....__:...', I i \
- 4. . g . ...... . . . .
2 . ;
\
outm o si g3
; BUGING 30 l
_j " . . ' . . ..g
~ . .,..; j
\
. g.
; \
l \ ,
; \ ,
. j... ,. , ,
...; . .......g........
i ,*t' _
\
m4 . . t g i :e- :e: . !: * . j.. " . . 4.. . - j. .. -g .g . .... . i ! I- l \ 3
\
!. l*.. .....e
. *.* *ai l g(,, l i_ ' g. . . .
.q _
.Q. . . . -
x 'x x x~x k x x g
>l
\ ,
t
>l I
\ \
- *' s2 Y5 Y x
N h L MEASUREMENT / SAMPLING qI LOCATIONS
-X X X FENCE e SURFACE ACTMTV ,
d
]PRED AREA N SURFACE SOIL AND 0 FEET 60 EXPOSURE RATE .
6 2'O METERS FIGURE 28: Secured Area West (SGOD3) - Measurernent and Sampling Locations Shoreham Nudcar Power 5t.tmo . February 3. Im 43 sw.ps,epe,1,1.soresamsso,esam.ooi
.SHR77 SH0R HAM N L po, p s AT O, LONG ISLAND SOUND
=
[6 NORTH COvfqg Hwy 2' ? h,+: 5 254 l WILDWOOD k STATE PARK o SOUND AVE. __ f et 4- . h$ E yV 8g ? S o ICALVERTO'N'
$ , NAT10NAL : 2 p [ .EIROOKHAVENST. PARK . g 1 CEMETARY' W o E C' @ --
y \ . 5" ROAD S COUNTRY l N MEASUREMENT / SAMPLING h LOCATIONS JL
'7F 4 S EXPOSURE RATE AND b SURFACE SOIL MILES
.0 1 6 i KILOMETER 5 FIGURE 29: Background Soil Sampling and Exposure Rate Measurernent Locations
$boreham Nuclear Power Stathm February 3,1994 44 b.\ensap\reportsinhorcien\nhoreham.001 l
l
l p TABLE 1 8 I ,
SUMMARY
OF SURFACE ACTIVITY LEVELS
,fr TURBINE BUILDING, SITE GROUNDS, AND SITE EXTERIORS ;
} SIIOREIIAM NUCLEAR POWER STATION
[ BROOKIIAVEN, NEW YORK f i f Location" Number of Total Activity Range Removable Activity Range (dpm/100 cm 2)
$ Measurement (dpm/100 cm 2) g Locations Beta b ip a* d h
TB016 North Condenser Hallway 30 -570 to 440 -1 to 4 -5 to 4 TB017 West Condenser Bay 30 -680 to 290 -1 to 6 -6 to 5 TB031 Steam Seal Evaporator Room 30 -290 to 860 -1 to 4 -4 to 7 i N TB035 Turbine Bldg. Truck Bay 30 -690 to 440 -1 to 4 -5 to 7 TB060 Chemistry I2boratory 30 -430 to 770 -1 to 4 -5 to 6 TB081 Re-heater Area-East 30 -800 to 2,100 -1 to 4 -7 to 16 TB082 Re-heater Area-West 30 -540 to 470 -1 to 4 -4 to 7 i TB089 Black Battery Charger Room 30 -140 to 1400 -1 to 4 -6 to 7 y SU005 Feedwater Control 5 -680 to 80 -1 to 1 -5 to 3 f SUO14 Influent Drain Piping 16 -730 to 040 -1 to 4 -5 to 5 SU014X03 Tank 12 6 -650 to -340 -1 to 4 -7 to 7 , SUO24 Main Steam Components f 30 -720 to 320 -1 to 4 -7 to 7 i SUO25X02 Main Condenser TB-15 30
-910 to 5,100 -1 to 4 -5 to 8 h SUO32 Lube Oil Sump Tank 91 g 3 -570 to 230 -1 to 1 -4 to 4 SUO34 Valve 035C 3 -490 to -460 -1 to 1 -1 to 0 m ____. -_.__ _ __.mm __ m_ _ _....______s.___ _m___ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ i___________..___ ._.-__:_ ___
.~
TABLE 1 (Continued) I i
SUMMARY
OF SURFACE ACTIVITY LEVEI.S I TURBINE BUILDING, SITE GROUNDS, AND SITE EXTERIORS ! k SIIOREIIAM NUCLEAR POWER STATION
! BROOKIIAVEN, NEW YORK F
i
? Number of Total Activity Range Removable Activity Range (dpm/100 cm ) 2 (dpm/100 cm2) $ Location
- Measurement E Locations Beta b p a* Betad SUO46 Condensate Trans and Storage 30 -390 to 5,800 -1 to 4 -7 to 16 SUO54X03 Tank 186 10 -610 to 470 -1 to 4 -5 to 4 SUO71X70 Secondary Access Vents 30 -600 to 270 -1 to 4 -4 to 13 s SE002 General Bldg. "A" Exterior 30 -760 to 270 -1 to 10 -4 to 7 SG003 Secured Area West, Paved Area 30 76 to 1,300 -1 to 6 -7 to 7 Miscellaneous Turbine Building Vents 4 -400 to 240 -1 to 1 -4 to 3
" Refer to Figures 7 through 14 and 16 through 28.
6 , MDAs = 990 to 1300 dpm/100 cm2
*MDA = 12 dpm/100 cm2 d
7 MDA = 16 dpm/100 cm2 i i T ' 1 I F a a
i . TABLE 2 INTERIOR EXPOSURE RATES TURBINE BUILDING i SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK l Number of Exposure Rate Range Location" Measurement Locations
"'
- l Ilackground Ccit Building 10 4 to 5 Turbine Building TB016 Nort*i Condenser Hallway 9 3 to 4 TB017 West Condeiuer Bay 6 4 to 5 1
TB031 Steam Seal Evaporator Room 15 4 to 5 TB035 Truck Bay 24 4 to 6 TB060 Chemistry Laboratory 13 5 to 6 i TB081 Re-heater Area-East 12 5 to 6 TB082 Re-heater Area-West 10 4 to 5 TB089 Black Battery Charger Room 12 6 to 7
' Refer to Figures 7 through 15 .
l l i l Shoreham Nuclear Power Statme - rebruary 3, IW 47 Messap\repodwhorcham\shoreham 001 m - , . . - , . . --. . .,m - . . . - - . , - - 1
TABLE 3 EXTERIOR EXPOSURE RATES AND Co-60 CONCENTRATIONS IN SURFACE SOIL SAMPLES SIIOREIIAM NUCLEAR POWER STATION 1 BROOKIIAVEN, NEW YORK Location" Exposure Rate at 1 m (g'R/h) Co-60 Concentration (pCi/g) Ilackground Location #1 6 < 0.1 Location #2 7 < 0.1 Location #3 9 < 0.1 Location #4 7 < 0.1 Location #5 8 < 0.1 Location #6 9 < 0.1 Secured Area West (SG003) Location #1 9 < 0.1 Location #2 8 < 0.1 Location #3 8 0.1 0.l b Location #4 9 < 0.1 -l Location #5 8 < 0.1 l
.i
" Refer to Figure 28 and 29.
b Uncertainties represent the 95% confidence level, based only on counting statistics. l l Shorehnin Nucker Power Statma - rebruary 3,19N - 48 h %spireportshhoreham'whoreham.001
TABLE 4 CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
-STRUCTURES, SITE GROUNDS, SITE EXTERIORS l SIIOREHAM NUCLEAR POWER STATION BROOKIIAVEN, NY Radiological Survey Unit'
""'"'* U TB016 TB017 TB031 TB035 TB060 Total Beta Activity (dpm/100 cni)
# of Direct Measurements 30 30 30 30 30 Mean(X) -62 -130 7 -110 200 LlPA X -63 -480 -16 24 190 F= 30 -52 77 -27 300 ,
Conditions and 5,000/15,0000 dpm/100 cm2Guidelines Satisfied Yes Yes Yes Yes Yes Removable Beta Activity (dpm/100 cni)b
# of Smears 30 30 30 30 30 Mean(X) -1.2 0.1 0.1 -0.4 0.1 LIPA X 1.9 1.6 2.9 3.7 1.7 Fa -0.5 1.0 1.1 0.6 1.0 j Conditions and 1,000 dpm/100 caf l Guideline Satisfied Yes Yes Yes Yes Yes i Exposmr Rates at I m (pR/h) l
# of Exposure Rate Measurements 9 6 15 23 13 Net Mean (X) -0.7 -0.5 . -0.1 0.4 0.9 LIPA X. -0.1 0.2 0.2 0.1 0.7 Fa -0.5 -0.2 0.2 0.6 1.1 Conditions and 5 pR/h Above Background 1 Guideline Satisfied Yes Yes Yes Yes Yes I l
1 Shoreharo Nudrar Power Su6on Februncy 3, != 49 hw,w-.%h=%h-mi
i I j i i TABLE 4 (Continued) i CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
--STRUCTURES, SITE GROUNDS, SITE EXTERIORS SIIOREllAM NUCLEAR POWER STATION BROOKIIAVEN, NY ) Radiological Survey Unit'
"""""U TB081 TB082 TB089 SE002 SG003 Total Beta Activity (dpm/100 cnri
# of Direct Measurements 30 30 30 30 30 Mean(X) -290 -84 370 -270 4 LIPA X 450 65 -280 430 440 Fa -110 -2 480 -180 87 Conditions and 5,000/15,0000 dpm/100 cnf t Guidelines Satisfied Yes Yes Yes Yes Yes Removable Beta Activity (dpm/100 cni)b
# of Smears 30 30 30 30 30 Mean(X) 0.6 -0.2 -1.4 0.8 -1.0 LIPA X 3.5 4.1 0.7 2.1 2.6 Fa 1,9 0.6 - 0.4 1.8 -0.1 Conditions and 1,000 dpm/100 cm2
, Guideline Satisfied Yes Yes Yes Yes Yes Exposure Rates at 1 m ( R/h)
# of Exposure Rate Measurements 12 10 12 Net Mean G) 0.5 -0.3 2.3 - -
LIPA X -0.1 -0.5 1.0 --- - Fa 0.7 -0.1 2.4 -- -- Conditions and 5 R/h Above Background Guideline Satisfied , Yes Yes Yes -- --
' Refer to Figures 7 through 14 and 24 through 27. -
b All alpha removable activity was less than 12 dpm/100 cm 2,
* - = Measurement.s not performed.
sw um u ,.,rou54,..r % ,yu m 50 em emmeramm%s m.wi
,,~ _ -- ,
TABLE 5 CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
-SYS'ITalS TURBINE . BUILDING SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NY Radiological Survey Unit' Summary SU005 SUO14-Drains SUO14X03 SUO24 SU025X2 Total Beta Activity (dpm/100 cm 2)
# of Direct Measurements 5 16 6 25 30 Mean(X) -340 -340 -490 -240 52-LIPA X 380 -NA* -210 350 -120 Fa -57 -230 -370 -170 480 Conditions and 5,000/15,000 dpm/100 cnf Guidelines Satisfied Yes Yes Yes Yes Yes Removable : Beta Activity (dpm/100 cnf)b
# of Smears 5 16 6 25 30 Mean(X) - 0.1 -1.1 -1.0 -0.8 0.3 LIPA X 2.1 NA 6.2 6.2 7.2 Fa 3.1 0.1 0.3 0.2 1.4 Conditions and 1,000 dpm/100 cm2 l Guideline Satisfied Yes Yes Ye.s Yes Yes 1
Shoreham Nwlear b.wer Stauon February 3.19M 51 6:se-.et, rori wreham'.horeham ooi
TABLE 5 (Continued) CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
-SYSTEMS TURBINE IlUILDING SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NY Radiological Survey Unit' SUO32 SUO34 SUN 6 SUO54X3 SUO71X70 Total Beta Activity (dpm/100 cnf)
# of Direct Measurements 3 3 34 10 30 Mean(X) -410 270 300 -220 -90 LIPA X 290 300 560 -380 15 Fa -120 -390 630 7 -2) 5,000/15,000 dpm/100 cm2 Guidelines Satisfied Yes Yes Yes Yes Yes Removable Beta Activity (dpm/100 cn/)
# of Smears 3 3 30 10 30 Mean(X) 4).7 -0.5 1.2 -0.4 0.3 LIPA X 2.9 1.9 13.5 4.9 1.0 Fa 1.5 0.7 2.7 1.3 2.2 Conditions /1,000 dpm/100 cnf Guideline Satisfied Yes Yes Yes Yes Yes ,
- Refer to Figure 16 through 25.
b All alpha removable activity was less than 12 dpm/100 cm2,
'NA = not applicable j
l l Snorrhara Nuclear Power 5tsuon February 3, im 52 6 se psrerers.t.sorehano sores .ooi
l , e
- REFERENCES
- 1. l_ong Island Lighting Company, "Shoreharn Nuclear Power Station Site Characterization Program Final Report," May 1990.
- 2. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Internal Components, Shoreham Nuclear Power Station, Brookhaven, New York," July 1993.
- 3. J. D. Berger, Oak Ridge Associated Universities, Draft " Manual for Conducting Radiological Surveys in Support of License Termination," NUREG/CR-5849, June 1992.
- 4. Ieng Island Power Authority, "Shoreham Decommissioning Project, Termination Survey Plan, Revision 1," April,1993.
- 5. long Island Power Authority, "Shoreham Decommissioning Project Termination Survey Final Report, Volumes 1 through 5," September,1993.
- 6. Letter from T. J. Vitkus, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission, " Final !
Confirmatory Survey Plan for the Shoreham Nuclear Power Station, Brookhaven, New York l
- Docket File No. 50-322," November 4,1993.
- 7. Letter from D. N. Fauver, U.S. Nuclear Regulatory Commission, to T. Vitkus, ORISE, l July 1,1993. -
- 8. Letter from M. R. Landis, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission, "Shoreham Decommissioning Project, Termination Survey Plan, Revision 0, Shoreham Nuclear Power Station, October 199~2," January 12, 1993.
- 9. U.S. Nuclear Regulatory Commission, " Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1, September 1984.
l l l g Shorcham Nwican Power Statum February 1. Im 53 h v + co % 2,em % 6 ooi
i t' s l I APPILNDIX A AIAJOR INSTRUAfENTATION 1
'1 f
P i I Shoreham Haleer Power Stenon - Febnery 3, Irg4 h.hp\reporuinhoreham\ horchsm.001
s . APPENDIX A MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. l l DIRECT RADIATION MEASUREMENT Iristruments ! Eberline Pulse Ratemeter Model PRM-6 1 (Eberline, Santa Fe, NM) l l Eberline " Rascal" Ratemeter-Scaler ! Model PRS-1 ! (Eberline, Santa Fe, NM) Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., l Sweetwater, TX) E!'lMIDDi Eberline GM Detector Model HP-260 i Effective Area,15.5 cm2 (Eberline, Santa Fe, NM) Eberline ZnS Scintillation Detector Model AC-3-7 Effective Area,59 cm2 (Eberline, Santa Fe, NM) Ludlum Gas Proportional Detector Model 43-37 Effective Area,550 cm2 (Ludlum Measurements, Inc., Sweetwater, TX) l Shortham Nedcar Power St. tion February 3,1994 A-1 6:s psrepori.s. sores.r.s. sores t00: e, v- -- .m, , . _ _ g , ,, m _,,,n._,
Ludlum Gas Proportional Detector Model 43-68 Effective Area,100 cm2 (Ludlum Measurements, Inc., Sweetwater, TX) Reuter-Stokes Pressurized Ion Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH) Victorcen Nal Scintillation Detector Model 489-55 3.2 cm x 3.8 cm Crystal (Victorcen, Cleveland, OH) LABORATORY ANALYTICAL INSTRUMENTATION High Purity Extended Range Intrinsic Detectors Model No: ERVDS30-25195 (Tennelec, Oak Ridge, TN) Used in conjunction with: Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer 3100 Vax Workstation - (Canberra, Meriden, CT) High-Purity Germanium Detector Model GMX-23195-S,23% Eff. (EG&G ORTEC, Oak Ridge, TN) Used in conjunction with: Lead Shield Model G-16 (Gamma Products, Palos Hills, IL) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT) Low Background Gas Proportional Counter Model LB-5100-W (Oxford, Oak Ridge, TN) I a Shonharn Nucker Power statice February 3 19* A-2 hwencon.%um%6mmi
, - - =
e . APPENDIX B SURVEY AND ANAIXI'ICAL PROCEDURES 5 i haham Nucker Power 1>ti<m . February 3.194 h%=p\reportskbartham\ horeham.001
/
APPENDIX B SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES 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 I cm. A large surface I area, gas proportional floor monitor was used to scan the floors of the surveyed areas. Other surfaces were scanned using small area (15.5 cm 2
, 59 cm2 or 100 cm )2 hand-held detectors.
Identification of elevated 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: Alpha - gas proportional detector with ratemeter-scaler ZnS scintillation detector with ratemeter-scaler l Beta - gas proportional detector with ratemeter-scaler ; . j pancake GM detector with ratemeter-scaler Gamma - Nal scintillation detector with ratemeter Sur_ face Activity Measurements Measurements of total beta activity levels were primarily performed using GM detectors with portable ratemeter-scalers. 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 7 efficiency and correcting for the Shoreham 141cer Power $tation + February 3,1994 B-I b:\essep\reportswrehamWrcham.001 -
,v - e
,y, -
- r-,r . -,r-,--%-----,:.-.,~--.---
- - , - - - - , -. ,-,m%- --
.-v m~--- -iw..
active area of the detector. The beta activity background count rates for the GM detectors ranged from 22 to 42 cpm, respectively. Beta efficiency factors ranged from 0.16 to 0.18 for the GM detectors. The effective window for the GM detectors was 15.5 cm 2, Surface activity measurements which exceeded the normal background distribution were corrected for the Fe-55 contribution by multiplying the dpm/100 enf field activity level by a factor of 1.2. The instrument response level at which the detector output could be considered above background was defined as the critical level (L).c This level was defined for each detector / instrument combination as follows: ample count rate Backroud count rate 1.96
\ ample c unt time Background count time L* = (Detector Efficiency) (Detector Geometry)
Removnble Activity Mensttrement.s Removable activity levels were determined using numbered filter paper disks,47 mm in diameter. 2 Moderate pressure was applied to the smear and approximately 100 cm of the surface was wiped. Smears were placed in labeled envelopes with the location and other pertinent information recorded. Exnosure Rate Measurements l Measurements of gamma exposure rates were performed using a pressurized ionization chamber (PIC). . j Soil Sampling i Approximately 1 kg of soil was collected at each sample location. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures. l l l breham Nmicar Power Satma. February 3. Im B-2 kne ,wn.%-sam %hammt
ANAIXflCAL PROCEDURES Remoynble Activity Smears were counted on a low background gas proportional system for gross alpha, and gross beta activity, filunnia Socctrometry Soil and sludge samples were dried, mixed, crushed, and/or homogenized as necessary, and a portion scaled in 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry and ranged from 556 to 1238 g of-material. Net material weights were determined and the samples counted using intrinsic germanium-I detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak scarch, peak identification, and concentration calculations were performed using the computer I capabilities inherent in the analyzer system. The energy peak.used for determining the activity of the radionuclide of concerns was: l Co-60 1.173 MeV
- Secular equilibrium assumed.
Spectra were also reviewed for other identifiable photopeaks. UNCERTAINTIES AND DETECTION LIMITS I 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. Additional uncertainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this report. breham Nwicar Power $tatwo . February 3.1994 B-3 6:se .r s ,,po,i.wrehamwres .ooi
c . Detection limits, referred to as minimum detectable activity (MDA), were based on 2.71 plus 4.66 times the standard deviation of the background count [2.71 + (4.66/BKG)]. When the activity was determined to be less than the MDA of the measurement procedure, the result was reported as less than MDA. Because of variations in background levels, measurement efficiencies, and contributions j from other radionuclide in samples, the detection limits differ from the sample to sample and instmment to instrument. l CALIBRATION AND QUALITY ASSURANCE i
.i l
Analytical and field survey activities were conducted in accordance with procedures from the i following documents of the Environmental Survey and Site Assessment Program:
- Survey Procedures Manual, Revision 7 (May 1992) -1
- Laboratory Procedures Manual, Revision 8 (August 1993)
- Quality Assurance Manual, Revision 6 (July 1993) l 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 bas'ed on standards, traceable to NIST, when such standard were available. In cases where they were not available, standards of an industry recognized organization was used. Calibration of pres rized ionization chambers was performed - by the manufacturer. 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 DOFlEML Quality Assurance Programs.
- Training and certification of all individuals performing procedures.
- Periodic internal and external audits.
Skrrham Nudcar Power Statum February 3.1994 3-4
- h: \essap\ reports \shorehambhoreham. 001
O a L APPENDIX C REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS Shortham Nakar Power Steuon . February 3,1994 b;\ennap\ reports \shoreham\sborthem.001
U.S. ATOMIC ENERGY COMMISSION June 1974 REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. INTRODUCTION important to the safety of reactor operation is no longer required. Once this possession-only license is issued, Section 50.51, " Duration of license, renewal," of 10 reactor operation is not permitted. Other activities from CFR Part 50, " licensing of Production and Utilization the reactor and placing it in storage (either onsite or Facilities,' requires that eacn license - to operate a offsite) may be continued. production and utilization facility be issued for a specified duration. Upon expiration of the specified period, the A licensee having a possession-only license must retain, license may be either renewed or terminated by the with the Part 50 license, authorization for special nuclear Commission. So: tion 50.82, " Applications for termination material (10 CFR Part, 70, "Special Nuclear Material"), of licenses,' specifies the requirements that must be byproduct material (10 CFR Part 30, " Rules of General satisfied to terminate an operating license, including the Applicability to Licensing of Byproduct Material"), and requirement that the dismantlement of the facility and source material (10 CFR Part 40, " Licensing of Source disposal of the component parts not be inimical to the Material"), until the fuel, radioactive components, and common defense and security or to the health and safety soumes are removed from the facility, Appropriate of the public. ~1his guide describes methods and administrative controls and facility requirements are procedures considered acceptable by the Regulatory staff imposed by the Part 50 license and the technical for the termination of openting licenses for nuclear specifications to assure that proper surveillance is reactors. The advisory Committee on Reactor Safeguards performed and that the reactor facility is maintained in a has been consulted concerning this guide and has safe condition and not operated, concurred in the regulatory position. A possession-only license permits various options and B. DISCUSSION procedures for decommissioning, such as mothballing, entombment, or dismantling. The requirements imposed When a licensee decides to terminate his nuclear depend on the option selected. reactor operating license, be may, as a first step in the process, request that his operating license be amended to Section 50.82 provides that the licensm may dismantle restrict him to possess but not operate the facility. 'lhe and dispose of the component parts of a nuclear reactor in advantage to the licensee of converting to such a accordance with existing regulations. For research 1 1 possession-only license is reduced surveillance reactors and critical facilities, this has usually meant the ; requirements in that periodic surveillance of equipment disassembly of a reactor and its shipment organization for ) USAEC REGULATORY GUIDES ces et punhohad guideo mey be obtesewd by peount irwilcaterg tPe divesert neewiewy ows.e .. m.ved te desante and make eve.ieuw to the puu.c 8""*d "* ds. Atenue Enern Conwnsmen, Washinoten, D.C. 20646. methode oceepieue io it. Arc reeussiery staff of enpierentre speciele pwte Ama hewwemsimac - Wmose% w of the Commeomen's roguetiene. to enginete techevouse used by the eieff m ownm. Owdee are emeureged and Md W unt to ee evoluet+rq epecifte probleme er postulated scendente, or to provide gudence to Secretary of the Commise*en. U.S. Atomic Energy commee.en, Westersten. epp4cente. Regdetery Guidee are riot eJ>etstutee for re0Jeteens and *^"""# * * ***d"** **"" e mphence wim them m not required. Methods and solutione different from g these set out m the pudse w a be ecceptable if they provide e bee e for the fwwthge ,equesne to the eeuence w cent nuance of a permet se newee by tre p
- 2. Research and test Resetee. 7. Transportehen Pubbehod e oes wm be ,evised penedicee 3'"'""d"***'***'*'
r . o apprepnete. to aceemmedet. 8 ' 0 **""""no*v'. H* *'* eemmente end to ,anect entemeesen w operwe. [ y,"'"**,"g'*'p*,,"d s uw p et Note: Section electronicaHy reproduced from photocopy. C-l i
- o. .
further use. %e site from which a reactor has been c. Any pmposed changes to the technical specifications removed must be decontaminated, as necessary, and that reflect the ponession-only facility status and the inspected by the Commission to determine whether necessary disassembly / retirement activities to be unrestricted access can be approved. In the case of perfornal. nuclear power reactoa, dismantling has usually been accomplished by shipping fuel offsite, making the reactor d. A safety analysis of both the activities to be inoperable, and disposing of some of the radioactive accomplished and the proposed changes to the technical components. specifications. Radioactive components may be either shipped off-site e. An inventory of activated materials and their for burial at an authorized burial gmund or secured on the location in the facility, site. Rose radioactive materials remaining on the site must be isolated from the public by physical barriers or 2. ALTERNATIVES FOR REACTORPErlREMENT other means to prevent public access to hazardous levels of radiation. Surveillance is necessary to assure the long Four altematives for retirement of nuclear reactor term integrity of the barriers. He amount of surveillance facilities are considered acceptable by the Regulatory required depends upon (1) the potential hazard to 'he staff. Rese are: health and safety of the public from radioactive material remaining on the site and (2) the integrity of the physical a. Mothballing. Mothballing of a nuclear reactor barriers. Before areas may be released for unmstricted facility consists of putting the facility in a state of use, they must have been decontaminated or the protective storage. In general, the facility may be left ; radioactivity must have decayed to less than presenbed intact except that all fuel assemblies and the radioactive j limits (Table 1). fluids and, waste should be removed from the site. Adequate radiation monitoring, environmental The hazard associated with the retumed facility is surveillance, and appropriate security pmcedures evaluated by considering the amount and type of remaining should be established under a possession-only license contamination, the degree of confmement of the remaining to ensure that the health and safety of the public is not radioactive materials, the physical security pmvided by the endangered. confmement, the susceptibility to release of radiation as a result of natural phenomena, and the duration of requind b. In-Place Entombment. In-place entombment surveillance. consists of sealing all the remaining highly radioactive or contaminated components (e.g., the pressure vessel -l C. REGULATORY POSITION and reactor intemals) within a structure integral with the biological shield after having all fuel assemblies,
- 1. APPLICATION FOR A LICENSE TO POSSESS radioactive fluids and wastes, and certain selected BUT NOT OPERATE (POSSESSION-ONLY components shipped offsite. ne structure should LICEMSE) provide integrity over the period of time in which significant quantities (greater than Table 1 levels) of A request to amend an operating license to a radioactivity remain with the material in the possession-only license should be made to the Director of entombnwnt. An appropriate and continuing Licensing,U.S. AtomicEnergyCommission, Washington, surveillance program should be established under a D.C. 20545. %e request should include the following possession-only license, information:
- c. Removal of Radioactive. Com;x>nents and
- a. A description of the current status of the facility. Dismantling, All fuel assemblies, radioactive fluids and waste, and other materials having activities above
- b. A description of measures that will be taken to accepted unrestricted activity levels (Table 1) should be prevent criticality or reactivity changes and to minimize removed from the site. The facility owner may then micases of radioactivity from the facility, have unrestrictal use of the site with no requirement for a license. If the facility owner so desims, the Note: Section electronically reproduced from photocopy. C-2
--. - - _ - . ~ . - - - -
remainder of the reactor facility may ha dismantled and barriers in the facility. Sampling should b done along the all vestiges removed and disposed of. most probable path by which radioactive material such as that stored in the inner containment regions could be
- d. Conversion to a New Nuclear System or a Fmsil transporta! to the outer regions of the facility and Fuel Systan. His altemative, which applies only to ultimately to the emirons.
nuclear power plants, utilizes the existing turbine system with a new steam supply system. He original d. An emironmental radiation survey should be nuclear steam supply system should be separated from performed at least semiannually to verify that no the electric generating system and disgused of in significant amounts of radiation have been releam! to the accordance with one of the previous three retirement emironment from the facility. Samples such as soil, attematives. vegetation, and water should be taken at locations for which statistical data has been established during reactor
- 3. SURVEILLANCE AND SECURITY FOR TIIE operations.
RETIREMENT ALTERNATIVES %110SE FINAL STATUS REQUIRES A POSSESSION-ONLY e. A site representative should be designated to be LICENSE responsible for controlling authorized access into and movement within the facility. A facility which has been licensal under a possessionenly license may contain a significant amount f. Administrative procedures should be established for of radioactivity in the form of activated and contaminated the notification and reporting of abnormal occurrences hardware and structural materials. Surveillance and such as (1) the entrance of an unauthorized person or commensurate security should be provided to assure that persons into the facility and (2) a significant change in the the public health and safety are not endangered. radiation or contamination levels in the facility or the
- a. Physical security to prevent inadvertent exposure of offsite environment.
personnel should be pmvided by multiple locked barriers. He presence of these barriers should make it extremely g. He following reports should be made: difficult for an unauthorized penon to gain access to areas where radiation or contamination levels exceed those (1) An annual report to the Director of Licensing, specified in Regulatory Position C.4. To prevent U.S. Atomic Energy Commission, Washington, D.C. inadvertent exposme, radiation areas above 5 mR/hr, such 20545, describing the results of the environmental and as near the activated primary system of a power plant, facility radiation surveys, the status of the facility, and an i should be appropriately marked and should not be evaluation of the performance of security and surveillance accessible except by cutting of welded closures or the measures. , disassembly and removal of substantial stmetures and/or shielding material. Means such as a remote-readout (2) An abnormal occurrence report to the Regulatory ; intrusion alarm system should be prosided to indicate to Operations Regional Office by telephone within 24 hours ) designated personnel when a physical barrier is penetrated. of discovery of an abnormal occurrence. The abnormal l Security personnel that provide access control to the occurrence will also be retorted in the_ annual report facility may be used instead of the physical barriers and descriled in the preceding item. the intrusion alarm systems.
- h. Records or logs relative to the following items
- b. The physical barriers to unauthorized entrance into should be kept and retained until the license is terminated, the facility, e.g., fences, buildings, welded doors, and after which they must be stored with other plant reconis:
access openings, should be inspected at least quarterly to assure that these barriers have not deteriorated and that (1) Envimnmental surveys, locks and locking apparatus are intact. (2) Facility radiation surveys, 1 (3) Inspections of the physical barriers, and
- c. A facility radiation survey should be performed at least quarterly to verify that no radioactive material is (4) Abnormal occurrences.
escaping or being transTorted through the containment Note: Section 6lectronically reproduced from photocopy. C-3
l .
- 4. DECONTAMINATION FOR RELEASE FOR (2) A detailed health and safety analysis indicating that
, UNRESTRICTED USE the residual amounts of materials on surface areas, together with other considerations such as the prospective if it is desimi to terminate a license and to eliminate use of the premises, equipment, or scrap, are unlikely to any further surveillance requirements, the facility should result in an unreasonable risk to the health and safety of be sufficiently decontaminated to prevent risk to the public the public, heahh and safety. After the daontamination is I satisfactorily accomplished and the site inspected by the e. Prior to release of the premises for unrestricted use, ! Commission, the Commission may authorize the license to the licensee should make a comprehensive radiation survey be terminated and the facility abandoned or released for establishing that contamination is within the limits specified unrestricted use. He licensee should perfonn the in Table 1. A survey report should be filed with the decontammation using the following guidelines: Director of Licensing, U.S. Atomic Energy Commission, Washington, D.C. 20545, with a copy to the Director of
- a. %e licensee should make a reasonable effort to the Regulatory Operations regional Office having eliminate residual contamination, jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment. H e survey
- b. No covering should be applied to radioactive report should:
surfaces of equipnat of structures by paint, plating, or other covering material until it is known that contamination (1) Identify the premises; levels (determined by a survey and documented) are below the limits specified in Table 1. In addition, a reasonable (2) Show that reasonable effort has been nate to effort should be made (and documented) to further reduce residual contammation to as low as practicable minimize contamination prior to any such covering, levels;
- c. He radioactivity of the interior surfaces of pipes, (3) Describe the scope of the survey and the general drain lines, or ductwork should be determined by making procedures followed; and measurernents at all traps and other appropriate access points, provided contamination at these locations is likely (4) State the finding of the survey in units specified in to be representative of 2 contamination on the interior of Table 1.
the pipes, drain lines, or ductwork. Surfaces of premises, aiuipment, or scrap which are likely to be contaminated After review of the report, the Conunission may
- but are of such size, constmetion, or location as to make inspect the facilities to confirm the suivey prior to gnmting the surface inaccessible for purposes of measurement approval for abandonnet, should be assumed to be contaminated in excess of the permicible radiation limits.
, 5. REACTOR RETIREMENT PROCEDURES
- d. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, P indicated in Regulatory Position C.2, several equipment, or scrap having surfaces contaminated in altenatives are acceptable for reactor facility retirement.
excess of the limits specified. His may include, but is not If minor disassembly or "mothballing" is planned, this limited to, special circumstances such as the transfer of could be done by the existing operating and maintenance premises to another licensed organization that will continue procedures under the license in effect. Any planned to work with radioactive materials. Reqmts for such actions involving an unreviewed safety question or a authorization should provide: change in the' technical specifications should be reviewed and approved in accordance with the requirements of 10 (1) Detailed, specific information describing the CFR I 50.59. premises, equipment, scrap, and radi uctive contaminants and the nature, extent, and degree of residual surface If major structural changes to radioactive components contamination. of the facility are planned, such as removal of the pressure vessel or major components of the primary system, a Note: Section electronically reproduced from photocopy. C-4
4
- dismantlenut plan iecluding the information required by 9 50.8? should be submitted to the Commission. A dismantlenat plan should be submitted for all the )
altematives of Regulatory Position C.2 except mothballing. However, minor disassembly activities may still be I performed in the absence of such a plan, provided they are permitted by existing operating and maintenance proceduns. A dismantlenut plan should include the following:
- a. A description of the ultimate statas of the facility
- b. A description of the dismantling activities and the precautions to be taken.
- c. A safety analysis of the dismantling activities inchiding any effluents which may be rtieased.
- d. A safety r.nalysis of the facility in its ultimate status.
Upon satisfactory review s'vl approval of the dismantling plan, a dir.nantling order is issued by the Commission in ar ordance with 9 50.82. When ,; dismantling is completed and the Commission has been l notified by letter, the appropriate Regulatory Operations Regional Office inspects the facility and verifies completion in accordance with the dismantlenent plan. If . resiaual mdiation levels do not exceed the values in Table 1, the Commission may terminate the license. If l pcession-only license under which the dismantling l activities have been conducted or, as an altemative, may make application to the State (if an Agnenent State) for a bypmduct nuterials license. l Note: Section electrorucally reproduced from photocopy. C-5 i l __ __ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ . _ _ _ _ _ _ ._ ____ - ]!
1 1 l l l TABLE 1 l ACCElvrABLE SURFACE CONTAMINATION LEVEIS j l Nuclidd Average"' Maximum'd Removable6 ' U-nat, U-235, U-238, and associated decay products 5,000 dpm a/100 cnf 15,000 dpm a/100 cm2 1,000 dpm a/100 enf Transunmics, Ra-226, Ra-228, n-230, Th-228, Pa-231, Ac-227,1-125,1-129 100 dpm/100 cnf 300 dpm/100 cnf 20 dpm/100 cnf Th-nat, %-232, Sr-90, Ra-223, Ra-224, U-232,1-126, I-131,1-133 1,000 dpm/100 cnf 3,000 dpm/100 cnf 200 dpm/100 en/ I Beta-gamma emitters (nuclides with decay nules other than alpha emission or spontaneous fission) except Sr-90 and others ; notal above. 5,000 dpm 0y/100 cnf 15,tN dpm Sy/100 cnf 1,000 dpm 07/100 enf
'Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits estabbsherl for alpha- and beta-gamma <mitting nuclides should apply inspendently.
'As used in this table, dpm (disintegrations pr minute) means the rate of emission by radioactive material as determined by corrating the counts per minute observed by an opropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
%feasumtnents of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.
"Ihe maximum contamination level applies to an area of not more than 100 cnf.
"Ihe amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and asser, sing the amount of radioactive material on the wipe with an armpriate instmment at known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
Note: Section electronically reproduced from photocopy. C-6
DATE: February 23, 1994 NOTE T0: Janette Copeland FROM : Cathy Poland, NMSS Document Liaison Officer
SUBJECT:
PROBLEM (S) TO BE RESOLVED DEALING WITH YOUR REQUEST FOR CHANGES TO RIDS CODES /NUDOCS ENTRIES
- 1) PROBLEM IDENTIFIED BY DON LANHAM:
The attached document has the date of February 3,1993, instead of 1991
- 2) PLEASE DESCRIBE HOW THIS PROBLEM (S) SHOULD/CAN BE CORRECTED:
(Note: Attach any documentation necessary to rectify this problem (s)) fcf wd lLcw G L b i O C 4 O .J S D A l dkW wj, o9aa & & /'Mb otdrLb CN_h $ 0!h ff L4censingAspistant Date I 's 7 Cathy Poland
> !Y Date NMSS Document Liaison Officer Please return this sheet with Itec No. 2 above filled in and signed by the Licensing Assistant. This sheet and the appropriate documentation should be returned to Cathy Poland within three working days from the date of this requested action.
l !__ . _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _______.________.___..______________.__s
*(17 i
NUDOCS REJECTED DOCUMENT DATE: '[ NUDOCS CONTROL NUMBER: h b - b/ ~ N. $
' /
DOCUMENT CONTROL DESK: ***** PLEASE RETURN THIS DOCUMENT TO SUBMITTER ***** REASON FOR [ EJECTION: DOCUMENT INCOMPLETE / MISSING PAGES AVAILABILITY UNCLEAR /NOT MARKED DOCUMENT NOT NORMALLY PROCESSED BY NUDOCS PER MANAGEMENT DIRECTIVE 3.50 INCONSISTENT DATA (i.e. DOCKETS. DATES) THROUGHOUT PACKAGE CONTAINS PRIVACY ACT/ COPYRIGHT / UNMARKED PROPRIETARY INFORMATION NO DOCKET OR UTILITY IDENTIFIED FORWARDING LETTER AND ENCLOSURES UNRELATED ~ * - - MISSING / INCORRECT DISTRIBUTION CODE NO CF/RES/WM SUBJECT FILE ASSIGNED DOCKET DATE ILLEGIBLE /NO DOCKET DATE OTHER: \ ^) ' ' ' I > D-- [i NUDOCS REJECTOR: biw d _ PHONE: S h (/ ( t / t m_ _ NRC SUBMITTER: PLEASE CORRECT NOTED PROBLEM AND RESUBMIT DOCUMENT (5) WITH I
-- THIS SHEET TO NUDOCS. C/O DOCUMENT CONTROL DESK (OWFN MAIL-STOP P1-137). ;
.1 NRC NOTES: _ _ga m
_ 4 4A_c [m , _j _,7_y__F A----A
& NLJb.oe's. L6 # f 4 ^3f Q__
ow A,o
~
06 M l%.-. .- NAME: _ PHONE: f REVISION 7,1/77/93 m+e e.,. ,- w ---e y.% -- e , m +-,%. ,,}}