ML20081A705
| ML20081A705 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/27/1995 |
| From: | Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20081A703 | List: |
| References | |
| CON-FIN-A-9076 NUDOCS 9503150255 | |
| Download: ML20081A705 (70) | |
Text
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I' CONFIRMATORY SURVEY-OF THE ,
RADWASTE BUILDING, SUPPRESSION POOL, PHASE 2, AND PHASE 3 SYSTEMS
'SHOREHAM NUCLEAR POWER STATION i R BROOKHAVEN, NEW YORK Prepared by T. J. Vitkus t
Environmental Survey and Site Assessment Program Energy / Environment Systems Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 l i
Prepared for the U.S. NuclearRegulatory Commission Headquarters Office Sponsored by the Division of Waste Management DRAFT REPORT, REVISION 1 ,
JANUARY 1995 i
t This repon 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.
'" "-- ** haven. NY - January 27, 1995 h;\cssapirepons\shorcham\brookhav.001 9503150255 950130
{DR ADOCK 05000322 PDR
ACKNOWLEDGEMENTS
- The author would like to acknowledge the significant contributions of the following staff members:
FIELD STAFF E. H. Bjelland E. H. .Montalvo .
J. R. Morton
< J. L. Payne -
LABORATORY STAFF R. D. Condra -
J. S. Cox M. J. Laudeman s
CLERICAL STAFF D.' A. Adams R. D. Ellis -
K. E. Waters ILLUSTRATOR T. D. Herrera i
ShorhBrathaven. NY . January 27.1995 h:\essap\ reports \shorcham\brookhav.001
TABLE OF CONTENTS PAGE List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -. . . . . . . . . . ii List of Tables ..............................................iv Abbreviations and Acronyms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . y Introduction and Site History . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . I Site Description . . . . . . . . . . . . . . . . . . . . . . . . .................... 2 i
Obj ectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- Document Review and LIPA Procedure Surveillance . . . . . . . . . . . . . . . . . . . . . . . 4 Procedures ................................................ 4 Findings and Results .......................................... 9 Comparison of Results with Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 References ...............................................48 Appendices:
Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86 Termination of Operating Licenses for Nuclear Reactors ShortharwBruukhaven. NY January 27.1995 i h:\cssap\ report \shoreham\brookhav.001 I
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i LIST OF FIGURES I
- - l PAGE -l U . FIGURE 1: -location of the Shoreham Nuclear Power Station . . . . . . .. . . . . . . . . . .16 ..
FIGURE 2: Plot Plan of the Shoreham Nuclear Power Station . .. . . . . . . . . . . . . . 17 :
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FIGURE 3: Radwaste Building, Elevations 15'6"/19'6" Floor -
Plan-Surveyed Areas ............................... .
18- j e i FIGURE 4: Radwaste Building, Elevation 37'6" Floor Plan- !
Surveyed Areas ................................... 19- l FIGURE 5: Radwaste Building, Elevation 50'6"/52'6" Floor Plan- l Surveyed Areas ...................................20 t' FIGURE 6: Reactor Building, Elevation 8'0" Floor Plan, Suppression l Pool-Surveyed Areas ...............................21 j FIGURE 7: Radwaste Building, Radwaste 15' North Hallway (RW013)- '
Measurement and Sampling locations . . . . . . . . . . . . . . . . . . . . . . . 22 j
j FIGURE 8: Radwaste Building, Cation / Anion Regen. and Resin Storage L Tanks Area (RW017)-Measurement and Sampling Locations . . . . . . . 23 j FIGURE 9: Radwaste Building, Liner Fill Stations /BW Storage Rooms (Cubicle A) (RWO23)-Measurement and Sampling locations. . . . . . . . .
24 FIGURE 10: Radwaste Building, Waste Evap./ Regen.Evap. Distil. Room !
(RWO40)-Measurement and Sampling Locations . . . . . . . . . . . . . . . 25 {
i FIGURE 11: Radwaste Building, Radwaste 37' North Hallway (RWO42)- {
Measurement and Sampling locations . . . . . . . . . . . . . . . . . . . . . . 26 - i f
FIGURE 12: Radwaste Building, "B" RW 0/G HEPA After Filter Area l
(RWO69A)-Measurement and Sampling locations . . . . . . . . . . . . . 27 FIGURE 13: Radwaste Building, "C&D" Dryer Skid Area (RWO69B)- j Measurement and Sampling locations . . . . . . . . . . . . . . . . . . . . . . 28 : j t
FIGURE 14: Radwaste Building, Off Gas Desiccant Dryers Area (RWO72)-
Measurement and Sampling locations . . . . . . . . . . . . . . . . . . . . . . 29 I
i FIGURE 15: Reactor Building, Suppression Pool, NW Quadrant (SP004) l Lower Walls and Floor-Measurement and Sampling locations . . . . . . 30 l i
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l LIST OF FIGURES (Continued)
PAGE i 1
FIGURE 16: Reactor Building, Suppression Pool, NW Quadrant (SP004) Upper ;
Walls-Measurement and Sampling Locations . . . . . . . . . . . . . . . . . 31 l
L FIGURE 17: Reactor Building, Suppression Pool,- Area Inside Vessel Pedestal (SP005)-Measurement and Sampling locadons . . . . . . . . . . . . . . . . 32 j u
[ FIGURE 18: Reactor Building, HPCI Valves E41-01V-3049 and 3050 (SUO12)-Measurement and Sampling Locations ...............33 L
FIGURE 19: Radwaste Building, Radwaste Influent Drain System, Drain Sump Tank-054 (SU14x09)-Measurement and Sampling Locations ..............................34 FIGURE 20: Radwaste Building, Equipment Drain System, -
Drain Sump Tank-071 (SUO14 x10)-Measurement and Sampling Locations ..............................35 FIGURE 21: Radwaste Building, Radwaste Equipment / Components, Flat Bed Floor Drain Filter IG11-FIe012 (SU014 x12)-Measurement and Sampling Locations ..............................36 FIGURE 22: Radwaste Building, Radwaste Equipment / Components, Waste Collector Tank 1G11-TK-10A (SUO14 x12)-
Measurement and Sampling locations . . . . . . . . . . . . . . . . . . . . . . 37 FIGURE 23: Reactor Building, Reactor Water Clean-up System Components ;
(SUO15)-Measurement and Sampling Locations ...............38 FIGURE 24: Radwaste Building, Condensate Demineralizers, Tank 1N52-DE-002E (SUO43)-Measurement and Sampling Locations ...............39
/
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a LIST OF TABLES
- t TABLE 1: Summary of Surface Activity Levels . . . . . . . -. . . . . . . . . . . . . . . . . ' 40 "
- f TABLE 2: Interior Exposure Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
42 j
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i TABLE 3: Embedded Piping Program Summary . . . . . . . . . . . .' . . . ... . . . . . . 43 i
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TABLE 4: Confirmatory Radiological Status Summary-Structures . . . . . . . ... . . .
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TABLE 5: Confirmatory Radiological Status Summary-Systems . . . -. . . . . . . . . . 47-
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L ABBREVIATIONS AND ACRONYMS L ti 1
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ac . acre. I W- ASME' ' American Society of Mechanical Engineers t-l
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cm2
,. y square centimeter cpm . counts per minute ;i lDOE Department of Energy -
. dpm/100 cm 2. .
disintegrations per minute per 100 square centimeters !
EML Environmental Measurements Laboratory. -'
f.9- EPA Environmental Protection Agency; .
ESSAP Environmental Survey and Site Assessment Program - !
ft2- square feet ' ,
, ha hectare- .
GM Geiger-Mueller :}
km kilometer j I, critical level j LILCO Long Island Lighting Company j LIPA . Iong Island Power Authority j m - meter i m2 - square meter j MDA minimum detectable activity 1 mi .. mile l NaI sodium iodide !
NIST National Institute of Standards and Technology {
NRC Nuclear Regulatory Commission' i ORISE Oak Ridge Institute for Science and Education ,
QA Quality Assurance !
QC Quality Control RW# Radwaste Building structural survey unit designation j SNPS Shoreham Nuclear Power Station SP# Suppression Pool structural survey unit designation- l SU# system survey unit designation i R/h . microroentgens per hour
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l CONFIRMATORY SURVEY OF THE- )
RADWASTE BUILDING, SUPPRESSION POOL, j PHASE 2, AND PHASE 3 SYSTEMS j' SHOREHAM NUCLEAR POWER STATION
' BROOKHAVEN, NEW YORK i
.l
' INTRODUCTION AND SITE HISTORY ,
1 The Long Island Lighting Company (LILCO) constmeted 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
~t (NRC Docket File No. 50-322), which pe'rmitted reactor operations at levels not to exceed 5%
of full power, commenced in July 1985. Reactor operations continued intermittently until l 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 - I 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. l Various reactor components, piping systems, and other equipment became radiologically : i i
contaminated as a result of reactor operation. The primary contaminants that were identified ,
during characterization studies included iron-55 (Fe-55), cobalt-60 (Co-60), nickel-63, and +
smaller quantities of tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152. l l
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 includes decontamination (grinding, high pressure !
washing, etc.) or removal of contaminated portions of the reactor and other plant systems and >
' equipment. A major consideration of the decommissioning plan is to maintain the integrity, when possible, of plant structurer and systems. Activities involved with the decommissioning and termination surveys will be conducted in 4 phases. The initial phase involved the termination survey of the internal components of the main turbine, which has since been e i
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followed by termination survey,s of.the remainder of the stmetures and systems located within
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the Turbine Building as.well as the site grounds and building exteriors. Phase 2 included the .l termination survey 'of the reactor suppression pool and several systems. Phase 3 involved the !
termination surveys for the Radwaste Building. Phase 4 will address the Reactor Building. jq l
It is the policy of the NR'C to perform confirmatory surveys of facilities that have undergone; decommissioning and have requested NRC license termination. The NRC Headquarters' Division of Waste Management 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 i project as the various decommissioning - milestones are' completed. The results of the confirmatory survey of Phase 1, the turbine internal components and the. Turbine Building, Site .
l Grounds, and Building Exteriors, are the subject of separate reports'.2a l This report describes -
the results of the confirmatory process that has been completed for the Radwaste Building (Phase y 3), Suppression Pool (Phase 2), and Phase 2 systems, SITE DESCRIPTION l l
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 Long Island Sound (Figure 1). Reactor and supponing operations were conducted within .;
a 32.4 ha (80 ac) portion of a larger 202 ha LILCO owned parcel of land that is bounded on the !
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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 j area. Within this boundary are the buildings and grounds classified as the Restricted Area, also ;
known as the power block, where radiological controls had been necessary (Figure 2). Each of . j the buildings that have been or will be addressed during the confirmatory surveys are located ' ll here and are shown on Figure 2 as the Turbine Building, the Reactor Building, and the Radwaste j Building. Radwaste Building construction is predominately of concrete and structural steel with a total floor space of approximately 4,700 m2 (51,000 ft 2) which is divided between three levels at elevations 15'6"/19'6", 37'6", and 50'6"/52'6" (Figures 3 through 5). The systems and Shoreham-Brookhaven. NY - January 27.1995 2 h:\essap\repons\shoreham\brookhav.001
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' equipment housed within the Radwaste Building include the condensate demineralizers, the liquid !
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radwaste system, the ' solid radwaste storage area, the crane and truck bay, the makeup water j t treatment plant, chemical support system, and a portion of the off-gas radwaste system. The Suppression Pool is located on the 8' level of the Reactor Building and is constructed of steel j plate (Figure 6). ' Surfaces' and components within the buildings remain essentially intact l' following decommissioning activities.
l Termination surveys have been performed in accordance with Draft NUREG/CR-5849.4 LIPA' l has classified plant systems, building surfaces, and outside areas into two categories for survey, !
t 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 .;
i potentially contaminated or have known contamination, or a system which circulated, stored or .
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processed radioactive materials such that they could become contaminated, or experience neutron . j activation, or where records indicated spills or other occurrences may, have resulted in j i
contamination; unaffected areas are those portions of the SNPS that are not expected to contain- l residual radioactivity."5 Area classification was determined by radiological use history, !
environmental monitoring activities,' and the results of the previous characterization survey. f Affected and unaffected areas are further subdivided into survey units. Survey units are l f
categorized as structures (floors, walls, ceilings, and exterior surfaces of piping and equipment), t plant systems (equipment and piping internals), and exterior areas (grounds and building - a exteriors). In addition, affected survey units also have sub-classifications as suspect or non-
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suspect, and may also be classified as alpha affected if involved with fuel handling or storage. f t
For the Radwaste Building, Suppression Pool, and Phase 2 Systems, there were a total of 77 survey units were addressed, of which 60 were structures and 17 were systems. Sixty-five 'j of these survey units were classified by the licensee as affected.
I OBJECTIVES
{
. i The objectives of the co'1firmatory activities were to provide independent document reviews, review and perform field observations of the LIPA procedures for embedded piping surveys, and shoreham-Brookhaven, NY
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I develop radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and termination survey results.
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 confirmatedy survey.54 Documents were reviewed for adequacy, accuracy, completeness, and consistency. Data were reviewed for appropriateness of calculations and interpretations relative to the guidelines. In addition, ESSAP reviewed the applicable procedures and records for both the calibration of instruments used in, and the survey data generated for, three representative sections of embedded piping. Together with observational surveillance of the resurvey of one section of selected embedded piping, the documentation was evaluated for appropriateness and consistency in field application.
s PROCEDURES During the period August 22 through 25,1994, an ESSAP team visited the SNPS and performed independent visual inspections, measurements, and sampling of the Radwaste Building, Suppression Pool, and Phase 2 Systems. Surveys were performed in accordance with a survey plan submitted to and approved by the NRC.7 Nine structural survey units and either the complete or components of four system survey units were selected for confirmatory surveys.
Survey units were selected either randomly by ESSAP or based on recommendations of the NRC site representative. Survey unit designators are alpha-numeric with the first figures designating the type of unit, stmetural (building specific, RW =Radwaste, SP = Suppression Pool), or system, followed by a three-digit numeric reference. Subunits are given an additional two-digit designation preceded by X. The survey units selected and the respective classification for each were:
Shorcham-Brtmkhaven, NY - January 27,1995 *$ h:\essap\ reports \shoreham\brookhav.001
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Affected (A)/ ' Structure / System /
. Survey Unit Survey Unit Name Unaffected (U) Building Grounds RW013 Radwaste 15' North Hallway .A structure
- RW017 - Cation / Anion Regen and Resin .A' structure -
Storage Tanks Area RW023 ' Liner Fill Stations /BW Storage A stmeture Rooms (Cubicle A) h RWO40 Waste Evap./ Regen. Evap. Distil. A structure L Room I
L RWO42 Radwaste 37' North Hallway A- structure t;
RWO69 "B" RW O/G HEPA After Filter A structure Area -
l RWO72 Off Gas Desiccant Dryers Area A structure l
SP004 Suppression Pool - NW Quadrant A stmeture SP005 Suppression Pool- Area Inside A structure Vessel Pedestal SU012 High Pressure' Coolant Injection A- system Valves E41-01V-3049 and 50 SU014X09 Radwaste Influent Drain System, A system Drain Sump Tank-054 SU014X10 Radwaste Building Equipment A' system i Drain System, Drain Sump Tank-071 SU014X12 Radwaste Equipment / Components, A system Flat Bed Floor Drain Filter 1G11-FL-012 and Waste Collector Tank 1G11-TK-10A SU015 Reactor Water Cleanup System A system SUO43 Condensate Demineralizers, Tank A system 1N52-DE-002E Figures 3 through 6 indicate the structural survey units surveyed. Confirmatory surveys for SUO12, SU014XO9, SU014X10, SU014X12, and SUO43 involved individual component (s) rather than the entire survey unit.
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( Field survey activities were conducted in accordance with the applicable' sections of the ESSAP '
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( ; Survey Procedures and Quality Assurance Manuals. fAppendices A and B provide' additional; information regarding instrumentation and procedures. , The.following procedures apply to -
survey units selected for. independent confirmatory surveys.
SURVEY PROCEDURES Reference System
- LIPA established the grid system that ESSAP used for referencing measurement and sampling -
l L 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:
1mx1m. Upper surfaces and equipment were referenced to either these grids or other prominent building features. Systems were referenced by either a distance from a specific point, -
by drawings, or by prominent components.
Surface Scans Surface scans for alpha, beta, and gamma activity were performed over 100% of floor and lower -
L 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 where material may have settled or accumulated. Iocations of elevated direct radiation detected by scans were marked for further investigation. Scans were performed using gas proportional,-
GM, and Nal detectors coupled to ratemeters or ratemeter-scalers with audible indicators; 1'
Serface Activity Mess.rar, ;s For each structural survey unit, ESSAP performed a minimum of 30 direct measurements for total beta surface activity. ESSAP also performed additional direct measurements at locations of elevated direct radiation detected by surface scans. Alpha surface activity measurements were Shorehan>Brm4 haven. NY . January 27.1995 6 h:WVepomWrchmuiraAtavm1
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=, not required bscause the selected survey units were not classified as alpha affected, and no alpha -
contamination was identified by surface scans. Measurements.were' performed using gas proportional or GM detectors coupled to ratemeter-scalers. A smear sample for determining -
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removable activity levels was collected from each direct measurement location. Figures 7 I
L - through 17 show measurement and sampling locations.
g Exposure Rate Measurements Exposure rate measurements in structural survey units were performed at each accessible floor grid block where ESSAP had performed direct surface activity measurements. All exposure L
L rates were measured at 1 m above surfaces using a pressurized ionization chamber (PIC).
l Figures 7 through 14 show measurement locations. Background exposure rates were previously determined during the confirmatory survey of the Turbine Building.'
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Systems 1
l LIPA provided access points into each system or system component listed on page 5-of this report. Beta and gamma surface scans were performed within the accessible portions of each system or component, followed by direct measurements and smear samples. The total number l' of direct measurements performed and smears collected was dependent upon component size and '
accessibility and ranged from 4 to 30 measurements per system. Scans and direct measurements were performed using gas proportional, GM, and/or Na1 detectors coupled to ratemeters or ratemeter-scalers. Figures 18 through 24 show measurement and sampling locations.
Embedded Piping Confirmation of the LIPA embedded piping termination survey program was accomplished '
through on-site review and observation of the LIPA procedures for instrument calibration and -
embedded piping survey design and performance, review of the data and records for the
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u termination surveys of selected embedded piping subunits,' and independent measurements and l
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b'. sampling of selected sections of piping. Specific procedures for each activity.are described i i
- below. l f
The calibration records for the detector / instrument combinations, refeired to as " pipe crawlers',"- ,
p used during termination survey data acquisitions for three. selected embedded piping subunits' were compared with and evaluated against the required calibration and operational check-out: , ,
t procedures and standards. These UPA instrumentation procedures included the following: j i
Control of Health Physics Instrumentation (SP Number 61X080.01), Chi-Square T st and : Li Control Chart Review (SP Number 61X081.01), Detector Calibration (SP Number 66X020.11) -
I and Instrument Calibration (SP Number 66X022.02). In addition, the recalibration of one i i
detector / instrument: combination was observed. ESSAP -then performed independent measurements and calculations to confirm the level of, and distribution of, Co-60 activity on two'. j a
of the custom sources that UPA used for the calibration check on the pipe crawler detector !
assemblies. - This information was used to evaluate the appropriateness of the UPA 'statede ;
detector efficiencies. Once these parameters were established, ESSAP confirmed the UPA j t~
computer-generated surface activity measurement data conversions to disintegrations per minute .
2 per 100 square centimeters (dpm/100 cm), critical level calculations, and the action level-calculations used by UPA for identifying " hot spots" while surveying embedded piping.
Three sections of embedded piping were selected for confirmatory evaluation and independent surveys. Embedded piping subunit selection was based on recommendations of the NRC site representative. ESSAP performed surface scans and direct measurements for beta activity over a length of each selected pipe run, nominally 4 m in either direction of the access point. Access was gained through sumps, drains, traps, or openings where pipe sections had been removed.
A total of 17 direct measurements were made. The surface activity data' collected were then j compared to the UPA-generated data from the corresponding section of each pipe run and the NRC surface activity guidelines. In addition, for each of these subunits, the Termination Survey _
Design (UPA Procedure SP Number 67X001.10) was compared to the field records and i evaluated for appropriateness and consistent implementation. UPA was also requested to.-
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. resurvey portions of the selected embedded piping subunits and the results compared with the j
. original termination survey data.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to ESSAP's Oak Ridge, Tennessee laboratory for analysis and interpretation.- Smears were analyzed for gross alpha and gross beta. activity using a' low background proportional counter. Smear and direct measurement data were converted to units -
of dpm/100 cm 2. Because Fe-55 cannot be adequately detected with field instrumentation, a -
l correction factor of 1.2.'was applied to those surface activity measurements that exceeded i a
background distribution levels, referred to as the critical level (IJ. LIPA developed,' and the j I NRC approved, the use of this correction factor based on the observed Co-60 to Fe-55 activity '
ratio identified in characterization samples.5 s Exposure rates were reported in microroentgens l
per hour ( R/h). Additional information concerning major instrumentation, sampling equipment, -
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and survey and analytical procedures is provided in Appendices A and B.
The 95 % confidence level ( .), in accordance with NUREG/CR-5849, was calculated for surface l activity and exposure rates for each survey unit selected for confirmation. A direct comparison j of the ESSAP and LIPA survey unit results was also performed. i FINDINGS AND RESULTS i
l DOCUMENT REVIEW ,
1 ESSAP's review of the termination survey plan indicated that the document provided an adequate l
description of survey methodologies and general approaches. Comments were provided to the -l, NRC in a January 12,1993 correspondence.' ESSAP's review of the termination survey final' j 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 were appropriately converted, tested, and presented.
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L SURFACE SCANS Alpha, beta, and gamma surface scans identified one small area of elevated direct beta radiation .
on a suppon bracket in SP004. The surface activity level at this location was 3,800 dpm/100 cm 2. All other surface scans were comparable to background levels.
SURFACE ACTIVITY LEVELS l
The results of total and removable surface activity levels are summarized in Table 1. The data reported below and in Table 1 is the difference between the gross field sample counts and area background. The difference is then corrected for detector efficiency and geometry, sample count time, and contributions from Fe-55 (when the net count rate exceeaed the background distribution [IJ). Actual values are reported including negative surface activity levels, which occurred when the field count rate was less than the background. Of 414 measurements, 160 exceeded the I, and I exceeded the instmmentation minimum detectable activity level)
Total beta activity levels for the structural survey units ranged from -310 to 3,800 dpm/100 cm2.
The highest direct measurement was on the SP004 suppon bracket discussed previously.
Removable activity levels ranged from -1 to 6 dpm/100 cm2 for alpha and -7 to 81 dpm/100 cm2-for beta. The mean residual activity in structural survey units ranged from 14 to 510 dpm/100 cm2and -1.3 to 3.4 dpm/100 cm 2for total and removable beta activity, respectively.
Total beta activity levels in the surveyed systems ranged from -760 to 1,600 dpm/100 cm2 . The '
removable activity levels were -1 to 8 dpm/100 cm 2 for alpha and -6 to 14 dpm/100 cm2 for 2
beta. The mean beta activity levels for systems ranged from -310 to 98 dpm/100 cm for total activity and -1.3 to 1.7 dpm/100 cm2 for removable activity.
EXPOSURE RATES As determined during the Turbine Building survey, the interior background exposure rates ranged from 4 to 5 pR/h and averaged 5 pR/h at I m. Individual gross exposure rates within Shoreham Brookhaven. NY - January 27,1995 10 h:Wsap\ reports \shorchamibrookhav.001
_i
n._ -
l i
L the Radwaste Building ranged from 4 to 6 pR/h at 1 m. The average gross exposure rates for ,
all survey units ranged from 4 to 5 pR/h at 1 m. Table 2 provides a summary of the exposure rates.
EMBEDDED PIPING Review of the embedded piping instrumentation calibration and calibration check; operational source cross-checks; survey procedure review and surveillance; and review of data conversions, critical levels, and action levels showed that all facets of the embedded piping survey program were performed in accordance with procedures and that the radiological status of embedded piping had been accurately presented. Specifically, ESSAP performed cross-checks of calibration source activity as well as UPA reported detector efficiencies using representative pipe calibration geometries. The action level, in counts per minute, that UPA developed and used for determining when small areas of residual activity in excess of the guidelines were present in a section of pipe was also confirmed. A confirmation of the embedded piping survey design was also conducted. For this confirmation, ESSAP evaluated the UPA requirements for total number of measurements in a given pipe section and compared the required number to the actual number of measurements that UPA performed. Because of the unique design of the pipe-crawler detector assemblies, ESSAP also evaluated the appropriateness of surface activity data I
conversions taken from gross field counts through the final reported surface activity levels. The final evaluations of the UPA embedded piping program included field observation of embedded piping survey procedures, a comparison of original data and data generated when UPA resurveyed three sections of pipe, and independent measurements by ESSAP for comparison with UPA data. Table 3 provides a summary of the information developed during these evaluations. ,
Surface scans performed in each piping section did not identify any locations of elevated direct radiation. The ESSAP total activity results for each subunit are as follows: SU014X02 (#366),
the range was -320 to 120 dpm/100 cm2 and the mean was -20 dpm/100 cm2 ; SU014X09 (#850),
the range was -360 to 40 dpm/100 cm2and the mean was -140 dpm/100 cm2; and SU016X01 3
(#20), the range was 400 to 690 dpm/100 cm2 and the mean was 540 dpm/100 cm2 ,
i Shoreham-Broothaven. NY . January 27.1995 11 h:\cssap\ reports \shoreham\brookhav.001
COMPARISON OF RESULTS WITH GUIDELLNES i e
The confirmatory survey results were compared with both the data provided by LIPA and the 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-ganuna emitters of which Co-60 and Fe-55 are the ,
primary contaminants at SNPS. The residual surface activity guidelines are:
Total Activity l 5,000 dpm #-7/100 cm 2, averaged over 1 m2 ;
i 15,000 dpm #-7/100 cm2 , maximum in 100 cm2 ,
Removable Activity 1,000 dpm #-7/100 cm2 ;
s t As previously discussed, the detection sensitivities of the field instruments are such that the residual Fe-55 activity cannot be detected. Therefore, total and removable surface activity measurements were 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 (p, or upper confidence level [UCL]), relative to the guidelines, in accordance with Draft l NUREG/CR-5849. These results are provided in Tables 4 and 5. ;
No direct measurements exceeded the average or maximum total activity guideline. Overall, f surface activity levels within each survey unit also satisfied the guidelines at the 95 % confidence level. All removable activity was below guidelines at the 95% confidence level. The maximum removable activity identified was 81 dpm/100 cm2.
A comparison of the ESSAP mean surface activity levels to the LIPA mean activity levels showed that the ESSAP mean was statistically less than or equal to the respective mean -
determined by LIPA for 6 of the 15 confirmatory survey units. The conditions established have ShordmBnxAhmn NY - knary 27,1995 12 h:\essap\ reports \shoreham\brookhsv.001 I.
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1 therefore been satisfied for these survey units. However, the ESSAP mean was greater than the)
[', ; UPA mean!for survey. units RWO13,. RW017, RW023, RWO42,= RWO72, SP004,- SUO43, . j;
' S_U014XO9, and SU014X10;' therefore, additional evaluation was necessary. .
~Of the nine units where the ESSAP total surface activity mean was higher than the LIPA mean, !
- h. UPA qualified the release record data for survey units RW013, RW017, RWO23, SP004, arxl '
c l SUO43'as containing' excessive negative measurements. According to UPA, this was due to 1 observed background levels being lower than the generic site backgrounds that.were used for- q surface activity measurement conversions. As a result, the mean survey unit total activity levels ;
were biased low. The maximum surface activity level obtained by ESSAP for these survey -;
2 units was 3,800 dpm/100 cm in SP004, and the maximum survey unit mean and UCL, found q 2 2 in RW023, was 300 dpm/100 cm and 400 dpm/100 cm , respectively. Although the condition l of the ESSAP mean being less than the UPA mean was not satisfied for these survey, units, q both termination and confirmatory survey surface activity levels are below the 5,000 - l 1
2
- dpm/100 cm average guideline. ,
' r The ESSAP surface ' activity means for survey units ~.RWO42, RWO72, SU014X09, and -
. 1 SUO14X10 were statistically higher than those for UPA, and UPA had not qualified the data? l for these units as biased low. Therefore, the LIPA surface activity levels, mean activity levels, 1
and UCLs for all remaining survey units were evaluated to determine the potential impact on the -
.I LIPA reported status of the Phase 2 and Phase 3 survey units, relative to the guidelines. The !
2 maximum LIPA survey unit mean of 2,317 dpm/100 cm (SUO67) and maximum UCL of - ~
2 812 dpm/100 cm (RWO61) were within acceptable criteria. The maximum observed difference !
2 of ESSAP and LIPA means was 330 dpm/100 cm . If this difference in activity levels were t
. applied to.the above, overall surface activity levels would not be significantly altered 'and the !
conclusions reached, that the radiological status of the Phase 2 and 3. survey units satisfies the !
guidelines, would remain valid.
] .
For embedded piping, ESSAP's surface scans and direct measurement results did not indicate q the presence of residual surface activity within the embedded piping, with most surface activity l a
levels comparable to background and all levels below the minimum detectable activity (MDA) .
{
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ShorehandBrookhaven, NY . January 27,1995 -13 h:\essap\ reports \shoreham\brookhav.001 .
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N of the: instrumentation. The comparison of the UPA and ESSAP embedded' piping direct
- measurement data indicates two discrepancies. - First, the LIPA mean activity levels (Table 3)
~ for two of the three sections of pipes investigated do not agree for the original survey and the ~
l !
resurvey of SU014X02 (#366) and SU014X09 (#850). The probable cause'of the difference in .
the means of the LIPA surveys may be attributed to variations in background levels. The' f
difference in the average activity. levels between the initial survey and resurvey of SU014X02 -
. (#366) was 22 counts' per. minute (cpm) (3.7 cpm per detector), and for SU014X09 (#850) the l
difference was 9 cpm (1.5 cpm per detector). The initial survey results and resurvey results for j SU016X01 (#20) were comparable.
[
j
. The second discrepancy was identified when the comparison of the means indicated that the ESSAP mean was statistically greater than the LIPA mean for each of the three data sets. The . -l observed difference in the surface activity level means between LIPA and ESSAP may' be the result of the differences in detector geometry. Each LIPA direct measurement location' consists of a 93 square centimeter (cm2 ) area. LIPA's reported total activity is the additive activity contribution from six locations distributed around the interior circumference of each 0.3 mi section of' embedded piping where a measurement was performed, whereas ESSAP performed i
one direct measurement, representing a 15.5 cm2 . area, every 0.3 to 0.6 m. Based'on these'. a factors, LIPA's conclusions as to the overall radiological status of the SNPS embedded piping-- .j t
appear to be appropriate. !
1 Exposure rates were compared with those obtained by LIPA and tested at the 95% confidence l level, relative to the 5 R/h above background guideline currently being used by the NRC .l (Table 4).' The Radwaste Building exposure rates were comparable to background exposure rate- (j levels and confirmed the findings presented by LIPA. j l
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ShorchanvBrookhaven. NY . January 27,1993 14 h:\cssap\ reports \shoreham\brookhsv.001 1
f5
SUMMARY
p 4
ESSAP performed confirmatory activities for the Radwaste Building, Suppression Pool, and.
- Phase 2 systems at the Shoreham Nuclear Power Station in Brookhaven, New York.- .
Confirmatory activities included document reviews, and during the period August 22 through
. 25, 1994, independent surface scans', surface' : activity measurements, . ' exposure . rate -
measurements, and operational surveillance were performed.
The survey results confirm the results of the LIPA termination surveys. These findings indicate.
that total and removable surface activity levels and exposure rates were'below the'NRC 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, s
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Shoreham-Brookhaven. NY January 27.1995 18 h:\essap\ reports \shoreham\brookhav.001 l
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FIGURE 7: Rodwoste Building, Radwoste 15' North Hollway (RWO13) -
Measurement and Sampling Locations .
shoren nrothaven. rn . J.ouary 27,1995 22 h;\c588P\ rtPorts\shoreham\brookhav.001
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METERS FIGURE 8: Radwaste Building, Cation / Anion Regen. and Resin Storage Tanks Area (RWO17) - Measurernent and Sampling Locations ;
Shoreham Brookhaven. NY January 27.1995 23 h \c5$$rcPortsishoreham\brookhav.001 ,
i 258-006 (3)
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FIGURE 9: Radwaste Building, Uner Fill Stations /BW Storage Rooms i
(Cubicle A) (RWO23) - Measurement and Sampling Locations Shoreham-Brookhaven. NY - January 27.1995 24 h:bsap\ reports'shoreham\brookhav.001
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4 EXPOSURE RATE ME ERS FIGURE 10: Rodweste Building, Weste Evap./ Regen. Evap. Distil. Room (RWO40) -
Measurement and Sampling Locations h:\cssap\ reports \shoreham\brookhav.001 ShoreharwBrookhaven. NY . January 27,1995 25
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FIGURE 11: Radwaste Building, Radwaste 37' North Hallway (RWO42) -
Measurement and Sampling Locations Shoreham-Broolhaven, NY . January 27,1995 26 , &mpVeponsbhorehamWrmkhav.M1
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FIGURE 12: Radwaste Building, "B" RW O/G HEPA After Filter Area (RWO69A) -
Measurement and Sampling Locations h:\essap\ reports \shoreham%rookhav.001 ShorthanBrtdhaven, NY - January 27,1995 27 1
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METERS I FIGURE 13: Radwoste Building, "C&D" Dryer Skid Area (RWO698) - l' Measurement and Sampling Locations h:\essap\repons\shorehannbrookhav.001 Shoreham-Brookhaven. NY - January 27,1995 28 I
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6 2 METERS FlGURE 14: Rodweste Building, Off Gas Desiccant Dryers Area (RWO72) - ,
Measurement and Sampling Locations .
h:\e==aP\ reports \shoreham\brookhav.001 !
Shorcharn-Brookhaven. NY - January 27,1995 29
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I FlGURE 15: Reactor Building, Suppression Pool, NW Quadrant (SP004)
Lower Walls and Floor - Measurement and Sampling Locations ShoretuuwBrookhaven. NY January 27,1995 30 h*''*""**"**'*"'"**"""
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0 METERS FIGURE 16: Reactor Building, Suppression Pool, NW Quadrant (SP004)
Upper Wcils - Measurement and Sampling Locations Shoreharn-Brookhaven. NY - January 27.1995 31 hws=p*rtsishorehain*rookha' 001
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H MEASUREMENT / SAMPLING LOCATIONS @ i SINGLE-POINT 9 LOWER WALLS AND FLOOR g SINGLE-POINT h UPPER WALLS FEET 0 6 W
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METERS l
l FIGURE 17:
Reactor Pedestal (SP005 Building,) Suppressionand
- Measurement Pool, Area Inside Sampling Locations Vessei Shoreham Brookhaven. NY - Ja sary 27, im 32 h:\cs5=P\ reports \shorehamibrookhav.001
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FIGURE 18: Reactor Building, HPCI Valves E41-01V-3049 and 3050 (SUO12) -
Measurement and Sampling Locations ShorehanFBrmelhaven. NY - January 27.1995 33 h;sess psreportisshorehamshrookhav. cot 1
i
. . . - ~ _ - - _ - - _ _ _ _ _ _ - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - . - - - - . - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ - - - - - - - - - - - _ _ _ - - - - - _ - - - -
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a CONCRETE h,
0 N 6 P-e O METERS 1 FIGURE 19: Radwaste Building, . .dwaste influent Drain System, Drain Sump Tank 054 (SU14X09) - Measurement and Sampling Locations Shorcham-Brookhaven. NY - January 27.1995 34 h:sessapsreport>\ihorehamsbrookhav ool
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METERS i r
FIGURE 20: Rodweste Building Equipment Drain System, Drain Sump Tonk-071 :
(SUO14X10) - Measurement and Sampling Locations ;
i Shoreharn-Brookhaven, NY January 27, im 35 h:58P \r:Pom\shoreham\brookhav.001
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. ~ . _
f- i 258-018 (3) i l
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MEASUREMENT / SAMPLING h LOCATIONS 4 DIRECT MEASUREMENT h
d FIGURE 21: Radweste Building, Radweste Equipment / Components, Flat Bed Floor Droin Filter 1G11-FL-012 (SUO14X12) - Measurement and Sampling Locations h:\essap\ reports \shoreham\brookhav.001 Shoreham-Brookhaven, NY - January 27,1995 36
258-021 (4) b l
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l FIGURE 22: Rodwoste Building, Rodwoste Equipment / Components, Waste Collector l Tank 1G11-TK-10A (SUO14X12) - Measurement and Sampling Locations '
W58PWpahdm%nehv.M1 ShorrtmBnxAhaven, NY . January 27.1995 37
( '
258-016 (2)
.11____g.__________ ________
W_ _ _ _ _ _ _
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_ _ _ _ _ _ _ _ .. . . . - _ _ _ - _ _ _ _ _ _a ( _ _ _ .g__ _ _.__ 9
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0 6 l m i 0 2 j j
l l FIGURE 23: Reactor Building, Reactor Water Clean-up System Components (SUO15) - Measurement and Sampling Locations sixnh-anmu=ven, NY - January 27,1995 38 h:\c158P\ reportsistereham\brookhav.001
X
'258-022 (3)-
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FIGURE 24: Radwaste Building, Condensate Demineralizers, Tonk 1N52-DE-002E i (SUO43) - Measurement and Sarnpling Locations l SWBrookhaven. NY - January 27,1995 39 hhapVcpomutarcham%raAhav21 ;
I
, . - . ~ ~
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F j TABLE 11 'l i-
SUMMARY
OF SURFACE ACTIVITY. LEVELS .i RADWASTE BUILDING, SUPPRESSION POOL, AND PHASE 2 SYSTEMS SHOREHAM NUCLEAR POWER STATION - 1 BROOKHAVEN, NEW YORK -
l
._ i
- . Removable - l Number of Total Activity Range -Activity Range - -!
Location" Measurement Locations -
. (dpm/100 cm2)
' Betab,e (dpm/100 'em2)4 i ;
d Alpha, Beta' -
RW013[15' N6rth Hallway 1 -
' ^
ME* - ' '% W j Floor 11 10 to 540 -1 to 1 . -5 to 1 ' !
. t Iower Walls 9 -260 to 260 -1 to 1 -4 to 4 - t Upper Walls -
5 -210 to 100 -1 to 3 - -5 to 3 -l j
i Equipment 5 -260 to 450 -1 to 1 -3 to 8 -
RW017,-15' CAT /AN/REGN Tank 9 * '
- ' l Floor 10 -200 to 360 -1 to 3 -3 to 9 :
Lower Walls 10 -100 to 190 -1 to ! ! -4 to 3 -
j ,
Upper Walls 7 -100 to 38 -1 to 1 -5 to 0 -i Equipment 3 -200 to -14 -1 to 3 -4 to 3
]
RW023,19'TCubicle AfLineiStations: ^ ^
l Floor 9 370 to 1100 -1 to l ' -4 to 3 I Walls 11 -250 to 490 -1 to 3 -5 to 5 Upper Walls 3 -170 to 230 1- O to 8 j Equipment 7 170 to 200 -1 to 1 -5 to 3 l RW640,t15' Evaporation Distil R6ami '
J - - -
a47 T j Floor - 13 220 to 440 -1 to 3 -5 to 9 l Walls 7 87 to 330 -1 to 1 -4 to 3 ) i Upper Walls 4 -26 to 180 -1'to 3 -1 to 5 j Equipment - 6 -43 to 660 -1 to 3 -5 to 1 ii
~
RWO42l37' NorttiHallway.: - ' ' ^'
^ - 4
. 1 -
j Floor 14 450 to 920 -1 to 1 -4 to 4 !
Lower Walls 6 230 to 460 -1 to 5 ' 4 to 3-l Upper Walls 3 190 to 280 -1 to 5 0 to 3 j Equipment 7 -150 to 520 -1 to 1 -5 to 3 )
Shoreham-Brookhaven NY + January 27,1995 40 h:\cssap\ reports \shoreham\brookhav.001
~
TABLE 1 (Continued) ,
l'
SUMMARY
OF SURFACE ACTIVlTY LEVELS RADWASTE BUILDING, SUPPRESSION POOL, AND PHASE 2 SYSTEMS
' SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK Removable - -
Number of Total Activity Range Activity Range >
' Location
- Measurement (dpm/100 cm2) (dpm/100 cm ) _ 2 Locations Beta b>*
Alpha, Beta' ;
RWO69, HEPA After Filter Area E Floor 11 110 to 490 -1 to 4 -3 to 6 Lower Walls 9 -62 to 130 -1 to 3 -4 to 10 Upper Walls . 5 -48 to 95 -1 to 1 -4 to 3 ;
Equipment 5 -210 to 140 -1 to 1 -1 to 3 ,
RWO72, Gas Desiccant Dryer: Area - !
Floor 11 410 to 920 -1 to 3 -4 to 8 Lower Walls '
'9 250 to 550 -1 to 3 -5 to 5 Upper Walls 3 270 to 380 -1t3 -5 to 1 ,
Equipment 7 81 to 580 -1 to 3 -5 to 3 j SP004(Suppression Pool NW Quad.t 31 -310 to 3800 -1 to 6 -5 to 81 SP005, Suppression Pool'In.' Pedistal ? 35 -210 to 350 -1 to 3 -7 to 8 SUO124 Hi Pressure Coolant Injection 4 -440 to -200 -1 to 1 -5 to 8 ~
SUO14 :x'09, Tank 54,' Influent Drain ~-' -
31 -320 to 870 -1 to 1 -3 to 6 SU614 x 10, Radwaste Equipment Drains' 11 -760 to 1600 -1 to 1 -4 to 6
~
SUO14Lx 12,'Radwaste Equipment / Comp? 50 -720 to 440 -1 to 5 -6 to 14 ~
SU015, Reactor Water Cleanup Systens 30 -520 to 1100 -1 to 5 -4 to 5 ,
SUO43l Condensate Demineralizer? 12 -270 to 300 -1 to 8 -5 to 3 4
' Refer to Figures 7 through 24.
'd Beta activity levels corrected for Fe-55 contribution as appropriate. j
'MDAs = 250 to 1100 dpm/100 cm2, d ;
MDA = 12 dpm/100 cm2,
'MDA = 16 dpm/100 cm2, i
f Shnrcham-Brookhaven. NY - January 27,1995 41 h:\essap\reporu\shoreham\brookhav.001 4
f .
~
TABLE 2
, INTERIOR EXPOSURE RATES :
RADWASTE BUILDING SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK tion, Number of Measurement Net Exposure Rates -
Locations at 1 m (gR/h)b RW013 11 -1 to 0 ,
RW017 6 -1 to 0 RW023 8 -1 to 0 RWO40 6 -1 to 0 RWO42 13 0 to 1 RWO69 6 O to 1 RWO72 11 0
' Refer to Figures 7-14.
b Site backgrouDd CXpOSure rate'WaS 5 pR/h.
4 i
i l
)
1 i
J i
J Shoreham-Brookhaven. NY - January 27,1995 42 h:\essap\ reports \shoreham\brookhav.001
ff 1 TABLE 3 L l EMBEDDED PIPING PROGRAM
SUMMARY
l SHOREHAM NUCLEAR POWER STATION 1 BROOKHAVEN, NEW YORK 1
1 TCalibration:
Pipe Efficiency 4" Pipe LIPA 6 detector Pipe Crawler Assembly 0.134' ESSAP HP-260 0.146b 8" Pipe LIPA 6 detector Pipe Crawler Assembly 0.152' ,
ESSAP HP-260 0.163 b Description LIPA Expected / Actual
- ESSAP Confirmation 4" Pipe Crawler Calibration Operational Check 44/48 (dpm/cm2) 44 (dpm/cm2) '
Source Activity (dpm/100 cm2 )
Action Level (for a 15,000 dpm/15 cm2 hot spotd ) 2408 cpm /830 cpm' 2410 cpm Survey Designi Required Number of Measurements Confirmed Number of b""'I "II Measurements (Per SP No. 66x020.11)
SU0l6 x01 (#20) 14 15 SUO14 x02 (#366) 28 30 SUO14 x09 (#850) 26 28
? D$ts Conversion'J LIPA ESSAP Confirmation Location Surface Activity Critical Level Surface Activity Critical Level (dpm/100 cm2) (dpm/100 cm 2) (dpm/100 cm2) (dpm/100 cm2) 20-1-3 -290 270 -290 270 l
20-5-2 -298 270 -298 270 366-2-1 -382 175 -382 175 ;
366-5-2 -271 181 -271 181 366-9-3 -338 178 -338 178 -
5thBrookhaven. NY - January 27.1995 43 h:\essap\ reports \shorehamil,rookhav.001
J I- i 1
TABLE 3 (Continued) t L EMBEDDED PIPING PROGRAM
SUMMARY
SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK ,
cData ConversionI(Continueil) .
LIPA -ESSAP Confirmation Location Surface Activity Critical Level Surface Activity Critical Level (dpm/100 cm2) (dpm/100 cm2) (dpm/100 cm 2) (dpm/100 cm2) 850-3-2 -508 257 -508 257 850-5-1 -556 254 -556 254 850-6-3 -411 263 -411 263 850-8-1 -556 254 -556 254 Survey Results ;
Survey Unit Data Origination SUo16x01 (#20) SUo14x02 (#366) SUO14x09 (850)
LIPA Termination Total Activity Range -468 to 169 -401 to -111 -379 to 16 Survey (dpm/100 cm2)
Mean Activity -245 -240 -196 ,
(dpm/100 cm2) ,
LIPA Fesurvey Total Activity Range -395 to -121 -469 to -271 -581 to -315 (dpm/100 cm2)
-245 -337 -488 Mean (dpm/100 Activity) cm ESSAP Survey Total Activity Range 400 to 690 -320 to 120 -360 to 40 .'
(dpm/100 cm2)
Mean Activity 540 -20 -140 (dpm/100 cm2)
'Per Table 4.3 Shoreham Decommissioning Project Termination Survey Plan, December 1993.
b Determined using an LIPA NIST traceable flexible mylar Co-60 source placed inside of a 4" and 8" piping spool piece.
- Determined from 8/19/94 LIPA Multiple G-M Detector Assembly Calibration Check Data Sheet -
(SPF66x020.11) for detector assembly IZ12-100PC4-0001.
d Action level developed to identify small areas of contamination measuring less than 100 cm2 and matching a pipe-crawlers individual " pancake" detector active area.
'830 cpm is the LIPA alarm setting for the 6 detector assembly /ratemeter-scaler combination, where additional ,
investigation of possible hot spots is required.
' Data points analyzed were representative of information collected during the resurvey of embedded piping subunits performed by LIPA. Data was tracked for accuracy from the field records to the final computer i generated report.
Shortham-Brookhaven. NY . January 27,1995 44 h:\essap\ reports \shoreham\brookhav.001
(
p l
1 1
TABLE 4
' CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
-STRUCTURES, RADWASTE BUILDING AND SUPPRESSION POOL 1 SHOREHAM NUCLEAR POWER STATION I BROOKHAVEN, NEW YORK I Radiological Survey Unit * ,
RW013 RWO17 RWO23 RWO40 RWO42
~
Total Beti Activity (dpni/100 crh2) \ ,
- of Direct Measurements . 30 30 30 30 30 Mean(X) 82 14 300' 240 430 LIPA X -170 -130 13 -
110 280 Fa 140 60 400 290 510 5,000/15,0000 dpm/100 cnf Yes Yes Yes Yes Yes >
Guidelines Satisfied Removable Beta' Activity'(ddI1/100 chf)6 6
- of Smears 30 30 30 30 30 Mean(X) -0.5 -0.1 -0.4 0.2 -1.3 LIPA X 7.5 2.6 3.9 3.2 0.3 Fa 0.4 0.9 0.6 1.2 -0.5 1,000 dpm/100 cnf Yes Yes Yes Yes Yes Guideline Satisfied Exposure Rates at 1 m (pR/h)i '
- of Exposure Rate Measurements 11 6 8 6 13 Net Mean (X) -0.7 -0.9 -0.4 -0.5 0.2 Net LIPA X -0.2 0.5 0.4 0.0 0.2 Fa -0.6 -0.7 -0.1 -0.2- 0.3 5 pR/h Aboyc Background Yes Yes Yes Yes Yes Guideline Satisfied i
ShhBrookhaven. NY - January 27.1995 45 h:\essap\itports\shoreham\brookhav.001
g i e
i t
TABLE 4 (Continued) ;
p' CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
-STRUC'IURuS, RADWASTE BUILDING AND SUPPRESSION POOL i
SHOREHAM NUCLEAR POWER STATION 1 BROOKHAVEN, NEW YORK i Radiological Survey Unit" l
Summary '
RWM9 RWO72 SP004 SP005 2
Total Beta Activity (dpm/IGO cm)
- of Direct Measurements 30 30 31 35 l Mean(X) 93 510 110 100 .
LIPA I 360 280 -220 76 !
F= 140 580 350 150 5,000/15,0000 dpm/100 cnf Yes Yes Yes Yes l Guidelines Satisfied l Remavable Beta' A'ctivity '('dpm/100 cnf)h :; ,
{
- of Smears s 30 30 31 35 Mean(X) 0.3- 0.1 3.4 -0.2 LIPA X 3.4 2.9 9.0 5.0 l'a 1.2 1.2 8.0 0.6 ;
1,000 dpm/100 cnf Yes Yes Yes Yes l Guideline Satisfied Fere Rates at I m (gR/h)- j c
- of Exposure Rate Measurements 6 11 - -
l Net Mean (X) 0.3 0.0 - - I Net LIPA X 0.1 0.1 - -
Fa 0.4 0.2 - -
f 5 pR/h Above Background Yes Yes - -
l Guideline Satisfied ;
i
- Refer to Figures 7 through 17. [
b All alpha removable activity was less than 12 dpm/100 cnf. j
- = Measurements not performed.
[
i ShhBrtuthaven. NY January 27.1995 46 h wsap\reponsumrchamibrookhav .001 !
i
i-TABLE 5 CONFIRMATORY RADIOLOGICAL STATUS
SUMMARY
--SYSTEMS SHOREHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK Radiological Survey Unit" Summary SUO12. SUO14 x 09 SUO14 x 12 SUO14 x 10 SUO15 SUO43 Total Beta Activity (dpm/100 cnf)
- of Direct Measurements 4 31 11 50 30 12 Mean(X) -310 -48 26 '80 -32 66 LIPA X 150 -170 -170 11 87 4.6 14 -190 42 170 180 59 160
. 5,000/15,0000 dpm/100 cnf Yes Yes Yes Yes Yes Yes Guidelines Satisfied 2
Removable Beta Activity'(dpm/100 cm)6'
- of Smears 4 11 7 50 25 12 Mean(X) 0, 0.9 -1.3 1.7 0.2 -0.3 LIPA X 7.2 13.9 6.6 13.1 5.8 16.7 14 6.9 2.8 1.3 2.6 1.0 1.0 1,000 dpm/100 cnf Yes Yes Yes Yes Yes Yes Guideline Satisfied
' Refer to Figures 18 through 24.
b All alpha removable activity was less than 12 dpm/100 cnf. J l
l l
l l
i Shorelem4nxAhaven. NY - January 27.1995 47 h:\cssap\repons\shoreham\brookhav.001
h4 4 ,
w 6 g m _ , q i
g;
. REFERENCES. -l pf
.l 1.1 Long-Island. Lighting, Company, "Shoreham Nuclear Power Station Site Cimism. dos q Program Final Report," May 1990. j t
- 2. ' T. J. Vitkus,' ORISE, " Confirmatory Survey of the Turbine Internal Ccw@ms, Shoreham j
- Nuclear Power Station, Brookhaven, New York," July.1993. -i
~
' 3. ' T. J. Vitkus,' ORISE, " Confirmatory Survey of the Turbine Building, Site Grounds, and Site' l 4' Exteriors, Shoreham Nuclear Power Station, Brookhaven,' New York," September 1994.
- 4. J. D. Berger, Oak Ridge' Associated Universities, Draft " Manual for Conducting Radiological i Surveys in Support of License Termination," NUREG/CR-5849, June 1992. '
- 5. Long Island Power Authority, "Shoreham Decommissioning Project, Termination Survey Plan, ;
Revision 1," April,1993. j
- 6. Long Island Power Authority, "Shoreham Decommissioning Project Termination Survey Final . l Report, Volumes 1 through 5," September,1993.
l
- 7. Ietter from T. J. Vitkus, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission, " Final - l Confirmatory Survey Plan for the Shoreham Nuclear Power Station, Brookhaven, New York - ,
Docket File No. 50-322,NNovember 4,1993. .
- 8. . Ietter from D. N. Fauver, U.S. Nuclear Regulatory Commission, to T. Vitkus, ORISE, 1 July 1~, 1993. .i l
- 9. Ixtter from M. R. Landis, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission, "Shoreham Decommissioning Project, Termination Survey Plan, Revision O, Shoreham Nuclear ,
.j Power Station, October 1992," January 12, 1993. l
- 10. U.S. Nuclear Regulatory Commission, " Guidance and Discussion of Requiirments for an '
Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1, !
September 1984.
.l senroou=vens - unuary n im 48 h:W.cAhortham\brookhav.001
~
L' .
i I
a APPENDIX A MAJOR INSTRUMENTATION E
i s
i s
t r
l t
Shorcham-BrnoLieven. NY - January 27.1995 h:\essapireporuuhorcham\brnokhav.001
l' APITNDIX 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.
DIRECT RADIATION MEASUREMENT Instruments >
Eberline Pulse Ratemeter Model PRM-6 (Eterline, Santa Fe, NM) }
l Eberline " Rascal" Ratemeter-Scaler -
Model PRS-1 !
(Eberline, Santa Fe, NM)
Ludlum Ratemeter-Scaler Model 2221 '-
- (Ludlum Measurements, Inc.,
Sweetwater, TX) .
Detectors Eberline GM Detector i
Model HP-260 Effective Area,15.5 cm2 (Eberline, Santa Fe, NM) i Imdlum Gas Proportional Detector Model 43-37 Effective Area,550 cm2 (Ludlum Measurements, Inc.,
Sweetwater, TX)
Imdlum Gas Proportional Det *or Model 43-68 Effective Area,100 cm2 (Ludlum Measurements, Inc., -
Sweetwater, TX) i Shoreham Bnx4 haven, NY - January 27.19c5 A-1 h:\essap\ reports \shoreham\brookhav.001 l
f? g .
L
- Reuter-Stokes Pressurized Ion Chamber-
~
' Model RSS-111'
. (Reuter-Stokes, Cleveland, OH),
Victorcen Nal Scintillation Detector Model 489-55 3.2 c:n x 3.8 cm Crystal
, - (Victoreen, Cleveland, OH)1 LABORATORY ANALYTICALINSTRUMENTATION Low Backgroutul Gas Proportional Counter
.Model LB-5100-W (Oxford, Oak Ridge, TN) _
i s
Shoreham Brookhaven, NY January 27,1995 A-2 h:\cssap\reporu\shoreham\brookhav.001
I I
-l
- 1 e ;
l APPENDIX B SURVEY AND ANALYTICAL PROCEDURES l
s l
Shmdam-Brookhaven. NY - January 27,1995 h:\cssap\ reports \sborcham\brookhav.001
(;
v<
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 1 cm. A large surface L area, gas proponional floor monitor was used to scan the floors of the surveyed areas. Other -
2 surfares were scanned using small area (15.5 cm , 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 instmment. Combinations of detectors and instmments used for the scans were:
Alpha -
. gas proportional detector with ratemeter-scaler Beta -
gas proponional detector with ratemeter-scaler pancake GM detector with ratemeter-scaler Gamma -
Nal scintillation detector with ratemeter Surface Activity Measurements Measurements of total beta activity levels were performed using GM and gas proportional detectors with ponable ratemeter-scalers.
Count rates (cpm), which were integrated over 1 minute in a static position, were convened to activity levels (dpm/100 cnf) by dividing the net rate by the 4 r efficiency and correcting for the active area of the detector. The beta activity background count rates for the GM and gas proponional detectors ranged from 22 to 34 cpm and from 129 to 174 cpm, respectively. Beta efficiency factors Shoreham-Brookhaven. NY January 27.1995 B-1 h:\cssap\ reports \shoreham\brookhav.001
p c ranged from 0.16 to 0.17 for the GM detectors and from 0.21 to 0.23 for the gas proportional
! ' detectors. 'Ihe effective window for the GM arxl the gas proportional detectors were 15.5 cm2 and .
100 cm2, respectively.
Surface activity measurements which exceeded the normal background distribution were corrected '
for the Fe-55 contribution by multiplying the dpm/100 crrf field activity level by a factor of 1.2. The
~
instmment response level at which the detector output could be considered above background was defined as the critical level (IJ. This level was defined for each detector /instmment combination as follows: -
1.% "E '*""' '' + N 'N '#" '*""' '"
% Sample count time Background count time (Detector Epiciency) (Detector Geometry)
Removable Activity Measuremen_ts 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.
Exposure Rate Measurements Measurements of gamma exposure rates were performed using a pressurized ionization chamber (PIC).
l ANALYTICAL PROCEDURES Removable Activity Smears were counted on a low background gas proportional system for gross alpha, and gross beta activity.
Shoreham-Bmothaven. NY - January 27.1995 B-2 h:sessapsreparisinhorehamsbrookhav. con !
.c
[
1 l
. UNCERTAINTIES AND DETECTION LIMITS The uncertainties associated with the analytical data presented in the tables of this report represent the 95% confidence level for that data. These uncenainties were calculated based on both the gross sample count levels and the associated background count levels. Additional uncenainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this ,
repon. _
t 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 + (4.66VBKG)]. Although data is -
reported as actual values, including negative values, in the document text and tables, the MDAs for total and removable activity levels are provided in the f otnotes of applicable tables. Because of , .
variations in background levels, measumment efficiencies, and contributions from other radionuclide ':
in samples, the detection limits differ from the sample to sample and instmment to instmment.
CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards, traceable to NIST, .
when such standard were available. In cases where they were not available, standards of an industry mcognized organization were used. Calibration of pressunzed ionization chambers was performed by the manufacturer.
Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Prognan:
- Survey Procedures Manual, Revision 8 (December 1993) ;
- Laboratory Procedures Manual, Revision 8 (August 1993) -
- Quality Assurance Manual, Revision 6.1 (November 1993)
ShoreharwBr=Ahaven. NY . January 27. Iws B-3 hwapvep=ehmaamwr=*hav.mi
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The procedums contained in these manuals were developed to meet the' requirements of DOE Ortler 5700.6C and ASME NQA-1 for Quality Assurance and contain measures to assess processes during their perfonnance.
~ Quality control procedures include:
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- ~ Daily instmment backgmund and check-source measumments to confirm that equipment operation is within acceptable statistical fluctuations.
- Training and certification of all individuals performing procedums.
- Periodic internal and external audits.
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i APPENDIX C !
REGULATORY GUIDE 1.86, TERMINATION OF OPERATING !
, LICENSES FOR NUCLEAR REACTORS
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Shoreham-Brooktaven, NY - January 27,1995 h:\cssapirepombhoreham\brooktav.001 1
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, U S, ATOMIC ENERLY COMMISSION June 1974 REGULATORY GUIDE
- DIRECTORATE OF REGULATORY STANDARDS L
REGULATORY GUIDE 1.86 l TERMINATION OF OPERATING LICENSES l FOR NUCLEAR REACTORS
! A. LNTRODUCTION important to the safety of reactor operation is no longer f sequired Once this possession-only license is issued, Section 50.51, " Duration of license, renewal," of 10 reactor operation is not pennitted. Other activities from CFR Part 50, " Licensing of Production and Utilization the reactor and placing it in storage (either onsite or Facilities," requires that each 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 licensr Aving a possession +nly license must retain, license may be either renewed or termmated by the with the Part 50 license, authorization for special nuclear Conunission. Section50.82,"Applicationsfortermmation , 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 termmate an operating license, including the Applicability to Licensing of Byproduct Material"), and :
requirement that the dismantlement of the facility and source inaterial (10 CFR Pan 40, " Licensing of Source disposal of the component pans not be inimical to the Material"), until the fuel, radioactive components, and l common defense and security or to the health and safety sources are removed fmm the facility. Appropnate of the public. This guide describes methods and administrative controls and facility requirements are j procedures considered acceptab!c by the Regulatory staff imoc.cd by the Part 50 license and the technical for the termmation of operating licenses for nuclear specifications to assure that pmper surveillance is i reactors. The advisory Cormnittee on Reactor Safeguards performed and that the reactor facility is maintained in a has been consulted concernmg this guide and has safe condition and not operated.
concurred in the regulatory position.
A possession-only license permits various options and l B. DISCUSSION procedures for decomnussioning, such as mothballing, entombment, or dismantling. The requirements imposed When a licensee decides to termmate his nuclear depend on the option selected.
scactor operating license, he may, as a first step in the pmcess, request that his operatmg license be amended to Section 50.82 provides that the licensee may dismantle restrict him to possess but not operate the facility. The 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 researth possession +nly 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 j
)
USAEC REGULATORY GUIDES c,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,n,,,,,,,,
anguietoey oundee are issued to decribe end en k. evenewe to the pubiac 8"nd to it= u.s. Atomic Energy commission, wahington, o.c. 2054s.
methods acceptst de to the AEC regulatory staff of implementm0 specific parts Anon a Way underds. Canonu and sugguons tw Of the Comentsalon's tegulations.10 origenets techniouse used by the staff in p
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evaluatinD uante. SpeGif6c wou,,y problems.or o es e,e -t postulated euh.dtut. accidents,..orsa to,o,rovide
- n. end guidance to compthence wtth them la riot required. Methods and solunons cliffererit from those met out in the ptsdes will be acceptable if they provide a tmasa for the M f ng an W hh r sisite to the issuance or continuance of a permit or license by the w 6. hh
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not.: Section ei.ctronicay reproduc.%. ;.notocopy. C-1 f
. .m, funher use. He site from which a reactor has been c. Any pmposed changes to the technical specifications removed must be decomamled. as necessary, and that reflect the possession-only facility status and the inspected by the Comnussion to determme whether necessary dimeembly/ retirement activities to be unrestricted access can be approved. In the case or performed.
nuclear power reactors, dismantling has usually been accomplished by shipping fuci offsite, making the reactor d. A safety analysis of both the activities to be moperable, and disposing of some of the radioactive accomplished and the pmposed changes to the technical b components. specifications.
- e. An inventory of activated materials and their Radioactive components may be either shipped off-site location in the facility.
for burial at an authorized burial ground or secured on the site. Rose radioactive materials remaining on the site 2. ALTERNATIVES FOR REACTORRETIREMENT must be isolated from the public by physical barriers or other means to prevent public access to hazardous levels Four altematives for retirement of nuclear reactor l
of radiation. Surveillance is necessary to assure the long facilities are considered acceptable by the Regulatory term integrity of the barriers. The amount of surveillance staff. Rese are:
required depends upon (1) the potential hazard to the health and safety of the public from radioactive material a. Mothballing. Mothballing of a nuclear reactor remammg on the site and (2) the integrity of the physical facility consists of putting the , facility in a state of barriers. Before areas may be released for unrestricted protective storage. In general, the facility may be left use, they must have been h M ud or the intact except that all fuel assemblies and the radioactive radioactivity must have decayed to less than prescribed fluids and waste should be removed from the site, limits (Table 1). Adequate radiation monitoring, environmental i surveillance,' and appropriate security procedures ne hazard associated with the retumed facility is should be established under a possession-only license evaluated by considering the amount and type of remaining to ensure that the health and safety of the public is not l contammation, the degree of confinement of the remauung endangered.
radioactive matenals, the physical security provided by the confinement, the susceptibility to release of radiation as a b. In-Place Entombment. In-place entombment j result of natural phenomena, and the duration of required consists of sealing all the remainmg highly radioactive l
surveillance. or contammated components (e.g., the pressure vessel and reactor internals) within a structure integral with C. REGULATORY POSITION the biological shield after having all fuel assemblies, radioactive fluids and wastes, and certain selected
- 1. APPLICATION FOR A LICENSE TO POSSESS components shipped offsite. He structure should BUT NOT OPERATE (POSSESSION-ONLY provide integrity over the period of time in which LICENSE) significant quantities (greater than Table I levels) of radioactivity remam with the matenal in the A request to amend an operating license to a entombment. An appropriate and continuing possession <mly license should be made to the Director of surveillance program should be established under a Licensing, U.S. Atomic Energy Commission, Washington, possession-only license.
D.C. 20545. He request should include the following information: c. Removal of Radioactive. Components and Dismantling. All fuel asaemblies, radioactive fluids
- a. A description of the current status of the facility, and waste, and other matenals having activities above accepted unrestricted activity levels (Table 1) should be
- b. A description of measures that will be taken to removed from the site 'he facility owner may then prevent criticality or reactivity changes and to muumtze have unrestricted uw the site with no requirement releases of radioactivity from the facility, for a license. If the racility owner so desires, the Note: Section elecnonically reproduced from photocopy. C-2
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f :=nninder of the reacsor facility may be dismantled and bemers in the facility. Sampimg should be done along the Q{' f'g '
w 4 all vesuges removed and disposed of.1 i most probable path by which radioactive material sudi as
+ that stored in the inner containment regions.could be2 l d. Conversion to a New Nuclear System or a FeasEl transported to"the outeriregions of'the facility and 2
, ; Fuel System.L *Ihis alternative, which applies only to ' ultimately to the environs.
_7 1inclear power plants,; utilizes the existmg turbme
>y' , system with a new steam supply system. The original ' d.~ An environmental radiation survey should be -
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nuclear steam supply system should be separated from ' . performed at- least' nemiannually' to verify; that no the electric . generating system and disposed,of in _ sph' -d amounts of radiarian have been released to the .
accordance with one of the previous three retirement envuonment from the facility.' - Samples such as soil,'
alternatives.- vegettuon, and water should be taken at locar= for'
' which statistical data has been established durmg reactor -
3[SURVFRI.ANCE AND SECURITY FOR THE o;mations.
Of REI1REMENT ALTERNA11VES WHOSE HNAL STATUS REQUIRES A POSSESSION 4NLY e. A site representative should be designated to be -
. LICENSE responsible for controlling authorized access into and movement within the facility.'
L A facility which has been licensed 'under a
, possession-only license may contam a significant amount f. M Mve procedures should be established for .
of radioactivity in the form of activated and contammated the w rd, and reporting of abnormal ocxurrences 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 esda,44. radiaten or ennenminarmn levels in the facility or the
- a. Physical security to prevent inadvenent exposure of offsite environment, imewd should be provided by multiqle locked bamers.
'Ihe presence of these barriers should make it extremely l g. "Ihe following repons should be made:
difficult for an unauthorized person to gain access to areas where rachation or contammanon levels exceed those (1) An annual report to the Duector of I 1-ing, specified in Regulatory Position C.4. To prevent U.S. Atomic Energy Cornmianian, Washington, D.C.
inadvertent exposure, radiation areas above 5 mR/hr, such 20545, describing the results of the envuonmental and-as near the activated primary system of a power plant, facility radiation surveys, the status of the facility, and an should be appropriately marked and should not be evaluanon of the performance of security and surymilance accessible except by cutting of welded closures or the measures.
disassembly and removal of substantial structures and/or shielding material. Means su:h as a remote-readout (2) An abnonnal occunence report to the Regulatory intrusion alarm system should be provided to indicate to Operanons Regional Office by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> designated pmannel when a physical barrier is paw M. of discovery of an abnormal occunence. 'Ibe abnormal Security personnel that provide access control to the occunence will also be reported in the annual report facility may be used instead of the physical bamers and described in the precmchng item.
the intrusion alarm systems,
- h. Records or logs relative to the following items '
- b. The physical bamers to unauthonzed entrance into should be kept and retained until the license is terminated, the facility, e.g., fences, buildings, wekled doors, and after which they must be stored with other plant recxxds, access opemngs, should be inspected at least quarterly to assure that these bamers have not detenorated and thm (1) Emb a surveys, locks and lockmg apparatus are intact.
(2) Facility radiation surveys,
- c. A facility radizion survey should be performed at I, (3) Inspections of the physical barriers, and least quarterly to verify that im radioactive matenal is escaping or being h-ymied through the coprammt (4) Abnormal occunences
, Note: Section electronically reproduced from photocopy. C-3
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- 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 desired to terminate a license and to elimmate 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 decontammated to prevent risk to the public the public.
health and safety. After the decontammation is satisfactorily accomplished and the site inspected by the e. Prior to release of the prenuses for unrestricted use, Comnussion, the Commission may authorize the license to the licensee should make a comprehensive radiation survey be termmated and the facility abandoned or released for~ establishing that contammation is within the limits specified unrestricted use. The licensee should perfonn the in Table 1. A survey report should be filed with the i decontammation using the following guidelines: Director of Licensing, U.S. Atomic Energy Comnussion, I
Washington, D.C. 20545, with a copy to the Director of l a. The licensee should make a reasonable effort to the Regulatory Operations regional Office having l eliminate residual contamination. jurisdiction. He report should be filed at least 30 days j prior to the planned date of abandonment. The survey
- b. No covering should be applied to radioactive report should:
surfaces of equipment of structures by paint, plating, or other covering material until it is known that contammation (1) Identify the premies; levels (determmed by a survey and documented) are below the limits specified in Table 1. In addition, a reasonable (2) Show that reasonable effort has been made to l
effort should be made (and documented) to further reduce residual contammation to as low as practicable mminuze contammation prior to any such covering. levels;
- c. The 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 measurements at all traps and other appropriate access points, provided contammation at these locations is likely (4) State the finding of the survey in units specified in to be representative of contammation on the interior of the Table 1.
pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated After review of the report, the Commission rnay but are of such size, construction, or location as to make mspect the facilities to confirm the survey prior to granting the surface inaccessib!c for purposes of measurement approval for abnndmment, should be assumed to be contammated in excess of the permissible radiation limits. 5. REACTOR RETIREMENT PROCEDURES
- d. Upon request, the Comnussion may authorize a As indicated in Regulatory Position C.2, several licensee to relinquish possession or control of premises, alternatives are acceptable for reactor facility retirement.
equipment, or scrap having surfaces contaminated in if minor disassembly or "mothballing" is planned, this excess of the limits specified. His may include, but is not could be done by the existing operating and maintenance limited to, special circumstances such as the transfer of procedures under the license in effect. Any planned premises to another licensed organization that will continue actions involving an unreviewed safety question or a to work with radioactive materials. Requests for such change in the technical specifications should be reviewed authorization should provide: and approved in accordance with the requirenrnts of 10 CFR I 50.59.
(1) Detailed, specific information describing the premises, equipment, scrap, and radioactive m- hts If major structural changes to radioactive components and the nature, extent, and degree of residual surface of the facility are planned, such as removal of the pressure contamtnation. vessel or major components of the primary system, a ,
dismantlement plan including the information requued by {
Note: Section electronicaHy reproduced from photocopy. C-4 l
i 50.82 should be submitted to the Comnussion.' A T
dismantlement plan should be submitted for all the alternatives of Regulatory Position C.2 except mothballing.
However, minor disassembly activities may still be
- performed in the absence of such a plan, provided they are permitted by existing operating and maintenance i procedures. A dismantlement plan should include the
- following:
- a. A description of the ultimate status of the facility L
- b. A description of the dismantling activities and the
[
ll precautions to be taken.
- c. A safety analysis of the dismantling activities including any effluents which may be released.
- d. A safety analysis of the facility in its ultimate
! status.
Upon satisfactory review and approval of the
- dismantling plan, a dismantling order is issued by the
( Commission in acconlance with I 50.82. When
! dismantling is completed and the Commission has been notified by letter, the appropriate Regulatory Operations Regional Office inspects the facility and verifies -
j completion in accordance with the dismantlement plan. If residual radiation levels do not exceed the values in Table f
[-
1, the Commission may terminate the license.' If j possessionenly license under which the dismantling activities have been conducted or, as an alternative, may make application to the State (if an Agreement State) for
- a byproduct materials license.
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-TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVEL 3 ' :
l Nuclide* Average *# Maximunfd Removablebd U-nat, U-235, U-238, and ,
associated decay pmducts 5,000 dpm a/100 cm 15,000 dpm a/100 cuf 1,000 dpm a/100 cm' .!
Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I 129 100 dpm/100 cul 300 dpm/100 caf 20 dpm/100 cm'
'Ih-nat, Th-232, Sr-90, Ra-223, j Ra-224, U-232, I-126, I-131, I-133 1,000 dpm/100 enf 3,000 dpm/100 cnf 200 dpm/100 cm'. ,
i l Beta-gamma emitters (nuclides with decay modes other than alpha emission or :
spontaneous fission) except Sr-90 and others noted above. 5.000 dpm Sy/100 enf 15400 dpm Sy/100 cnf 1,000 dpm Sy/100 cnf -
'Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta- -l gamma-emitting nuclides should apply independently. l l "As used in this table, dpm (disintegrations per minute) m:ans the rate of emission by radiaactive material as determmed by correcting the counts per minute observed by an appmpriate detector for background, efficiency, and geometric factors associated - ;
with the instrumentation. !
' Measurements of average contarnmant should not be averaged over more than 1 square treter. For objects ofless surface area, the average should be derived for each such object.' !
- Ihe maximum contamination level applies to an area of not more than 100 enf. ,
'The amount of removable radioactive material per 100 cm2 of surface area should be detennined by wiping that area with dry filter-or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determmed, the pertinent levels should be reduced proportionally and the entire surface should be wiped.'
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