ML040360630
| ML040360630 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/24/2003 |
| From: | Adams W Oak Ridge Institute for Science & Education |
| To: | John Hickman NRC/NMSS/DWM |
| References | |
| -RFPFR, RFTA 03-026 | |
| Download: ML040360630 (48) | |
Text
1 s O A K R I D G E INSTITUTE F O R S C I E N C E A N D
&&!VED December 24,2003
'04 JRN -2 P I :47 Mr. John Hickman Mail Stop: 7F27 Division of Waste Management U.S. Nuclear Regulatory commission Two White Flint North 11545 Rockville Pike Rockvllle, MD 20852-2738
SUBJECT:
FINAL REPORT- CONFIRMATORY SURVEY OF THE TURBINE BUILDING AND PORTIONS OF' T m SERVICE BUILDING OUTSIDE THE RCA, YANKEE NUCLEAR POWER STATION, R O W , MASSACHUSETTS [DOCKET NO. 50-29; RFTA NO. 03-0261
Dear Mr. Hickman:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed confirmatory survey activities in the Turbine Building and portions of the Service Building outside the RCA at the Yankee Nuclear Power Station (YNPS) Plant in Rowe, Massachusetts. At the request of the NRC site representative, limited radiological surveys of the Front Office Rubble Pile were also performed. Survey activities included document and data reviews; beta and gamma surface scans; and, beta surface activity measurements.
Enclosed are five copies of the subject report with your comments incorporated. If you have any additional questions or comments, please direct them to me at (865) 576-0065 or Timothy J. Vitkus at (865) 576-5073.
Sincerely, d&
Wade C. Adams c.Psg0, Health Physicist/Project Leader Environmental Survey and Site Assessment Program WCA:ar Enclosure cc: T. McLaughlin, NRC/NMSS/TWFN 7F27 , E. Abelquist, ORISE/ESSAP E. Knox-Davin, NRC/NMSS/TWFN 8A23 T. Vitkus, ORISE/ESSAP J. Wray, NRC/Region I File/0885 P. 0. BOX 117, OAK RIDGE, TENNESSEE 37831-01 17 Operated by Oak Ridge Associated Universities for the US. Department of Energy
CONFIRMATORY SURVEY OF THE TURBINE BUILDING AND PORTIONS OF THE SERVICE BUILDING OUTSIDE THE RCA YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS W.C. ADAMS Prepared for the U.S. Nuclear Regulatory Commission Division of Waste Management
ORlSE 03-1605 CONFIRMATORY SURVEY OF THE TURBINE BUILDING AND PORTIONS OF THE SERVICE BUILDING OUTSIDE THE RCA YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS Prepared by W. C. Adams Environmental Survey and Site Assessment Program Radiological Safety, Assessments and Training Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 3783 1-0117 Prepared for the U.S. Nuclear Regulatory Commission Division of Waste Management FINAL REPORT DECEMBER 2003 This report is based on work performed under an Interagency Agreement ( N R C Fin. No. 5-5403) 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-AC05-000R22750 with the U.S. Department of Energy.
YNPS Turbine Building 12-09 Fiiial Reporr projccts\S8~\l~epo~tsV003-
CONFIRMATORY SURVEY OF THE TURBINE BUILDING AND PORTIONS OF THE SERVICE BUILDING OUTSIDE THE RCA YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS Prepared by: ~W. C. Adams,
& SurveyCProject Leader
+ L Date: L/4 /-'O3 Environmental Survey and Site Assessment Program Reviewed by: Date: )Z / h / J m 3 T. J. V i t k u G u h e y Projects Manager Environmental Survey and Site Assessment Program Reviewed by:
I '
R. D. Condra, Laboratory Manager Environmental Survey and Site Assessment Program Reviewed by: - Date: /h ?,/& 3 A. T. Payne, Quality Maniger Environmental Survey and Site Assessment Program Reviewed by: Date:
E. W. Abelquist, P Environmental Su YNPS Turbine 13uildiiig pro~ecrs~S85\Repoi-ts12003-12-09 Final Report
ACKiiOWLEDGMENTS The author would like to acknowledge the significant contributions of the following staff members:
FIELD STAFF T. D. Herrera A. L. Mashbum LABORATORY STAFF E. M. Ball R. D. Condra J. S. Cox W. P. Ivey CLERICAL STAFF D. K. Herrera K. L. Pond A. Ramsey ILLUSTRATORS T. L. Brown T. D. Herrera YNPS Turbine Building pl.ojects\SSS\Repol.tsU003- 11-09 Final lieport
TABLE OF CONTENTS PAGE List of Figures ................................................................................................................................. 11 List of Tables ................................................................................................................................. 111 Abbreviations and Acronyms ........................................................................................................ iv Introduction and Site History ........................................................................................................... I Site Description ................................................................................................................................ 3 Objectives ...................................................................................................................................... ..3 Document Review.......................................................................................................................... ..4 Procedures ........................................................................................................................................ 4 Sample Analysis and Data Interpretation ........................................................................................ 5 Findings and Results ....................................................................................................................... .6 Comparison of Results with Guidelines ......................................................................................... .7 Summary ......................................................................................................................................... .7 I
Figures .............................................................................................................................................. 9 Tables ............................................................................................................................................. 16 References..................................................................................................................................... .25 Appendices :
Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: IE Circular No. 81-07: Control of Radioactively Contaminated Material Y N P S Turbine Building I
LIST OF FIGURES PAGE FIGURE 1: Location of the Yankee Nuclear Power Station-Rowe, Massachusetts ...............10 FIGLIRE 2: Layout of the Surveyed Areas at the Yankee Nuclear Power Station-Rowe, Massachusetts ........................................................................................................ 11 FIGURE 3: Turbine Building, Ground Floor Level-Measurement and Sampling Locations ............................................................................................... 12 FIGURE 4: Turbine Building, Mezzanine Level-Measurement and Sampling Locations ............................................................................................... 13 FIGURE 5 : Turbine Building, Operating Floor Level-Measurement and Sampling Locations ............................................................................................... 14
- FIGURE 6: Service Building-Measurement and Sampling Locations ................................... 15 Y N P S Turbine Uuiidins ..
11
LIST OF TABLES PAGE TABLE 1: Surface Activity Levels-Ground Floor Level, Turbine Building ......................... 17 TABLE 2: Surface PLctivity Levels-Mezzanine Level, Turbine Building ............................. 19 TABLE 3 : Surface Activity Levels-Operating Floor Level, Turbine Building ..................... 21 TABLE 4: Surface Activity Levels-Front Office Rubble Pile, Turbine Building ............... ..23 TABLE 5 : Surface Activity Levels-Service Building ............................................................ 24 W P S Turbine Buildinp ...
111
ABBREVIATIONS AND ACRONYMS P-r beta- gamma Ei instrument efficiency ES surface efficiency total total efficiency AEC Atomic Energy Commission bi number of background counts in the interval BKG background cm centimeter cm' square centimeter CO-60 cobalt-60 CPm counts per minute (3-137 cesium- 137 d' index of sensitivity DOD Department of Defense DOE Department of Energy dpm/l00 cm2 disintegrations per minute per 100 square centimeters EML Environmental Measurements Laboratory EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program ft feet FSS final status survey H-3 tritium ISM integrated safety management IS0 International Standards Organization ITP Intercomparison Testing Program JHA job hazard analysis keV kiloelectron volts LSA liquid scintillation analyzer LTP license termination plan m meter MAPEP Mixed Analyte Performance Evaluation Program MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC minimum detectable concentration MDCR minimum detectable count rate MeV million electron volts min minute mm millimeter MW megawatt NaI sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission NRlP NIST Radiochemistry Intercomparison Program ORISE Oak Ridge Institute for Science and Education YNPS Turbine Btiiiding
ABBREVIATIONS AND ACRONYMS (continued) sec second Tc-99 technetium-99 YAEC Yankee Atomic Electric Company YNPS Yankee Nuclear Power Station I
V
- CONFIRMATORY SURVEY OF THE TURBINE BUILDING
.hYD PORTIONS OF THE SERVICE BUILDING OUTSIDE THE RCA YANKEE NUCLEAR POWER STATION
_- ROWE, MASSACHUSETTS
- INTRODUCTION AND SITE HISTORY The Yankee Atomic Electric Company (YAEC) was incorporated in Massachusetts in 1954.
YAEC was sponsored by ten New England utilities for the purpose of constructing and operating New Englands first nuclear power plant (and the United States third nuclear plant), the Yankee Nuclear Power Station (YNPS). YAEC is the holder of YNPS Facility Operating License DPR-3 issued under the authority of the Atomic Energy Commission (AEC) Docket Number 50-029. The plant achieved initial criticality in 1960 and began commercial operations in 1961. The original thermal power design limit of 485 megawatts (MW) was upgraded to 600 MW in 1963 (YAEC 2003a).
On February 26, 1992, the YAEC Board of Directors decided to cease power operations
- permanently at YNPS. On August 5, 1992 the U.S. Nuclear Regulatory Commission (NRC) amended the Y S Facility Operating License to a possession-only status.
Three decommissioning approaches have been submitted to the NRC. The first approach was a Decommissioning Plan submitted on March 29, 1994, which received final approval in October 1995. In May 1997, Yankee submitted to the N R C for approval a License Termination Plan (LTP) for YNiS, pursuant to 10 CFR 50.82 (a)(9). The initial YNPS LTP employed a survey methodology based upon the Manual for Conducting Radiological Surveys in Support of License Termination, also referred to as the Draft NLXEG/CR-5849 methodology (NRC 1992).
Subsequently the NRC, jointly with the DOD, DOE, and EPA, approved an alternate survey
- methodology documented in MARSSrCvf [Multi-Agency Radiation Survey and Site Investigation Manual (NRC 2000)l. In May 1999, YAEC advised the NRC that it intended to shift from the survey methodology in NVREG/CR-5849 to the MARSSIM methodology, and withdrew its previously submitted LTP application. The current LTP is written to reflect the ML4RSSIh4 methodology. as well as resulatory guidance made available since the previous LTP submittal (YAEC 2003a).
i 2-09 Final lieport projects~~885.ReportsVOC)3-
The turbine system components processed steam, from the steam generators, that rotated the turbine blades and produced electrical power via the motor end of the turbine-the system was not intended to involve radioactive materials. Currently, YAEC is decommissioning the Turbine Building and has submitted radiological survey data to support the release of the shell and supporting structural components of the Turbine Building (YAEC 2003b). YAEC intends to demolish the structure and dispose of the debris. The following information identifies conditions and events where radioactive material was present in the Turbine Building.
A portion of the Turbine Building became contaminated in 1967 while a main coolant pump was being refurbished on the turbine deck; at that time the area was decontaminated. The event was incorporated into plans for decommissioning activities and survey plans developed for this area.
The condensate system contained radioactive materials as a result of primary to secondary system leakage that occurred in the steam generators. Contamination from this leak was identified in the floor drain system and in the soil around and under the floor drains. Additional contaminated concrete surfaces and soil below the concrete floor were identified near turbine support pedestal #4. All of these identified sub-surface locations have undergone a remediation process and have been backfilled to grade. The interior of the structure and slab were surveyed under Draft NUREGICR-5849 criteria after decommissioning activities were complete.
There is also a known plume of tritium (H-3) beneath the building. The general sub-surface conditions are the subject of a continuing investigation.
Current decontamination and decommissioning activities for the Turbine Building are as follows:
a Removal of secondary systems;
. Removal of equipment;
. Removal of sub-floor systems (floor and equipment drains, service water piping);
. Removal of soil from around the sub-floor systems; and Soil excavations backfilled.
Planned decommissioning activities for the Turbine Building include the demolition of the entire structure to elevation 1022' 8" (grade).
'I'YI'S 'l'uhne Id iny 13111
In May 1999, the Environmental Survey and Site Assessment Program (ESSAP)of the Oak Ridge Institute for Science and Education (ORISE)performed decommissioning inspection activities at YNPS which included survey activities of the Turbine Building (ORISE 1999).
The N i C ' s Headquarters and Region I Offices requested that ESSAP perform additional confirmatory surveys of the Turbine Building and limited confirmatory survey activities in the Service Building at the YNPS. During the survey activities, the N R C site representative also requested that ESSAP perform limited radiological survey activities on the Turbine Building Front Office Rubble Pile.
SITE DESCRIPTION The YNPS is located at 49 Yankee Road in Rowe, Massachusetts (Figure 1). The Turbine and Service Buildings are located within the restricted area of the power plant (Figure 2). The Turbine Building, which contained the turbine system, measures 48 m (159 ft) by 23 m (77 ft) high by 27 m (87 ft) wide and consists of three floors. The Mezzanine Level and the turbine deck (Operating Floor Level) have a large area of open space in the center where the turbine was previously located. The Turbine and Service Buildings are constructed of heavy steel framework with a concrete block lower structure and a steel frame and metal panel upper structure (YAEC 2003a). The concrete (and concrete block) surfaces were either found to be free of paint and other surface coatings in some locations, were painted in some areas, or had been scabbled in other locations during remediation. Other surfaces included metal grating used for the Mezzanine Level floor and the stairways, metal structural support beams and some sheetrock used on the walls.
OBJECTIVES The objectives of the Confirmatory survey were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and final status survey (FSS) results and conclusions.
YNPS Turbiiie Buiidiiig 3
DOCUMENT REVIEW ESSAP personnel reviewed the licensee's FSS documentation and survey data for the Turbine Building and the Turbine Building Front Office for adequacy and appropriateness (YAEC 2003b and c). FSS results were not yet available for the Service Building at the time of the ESSAP confirmatory survey activities.
PROCEDURES ESSAP personnel visited the YNPS facility during the period of September 24 to 25, 2003 and performed visual inspections and independent measurements and sampling of portions of the site. Survey activities were conducted in accordance with a site-specific survey plan and the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 2003a, b, and c).
Additional survey activities were performed on various Front Office Building Rubble Pile remains, which included various construction materials such as concrete block, metal siding, sheetrock, wood and metal beams. Survey activities were not performed on the floor surface of the Ground Floor since the planned demolition of the Turbine Building structure will be down to 1 the Ground Floor elevation ( Y A K 2003a).
REFEREXCE SYSTEM Measurements and sampling locations for'the Turbine and Service Buildings were referenced to the existing YAEC-established grid system and on figures prepared by ESSAP (Figures 3 through 6). A figure is not provided for the Turbine Building Front Office Rubble Pile measurement locations.
SURFACE Scslius Surfaces in each survey unit were scanned for total beta radiation using gas propoi-tional detectors and scanned for gamma radiation using YaI scintillatioii detectors. Total beta and gamma radiation scans were perfonned on approximately 25% of the concrete floors and walls.
-1
Particular attention was given to cracks and joints in the concrete surfaces, scabbled surface areas, and other locations where material may have accumulated. All detectors were coupled to ratemeters or ratemeter-scalers with audible indicators.
S u R F , ~ C EACTIVITY MEASUREMENTS The construction material-specific beta background for concrete and metal surfaces for the gas proportional detectors was determined while on site. Direct measurements for total beta activity on Turbine Building surfaces were performed at 152 locations which were identified by surface scans or corresponded to licensee measurement locations (Figures 3 through 5 ) . Direct measurements for total beta activity on the Service Building (Figure 6) and the Front Office Rubble Pile surfaces were performed at 23 and 20 locations, respectively. Measurements were performed using gas proportional detectors coupled to portable ratemeter-scalers. Smears, for determining removable gross alpha and gross beta activity, were collected at each direct measurement location. A second wet smear, for determining removable H-3 activity, was collected from ten of the direct measurement locations on each floor of the Turbine Building-H-3 smears were not collected from the Service Building or the Front Office Rubble Pile.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Samples were analyzed in accordance with the ESSAP Laboratory Procedures Manual (ORISE 2003d). Smears were analyzed for gross alpha and gross beta activity using a low-background gas proportional counter and for H-3 using a liquid sciiitillation analyzer (LSA). Smear data and direct measurements for surface activity were converted to units of disintegrations per minute per 100 square centimeters (dpnd100 cm').
Survey data were then compared with the site-specific guideline levels for the Turbine Building which are from the NRC Circular 8 1-07 (NRC 1981). The primary contaminants of conceiii for the Turbine Building (and other areas) were beta-gamma emitters-fissiou and activation products-resdting from reactor operation. Appendices A and B provide additional infbiinatioii
- concerning major instrumentation, sampling equipment, and analytical procedures discussed in this report, including minimum detectable concentrations for field and laboratory instruments.
FINDINGS AND RESULTS DOCUMENT REVIEW Inforrktion provided in YAECs FSS documentation was evaluated to assure that areas identified as exceeding guidelines had undergone decontamination and that residual activity levels satisfied the established guidelines.
SURFACE SCANS Beta surface scans of the floors and walls of the Turbine and Service Buildings and the Front Office Rubble Pile did not identify any areas of elevated radiation. Gamma scans did not identify any indications of volumetric or subsurface contamination (Le., gamma radiation levels were consistently within backgound ranges) except for portions of the northern walls which are in proximity to the reactor containment vessel.
SURFACE ACTIVITY LEVELS Turbine Building Results of total and removable surface activity for the Turbine Building are provided in Tables 1 through 3. Total beta surface activity for the Ground Floor, Mezzanine, and Operating Floor levels of the Turbine Building ranged from -610 to 850 dpm/l00 cm2, -580 to 970 dpm/100 cm.
and -330 to 1,200 dpm/lOO cm2, respectively. Removable surface activity for all the levels ranged from 0 to 5 dpm/l00 cin for gross alpha, -6 to 8 d p d l 0 0 cm for gross beta, and - 16 to 52 dpm/l00 cm for H-3.
YUPS Tui-bine Building 6
Front Office Rubble Pile Results of total and removable surface activity for the Front Office Rubble Pile are provided in Table 4. Total beta surface activity ranged from 130 to 1,300 dpmil00 cm2. Removable surface activity ranged from 0 to 1 d p d 1 0 0 cm' for gross alpha and -5 to 6 dpm/100 cm2 for gross beta.
Service Building Results of total and removable surface activity for the Service Building are provided in Table 5 .
Total beta surface activity ranged from -3 10 to 1,300 dpm/100 cm'. Removable surface activity ranged from 0 to 3 dpm/l00 cm2 for gross alpha and -4 to 5 dpmi100 cm' for gross beta.
COPIPARISON OF RESULTS WITH GUIDELINES The primary contaminants of concern for the Y X T S are beta-gamma emitters-fission and activation products-resulting from reactor operation. Cesium- 137 (Cs- 137) and cobalt-60 (CO-60)were identified during characterization as the predominant radionuclides present on surfaces. The minimal detection criteria from NRC Circular 81-07 (NRC 198 1) are as follows:
Total Activity 5,000 P-y d p d 1 0 0 cm2, maximum in a 100 cm' area Removable Activitv 1,000 P-y d p d 1 0 0 cm2 No direct measurements performed in the Turbine and Service Buildings or the Front Office Rubble Pile exceeded the Suidelines.
SUMMARY
.. At the request of the Nuclear Regulatory Commission's Headquarters and Region I Offices, the Environmental Survey and Site Assessment Program of the Oak Ridge Institute for Science and Education conducted a confirmatory survey of the Turbine Building and the Service Building and a limited radiological survey of the Front Office Rubble Pile at the Yankee Nuciear Power
Station in Rowe, Massachusetts. Confirmatory activities performed during the period September 24 through 25, 2003 included reviews of final status survey data, surface scans and direct surface activity measurements. Overall, the results of the survey activities confirmed that the radiological conditions of the Turbine Building and the Service Building met the approved site-specific criteria for unrestricted use or release. The results of the limited radiological survey of the Front Office Rubble Pile also indicated that this material met the criteria for unrestricted use or release.
YN 1s TU~-b Iiie Bui Id ing 8
FIGURES 885-001 (x)
/ MASSACHUSETTS 4 I\
Yankee Nuclear Power Station N
NOT TO SCALE FIGURE 1: Location of the Yankee Nuclear Power Station - Rowe, Massachusetts projects :SX5\Iieporrs:2003 - i 2 -09 F:nai lieport 10
885-002 (1)
WAFGHOUSE I
h n h T
N I
SURVEYED AREA v
v 2 2 ?c FENCE NOT TO SCALE FIGURE 2 : Layout of the Surveyed Areas at the Yankee Nuclear Power Station - Rowe, Massachusetts YNPS Tiirhine Bunitliiig 11
585-003 (3) iir 50 308 + 49 A A I 43 40 2LE 4 51 I 39 22E L P-318 1 328 I I + I OIL ROOM
@ @ D I 59 I I h 38 I TRENCH I A 36 I 455 57 @ \
34 HEATING AND BOILER RDOM WIIA N
MEASUREMENT/SAMPLING LOCATIONS
- - SINGLE-POINT e FLOOR
- SINGLE-POINT A LOWERWALLS ic SINGLE-POINT UPPER SGRFACES NOT TO SCALE FIGURE 3: Turbine Building, Ground Floor Level - Measurement and Sampling Locations YNI'S Turbine Building 12
885-004 (2) n n N
MEASUREMXNT/SAMPLING LOCATIONS 3 SINGLE-POINT FLOOR i: SINGLE-POINT A LOWER WALLS 3 SINGLE-POINT UPPERSURFACES NOT TO SCALE FIGURE 4: Turbine Building, Mezzanine Level - LMeasurement and Sampling Locations YNPS Turb!iie Building 13
885-005 (1)
MECH EQUIP ROOF N
MEASUREMENT/SAMPLING LOCATIONS
- SINGLE-POINT FLOOR
- SINGLE-POINT A LOWERWALLS 8 SINGLE-POMT UPPERSURFACES NOT TO SCALE FIGURE 5: Turbine Building, Operating Floor Level - Measurement and Sampling Locations 14
885-006 (3) 72A A 87.4 0
I7IA : 0 0
86A 88A 91A 84A I I
92A 0 83A 89A 90A 0
0 r
Y3A I
78A A 76A 0 79A 0
MEASUREMENT/SMLING N LOCATIONS
- SINGLE-POINT FLOOR
- SINGLE-POINT A LOWERWALLS A
NOT TO SCALE
- EQUlPMENT SURFACE FIGURE 6: Service Building - Measurement and Sampling Locations YN PS Titi-bine Bui id ing 15
TABLES TA4BLE1 SURFACE ACTIVITY LEVELS GROUND FLOOR LEVEL TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS 1
1 I
1 Total Beta Removable Activity ( d p d 1 0 0 cm')
j I
Location" Activity
( d p d l 0 0 cm') Alpha ~
Beta I H-3 I
~
SUTB002 2411 1-4 LW 4s I 0 -4 -10 25112A LW 24 0 -1 3 I 26113A 1 LW -210 I 0 -4 -10
.- I 271 14A LW -63 I 1 1 22 i 1 28/15A LW us 87 0 -3 3 I 32B -330 0 -2 -- C I I
I 33B us s50 0 3 I -- I LW 320 0 1 21 i 30117A LW I -79 3 3 -1 31118A LW -410 0 1 15 LW -8 0 -1 13 i SUTB006 1 35 us -370 0 -6 --
I --
~
36 LW -3 80 0 2 I I i 37 I LW -130 1 -6 I --
I I
I SUTB007
' I
~
I 33120A LW -600 0 2 14 I 34 LW -450 5 j -3 I _- I 5s LW 480 0 3 j -- 1 SU TB008 I 55 I LW -330 0 1 -I _-
I 56 ! LW -170 I 0 -1 --
1 57 i LW -71 I 0 1 _-
~
SUTB009 I
49 I LW 40 i 0 -2 I
50 i LW -5 6 1 -4 ~
51 I LW I -320 -0 3
I I
52 ~ LW I I 710 0 I -4 I 53 I LW I -610 1 I -4 I _-
~
39B us I 16 1 0 I I 4 _-
I I
3 OB US -30 I 0 I I
3 I _-
17
TABLE 1 (continued)
SURFACE ACTIVITY LEVELS GROUND FLOOR LEVEL TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS 1 Total Beta Removable Activity (dpm/100 cm) 1 Location Surfaceb Activity I
( d p d 1 0 0 cm) Alpha Beta H-3 J
59 LW 16 0 -2 --
60 LW -170 0 1 i --
44 LW ! 24 0 1 1 --
45 LW 740 0 -3 --
46 LW 130 1 1 -_
47 LW -120 1 1 --
43 LW -370 0 -1 --
25B us -5 10 1 -1 --
2 6B us 400 0 3 _-
27B us 110 0 2 --
28B I TJS I -250 I 3 I -1 I
I --
31B us -140 1 -1 --
61 LW -9 5 0 -3 I --
38 LW -280 0 3 I _-
39 LW -320 1 -2 I --
40 LW -250 1 1 ! --
41 LW -310 0 2 __
42 LW 390 0 1 i I --
_- 43 LW -300 0 -2 I __
2 1B US ! -100 I 0 -1 I I
22B US I I 370 I 0 -3 I -_
I 23B US I 56 0 -3 I
I _-
Refer to Figure 3 .
LW = lower wall and US = upper surface.
Measurement not performed.
18
TABLE 2 SURFACE ACTIVITY LEVELS MEZZANINE LEVEL TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, R/IASSACHUSETTS Total Beta Removable Activity (dpmA00 cm') ~
Locationa Surfaceb Activity I i I
( d p d 1 0 0 cm') Alpha Beta H-3 I I SUTB006 65A I I US -430 0 -3 --c SU TB017 I
~ 90121-4 91122-4
~
1 LW F 600
-340 1
1
-5
-3 17 15 92123A 1 LW 63 0 3 5 I
~
93l24A 94/25A 95126A I
1 . US LW F
290
-370 250 0
0 0
2 3
-1 0
15 0
1 96127A 1
1 97l28A 98129A
,1I LW F
us 63 490 560 0
0 1 3 1
1 I 6
3 0
j I
- 1. 99130A 100 1 us LW 140
-270 0
0 I -2
-1 I
I -5 i
47A LW 87 0 -3 ~
1
-I 48A I LW -150 i 0 8 --
49A I
i LW -24 I 1 3 I --
I I
50A 5 1A LW F
! -100 540 0
1
-1 3
/I 52A I F 440 0 -1 -- I i SUTB018 3 1A F -7 1 0 3 --
I, SU TB020 66A F I 570 0 -
-3 ! --
67A LW 180 I 0 -1 1 I I
68A LW 1 520 ~
1 I -3 -- I I
69A F I 700 1 0 I -4 I -- i 32A ' LW -580 ~ 1 1 5
I F ,
I 870 I I 0 , I 7 --
34A F I 750 1 I -
3 --
19
TABLE 2 (continued)
SURFACE ACTIVITY LEVELS MEZZANINE LEVEL TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS i Location I
~ Surface Total Beta Activity Removable Activity (dpm/100 cm)
Alpha Beta I H-3 I
i (dptd100 cm) ~ I i SUTB022 36A LW -520 0 -5 I --
37A I us 79 1 -3 i --
38A 1 F 410 1 3 I --
39A 1 LW -140 0 2 i --
I 40A F 220 0 -4 1 1 41A LW 790 1 I -1 --
j 4 2 ~ F 280 0 i 1 I
I --
I 43 A LW 420 1 4 I i --
I I 44A LW 110 1 -1 I --
1 45A LkV I
i -3 10 1 3 I --
46A F I 400 0 1 --
53A F I 970 1 -7 I
54A LW I -290 0 -4 --
x 55A LW -400 5 -1 --
I 1 56A LW -260 0 1 --
57A LW II 87 1 -3 --
1 58A 59A 60A LW US LW
-180 210 140 1
3 1
-7 2
-2 61A US 180 0 -2 --
62A 1 LW -150 0 2 --
I I I
j 63A I F 43 0 0 -2 I --
64A i LW -56 0 I 1 I
I --
Refer [o Figure -1.
F = tloor, L W = lower wall and US = upper surface.
Ivleasurement no[ performed.
YNPS rtirbirie Buiitiiiig 20
L TABLE 3 SURFACE ACTIVITY LEVELS OPERATING FLOOR LEVEL TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS
~
717A F 640 I 0 I -3 I -6 j I
818A LW -48 i 0 ~
-2 I 5 I 9l9A F I 590 I 1 1 1 I
-10 10110A i LW7 I I -150 ~ 0 I 5 52 1
I I 11 ,I LW / 220 I 0 I I 7 --
12 I LW 370 I
I 3 I -4 __
~
1 -
YNI'S Tiirbinc Buiidiiig 21
TABLE 3 (continued)
SURFACE ACTIVITY LEVELS OPERATING FLOOR LEVEL TURBINE BUILDING YAlUKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS I ,
I Total Beta Removable Activity (dpmA00 cm') I I
i Locationa su rface Activity I I , ( d p d l 0 0 cm') Alpha Beta H-3
- 1
~
TB030 (continued)
~
I 13 F I 480 0 1 I 14 LW I 43 0 1 5 I
I __ i 64 F 710 1 -2 _- I i TB031 15 LW 130 0 3 I --
16 LW -32 0 1 --
~
17 LW 140 0 7 _-
18 LW 680 5 1 --
19 LW -8 0 2 ! --
20 LW -330 0 I -1 I _-
21 LW -250 0 ! 3 __
73 F 360 0 -3 I -_
23 LW -63 I 0 -1 --
62 F 390 0 -1 --
63 F 430 0 -1 --
75 LW -8 3 3 -- j 72 LW 530 0 2 --
I 73 LW 290 0 -1 -- i 74 F 560 0 -3 9
I --
76 F 520 3 4 I -- I I
1 TB035 68 LW 290 0 1 1 __ I I
i 69 LW j 830 1 5 I
-- I I
70 1I F 500 5 6 i __ 1 c- 71 ! F 760 1 -1 I
- 2 4B us I1 130 1 -1 I
"Refer to Figure 5 .
'F = floor, LW = lower wall and US = upper surface.
C>'leasurenientnor performed.
YUI'S Tui-bine Btiiitling 23
TABLE 4 SURFACE ACTIVITY LEVELS FRONT OFFICE RUBBLE PILE TURBINE BUILDING YANKEE NUCLEAR POWER STATION ROWE, NlASSACHUSETTS I
I Total Beta ' Removable Activity ( d p d l 0 0 cm')
~
Location" Surfaceb Activity
( d p d 1 0 0 cm') Alpha I Beta iI I I I
1B Concrete 440 0 -2 j 2B Concrete 690 I 1 i 6 I
i 3B Metal 880 1 0 i 1 4B Metal 510 0 -4
.- 5B Concrete 290 0 -2 6B Concrete 1,100 0 -1 7B Concrete 420 0 -5
~
8B Concrete 130 0 -4 2 9B Sheetrock 750 0 3 1OB Wood 1,000 0 -3 11B Concrete 680 1 -3 1 12B 13B 14B Concrete Metal Metal 140 65 0 710 0
0 1
-3
-2 2 I I
I 15B Metal 780 0 1 I
1 16B 17B Metal Metal 920 1,300 1
0
-2 3
1I 18B 19B 20B 1 Metal Metal Metal 1,100 280 440 I
~
0 1
1
-1
-I
-3 I
1
~
"The Front Office portion of the Turbine Building was dismantled and placed in several rubble piles. a figure was not piovided.
'Construction material surface type.
YYPS Tui-bine Building 23
TABLE 5 SURFACE ACTIVITY LEVELS SERVICE BUILDING YAXKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS Location" Surfaceb Total Beta Activity I Removable Activity ( d p d 1 0 0 cm')
(dpm/100 cm') Alpha II Beta 70A F 370 ! 0 -3 71 A i LW 71 1 i 1 iI 72A 1 F 890 1 j 5
.1 73 A F 920 0 I 5 i 7 4 ~ I LW -140 0 I 2 I 75 A F 1,100 0 II -1 I
~
76 A LW -160 1 3 1 77A F 980 0 1 78A F 1,000 0 1 i
~
I I 79 A LW 260 0 2 80A F 790 0 -3 1 81A F 1,300 0 2 j 8 2 ~ LW -260 0 -2 j 83 A E 850 1 -1
~
I 84 A E 560 1 -1 I
85 A E I 870 0 I -1 86 A E 280 0 I 1 87 A F 760 0 1 1 88A I E 620 3 I 3 89A 1 F 540 I 0 i I
1 90 A E 870 0 -1 I 800 -
~
I 91 A 92A 93 A E
LW LW
-310
-79 I 0
0 0
-7 3
-3
'Refer to Figure 6 .
'F = floor, LLV = lower wall and E = equipment sur-face YUPS Tiirbiiie l3uiiciing 24
_-- REFERElliCES
_- Oak Ridge Institute for Science and Education (ORISE). Final Report-Decommissioning Inspection Activities Performed During the Period May 17 to 20?1999 at the Yankee Nuclear Power Station, Rowe, Massachusetts (Docket No. 50-29, RFTA No. 98-09). Oak Ridge,
__ Tennessee; July 14, 1999.
Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for the Turbine
_. Building and Portions of the Service Building Outside the RCA, Yankee Kuclear Power Station, Rowe, Massachusetts [Docket No. 50-29; RFTA No. 03-0261.Oak Ridge, Tennessee; September 23, 200321.
1 Oak Ridge Institute for Science and Education. Survey Procedures Manual for the Environmental Survey and Site Assessment Program. Oak Ridge, Tennessee; February 2003b Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Environmental Survey and Site Assessment Program. Oak Ridge, Tennessee; April 2 0 0 3 ~ .
Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Environmental Survey and Site Assessment Program. Oak Ridge, Tennessee; February 2003d.
U S . Nuclear Regulatory Commission (NRC). IE Circular No. 8 1-07: Control of Radioactively Contaminated Material. May 14, 198 1.
U.S. Nuclear Regulatory Commission. Draft-Manual for Conducting Radiological Surveys in Support of License Termination. MJREGKR-5849; Washington, DC; June 1992.
U.S. Nuclear Regulatory Commission. iMulti-Agency Radiation Survey and Site Investigation Manual (MARSSLM). NUREG-1575; Revision 1. Washington, DC; August 2000.
~-
Yankee Atomic Electric Company (YAEC). Draft - Yankee License Termination Plan, Rowe.
Massachusetts; September 2003a.
Yankee Atomic Electric Company. Radiological Release Data Package for the Turbine Building and the Service Building Area. Rowe, Massachusetts. September 200%.
Yankee Atomic Electric Company. Internal Communication, RE: Review of Turbine Building Front Office Pre-Demolition Survey. Rowe, Massachusetts. September 10, 2 0 0 3 ~ .
YUI'S Turbine Building 25
APPENDIX A MAJOR INSTRUMENTATION I
YNI'S Tui-biiie Building
APPENDIX A MAJOR INSTRUNIENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.
SCANXINC INSTRUMENTIDETECTOR COMBINATIONS Ludlum Floor Monitor lModel 23 9- 1 combined with Ludlum Ratemeter-Scaler Model 222 1 coupled to Ludlum Gas Proportional Detector Model 43-37, Physical Area: 550 cm' (Ludlum Measurements, Inc., Sweetwater, TX)
Ludlum Ratemeter-Scaler Model 222 1 coupled to Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm' (Ludlum Measurements, Inc., Sweetwater, TX)
Gamma Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NM) coupled to Victoreen NaI Scintillation Detector Model 489-55, Crystal: 3.2 cm x 3.8 cm (Victoreen, Cleveland, OH)
DIRECT MEASUREMENT INSTR~MENTIDETECTOR COMBINATIONS Ludlum Ratemeter-Scaler Model 222 1 coupled to Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 crn' (Ludlum Measurements, Inc., Sweetwater, TX)
A- I
LABORATORY ANALYTICAL INSTRUMENTATION Low Background Gas Proportional Counter Model LB-5 100-W (Tennelec!Canberra, Meriden, CT)
Tn-Carb Liquid Scintillation Analyzer Model 3 100 (Pacltard Instrument Co., Meriden, CT)
'4-2
APPENDIX B SURVEY AND ANALYTICAL PROCEDURES YNPS Turbine Buiiding
APPENDIX B SURVEY AND ANALYTICAL PROCEDURES PROJECT HEALTH AND SAFETY The proposed survey and sampling procedures were evaluated to ensure that any hazards inherent to the procedures themselves were addressed in current job hazard analyses (JHAs). All survey and laboratory activities were conducted in accordance with ORISE health and safety and radiation protection procedures.
A walkdown of the survey areas was performed in order to evaluate and identify potential health and safety issues. Falls from the stairs, floor openings, manlifts and ladders were of the greatest concern. YAEC provided general site-specific safety awareness and manlift training. Survey work was performed per the ORISE generic health and safety plans, a site-specific integrated safety management (ISM) pre-job hazard checklist, and the safety procedures discussed during the training.
CALIBUTION AND QUALITY &SLRAYCE Calibration of all field and laboratory instrumentation was based on standards/sources, traceable to NIST,when such standards/sources were available. In cases where they were not available, standards of an industry-recognized organization were used.
Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program:
Survey Procedures Manual. (February 2003)
Laboratory Procedures Manual, (February 3003)
-- Quality Assurance Manual, (April 2003)
The procedures contained in these inaiiuals were developed to meet the requirements of Department of Energy (DOE)Order 114.1'~ and the L.S. Nuclear ReguIatory Commission YNPS 'fiirbine Building B-1
Quality Asszircirzce Manual f o r the Office of Nuclear Material Safety and Safegunrds and contain measures to assess processes during their performance.
Quality control procedures include:
Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
Participation in MAPEP, hXP, ITP, and EML Laboratory Quality Assurance Programs.
Training and certification of all individuals perfoiining procedures.
Periodic internal and external audits.
Detectors used for assessing surface activity were calibrated in accordance with ISO-7503 '
recommendations. The total efficiency (EtOt,l)was determined for each instniment/detector combination and consisted of the product of the 2n instrument efficiency (EJ and surface efficiency (Q: i t o r a l = E, x E~
Tc-99 was selected as the calibration source (maximum beta energy of 292 keV) as it provides a conservative representation of the radionuclide mixture. ISO-7503 recommends an E~ of 0.25 for beta emitters with a maximum enersy of less than 0.4 MeV (400 keV) and an E, of 0.5 for maximum beta energies greater than 0.4 MeV. Since the maximum beta energy for the chosen YNPS calibration source was less than 0.4 MeV, an E~ of 0.25 was used to calculate 1 ~ ~ ~ ~ 1 .
Surface Scans Hand-held detectors were placed on contact with the calibration sources. A postulated hot-spot size of 100 cm2 was assumed n priori for determining scanning instrument efficiencies. The scanning E, value was 0.34 for the hand-held gas proportional detectors; with the scanning E ~ ~ ~ ~ I calculated was 0.08, Calibration source emission rates were not collected for geometry when sources larger than the detectors were used.
Surface Activitv Measurements The static El values for the single gas proportional detector used for the confirmatory survey surface activity measurements was 0.40; the static Etot,l was calculated to be 0.10. The calibration source emission rates were corrected to the physical area of the detectors when the source area exceeded the detector area.
SURVEY PROCEDURES Surface Scans Surface scans were performed by passing the detectors slowly over the surface; the distance between the detector and the surface was maintained at a minimum-nominally about 1 cm. A NaI scintillation detector was used to scan for elevated gamma radiation. Floor and wall surfaces and indentations (scabbled areas) were scanned using small area (126 cm2) hand-held detectors.
Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument.
Scan minimum detectable concentrations (MDCs) were estimated using the calculational approach described in hTUREG-1507'. The scan MDC is a hnction of many variables, including the background level. The beta activity background count rates for the gas proportional detectors averaged 325 cpm for concrete and 180 cpm for metal (and other miscellaneous surfaces such as wood or sheetrock). Additional parameters selected for the calculation of scan MDC included a two-second observation interval, a specified level of performance at the first scanning stage of 95% true positive rate and 25% false positive rate, which yields a d' value of 3.32 (NL-REG-1507, Table 6.1), and a surveyor efficiency of 0.5. To illustrate an example for the hand-held gas proportional detectors, the minimum detectable count rate (WIDCR) and scan MDC can be calculated as follows for concrete surfaces:
'NUREG- 1507. biiiiiiiiuin Detectable Coiicrniratioiis With Typical Radiation Surve!~ 11istriiiiicii1sfor \'xiutis Ci~tiianiiiiaiiisi i i d I;ieId Coiiditioiis. C.S. Yuc!eai- Regularoi-y Commission. Wasliingio~i,DC.June 1998.
YNPS Tiirbiiie Building B-3
b, = (325 cpm) (2 sec) (1 mid60 sec) = 10.8 counts MDCR = (2.32) (1 0.8counts) [(60 sec/min) / (2 sec)] = 229 counts MDCR,,,,.,,,,,. = 229
/ (0.5) = 324 cpm The scan MDC is calculated using the scanning EtOtalof 0.08:
The scan MDC for the gas proportional detectors used was approximately 4,000 dpm/lOO cm for concrete surfaces; for other surfaces, the scan MDC was approximately 3,000 dpm/l00 cm.
Specific scan MDCs for the NaI scintillation detector for Cs-137 and CO-60 in concrete were not determined as the instrument was used solely as a qualitative means to identify elevated gamma radiation for possible concrete sampling.
Surface Activitv Measurements Measurements of total beta surface activity levels were performed using a gas proportional detector with portable ratemeter-scalers. Count rates (cpm), which were integrated over one minute with the detector held in a static position, were converted to activity levels (dpm/l00 cm) by dividing the net count rate by the total static efficiency ( E ~ X E ~and
) correcting for the physical area of the detector.
Because different building materials (poured concrete, brick, wood, steel, etc.) may have different background levels, average background count rates were determined for each material encountered in the surveyed area at a location of similar construction and having no known radiological history. The beta activity background count rates for the gas proportional detectors averaged 325 cpm for concrete and 1SO cpm for metal (and other miscellaneous surfaces such as wood or sheetrock). The static beta MDCs-calculated using the average construction material background count rates for concrete and metal-for the single gas proportional detector (calibrated to Tc-99) used for direct measurements were 690 and 520 dpinil00 cm2. respectively.
The physical surface area assessed by the gas proportional detector used was 136 cm.
YNPS Turbine Building B-4
Removable Activitv Measurements Removable g o s s alpha and gross beta activity levels were determined using numbered filter paper disks, 47 mm in diameter. Moderate pressure was applied to the smear and approximately 100 cm2 of the surface was wiped. Smears were placed in labeled envelopes with the location and other pertinent information recorded.
For H-3 detemiinations, a second smear was moistened with deionized water and an adjacent 100 cm2 was wiped. The smear was then sealed in a labeled liquid scintillation vial with the location and pertinent information recorded.
RADlOLOClCAL LANALYSIS Gross AlphdBeta Smears were counted for two minutes on a low-background gas proportional system for gross alpha and beta activity. The MDCs of the procedure were 8 dpm/lOO cm2 and 15 d p d l 0 0 cm2 for gross alpha and gross beta, respectively.
Liquid Scintillation Smears were counted in a liquid scintillation analyzer for low-energy beta activity to determine H-3 activity with the typical MDC for the procedure being 22 d p d 1 0 0 cni'.
DETECTION LIMITS Detection limits, referred to as IMDCs, were based on 3 plus 4.65 times the standard deviation of the background count [3 i (4.65JBKG)I. Because of variations in background levels, measurement efficiencies, and contributions froin other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
B-5
APPENDIX C IE CIRCULAR NO. 81-07: CONTROL OF RkDIOACTIVELY CONTAMINATED NIA4TEFUAL YNI'S Tui.biiie Buiiding
UWITED STATES NLCLEAR REGULATORY COM,MISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 May 14,1981 IE Circular No. 8 1-07: CONTROL OF RADIOACTIVELY CONTAMlXATED MATERIAL Description of Circumstances:
Information Notice No. 80-22 described events at nuclear power reactor facilities regarding the release of radioactive contamination to unrestricted areas by trash disposal and sale of scrap material. These releases to unrestricted areas were caused in each case by a breakdown of the contamination control program including inadequate survey techniques, untrained personnel performing surveys, and inappropriate material release limits.
The problems that were described in IE Information Notice No. 80-22 can be corrected by implementing an effective contamination control program through appropriate administrative controls and survey techniques. However, the recurring problems associated with minute levels of contamination have indicated that specific guidance is needed by NRC nuclear power reactor licensees for evaluating potential radioactive contamination and determining appropriate methods of control. This circular provides guidance on the control of radioactive contamination.
Because of the limitations of the technical analysis supporting this guidance, this circular is applicable only to nuclear power reactor facilities.
Discussion:
During routine operations, items (e.g., tools and equipment) and materials (e.g., scrap material, paper products, and trash) have the potential of becoming slightly contaminated. Analytical capabilities are available to distinguish very low levels of radioactive contamination from the natural background levels of radioactivity. However, these capabilities are often very elaborate, costly, and time consuming making their use impractical (and unnecessary) for routine operations. Therefore, guidance is needed to establish operational detection levels below which the probability of any remaining, undetected contamination is negligible and can be disregarded when considering the practicality of detecting and controlling such potential contamination and the associated negligible radiation doses to the public. In other words, guidance is needed which will provide reasonable assurance that contaminated materials are properly controlled and disposed of while at the same time providing a practical method for the uncontrolled release of materials from the restricted area. These levels and detection capabilities must be set considering these factors: 1) the practicality of conducting a contamination survey, 2) the potential of leaving minute levels of contaniination undetected; and, 3) the potential radiation doses to individuals of the public resulting from potential release of any undetected, uncontrolled contamination.
c-I
IEC 8 1-07 May 14, 1981 Page 2 of 3 Studies performed by Sommers have concluded that for discrete particle low-level contamination, about 5000 dpm of beta activity is the minimum level of activity that can be routinely detected under a surface contamination control program using direct survey methods.
The indirect method of contamination monitoring (smear survey) provides a method of evaluating removable (loose, surface) contamination at levels below which can be detected by the direct survey method. For smears of a 100 cm area (a de facto industry standard), the corresponding detection capability with a thin window detector and a fixed sample geometry is on the order of 1000 dpm (i.e., 1000 dpm/l00 cm). Therefore, taking into consideration the practicality of conducting surface contamination surveys; contamination control limits should not be set below 5000 dpm/l00 cm2 total and 1000 dpm/l00 cm2 removable. The ability to detect minute, discrete particle contamination depends on the activity level, background, instrument time constant, and survey scan speed. A copy of Sommers studies is attached which provides useful guidance on establishing a contamination survey program.
Based on the studies of residual radioactivity limits for decommissioning (hTJREG-06 132 and N%REG-07073), it can be concluded that surfaces uniformly contaminated at levels of 5000 dpm/lOO cm2 (beta-gamma activity from nuclear power reactors) would result in potential doses that total less than 5 mrem/yr. Therefore, it can be concluded that for the potentially undetected contamination of discrete items and materials at levels below 5000 dpm/l00 cm2, the potential dose to any individual will be significantly less than Smrem/yr even if the accumulation of numerous items contaminated at this level is considered.
Guidance:
Items and material should not be removed from the restricted area until they have been surveyed or evaluated for potential radioactive contamination by a qualified individual. Personal effects (e.g., notebooks and flash lights) which are hand camed need not be subjected to the qualified individual survey or evaluation, but these items should be subjected to the same survey requirements as the individual possessing the items. Contaminated or radioactive items and materials must be controlled, contained, handled, used, and transferred in accordance with applicable regulations.
The contamination monitoring using portable survey instruments or laboratory measurenients should be performed with iiistrumentation and techniques (survey scanning speed, counting times, background radiation levels) necessary to detect 5000 dpm/l 00 cm2 total and 1000 dpm/lOO cm2 removable betdgamma contamination. Lnstruments should be calibrated with radiation sources having consistent energy spectrum and instrument response with the
- .4 qualiiied individual is defined as a person meeting the radiation protection technician qualifications of Regulatory Guide 1.8, Rev. 1. which endorses ANSI N 18.1. 1971.
YNIS Turbine Building C-2
IEC 8 1-07 May 14, 1951 Page 3 of 3 radionuclides being measured. If alpha contamination is suspected appropriate surveys and/'or laboratory measurements capable of detecting 100 dpm/lOO cm2 fixed and 20 dpm'l00 crn' removable alpha activity should be performed.
In evaluating the radioactivity on inaccessible surfaces (e.g., pipes, drain lines, and duct work),
measurements at other appropriate access points may be used for evaluating contamination provided the contamination levels at the accessible locations can be demonstrated to be representative of the potential contamination at the inaccessible surfaces. Otherwise, the material should not be released for unrestricted use.
Draft ANSI Standard 13.124 provides useful guidance for evaluating radioactive contamination and should be considered when establishing a contamination control and radiation survey program.
No written response to this circular is required. If you have any questions regarding this matter, please contact this office.
REFERENCES Sommers, J. F., "Sensitivity of Portable Beta-Gamma Survey Instruments," Nuclear Safety, Volume 16, No. 4, July-August 1975.
U.S. Nuclear Regulatory Commission, "Residual Radioactivity Limits for Decommissioning, Draft Report," Office of Standards Development, USNRC NUREG-06 13, October 1979.
3 U.S. Nuclear Regulatory Commission, "A Methodology for Calculating Residual Radioactivity Levels Following Decommissioning," USNRC NUREG-0707, October 1980.
4 Draft ANSI Standard 13.12, "Control of Radioactive Surface Contamination on Materials, Equipment, and Facilities to be Released for Uncontrolled Use." American National Standards Institute, Inc.. New York, NY, August 1975.
Attachments:
- 1. Reference 1 (Sommers Study) 2.Recently issued E Circulars C-3