ML071230672

In-Process Inspection Survey Results for Selected Inside & Outside Open Land Area Survey Units at Yankee Nuclear Power Station, Rowe, Massachusetts

ML071230672
Person / Time
Site:	Yankee Rowe
Issue date:	08/17/2006
From:	Adams W Oak Ridge Institute for Science & Education
To:	John Hickman NRC/NMSS/DWMEP
References
RFTA 05-008
Download: ML071230672 (12)

Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION August 17,200 Mr. John Hiclunan Division of Waste Management and Environniental Protection U.S. Nuclear Regulatory Coinnission Two \\Vilite Flint North Mail Stop: 7F27 11 545 Rockville Pike Rochde, AjlD 20852-2738

SUBJECT:

IN-PROCESS INSPECTION SURVEY RESULTS FOR SELECTED INSIDE AND OUTSIDE OPEN LAND AREA SURVEY UNITS AT THE YANKEE NUCLEAR POWER STATION, RO\\VE, MASSACHUSETTS [DOCKET NO.

50-29; RFTA NO. 05-0081

Dear Mr. I-Iicknian:

The Oak Ridge Instimtct for Science and Education (ORISE) performed in-process confirmatoiy inspection survey activities on selected Inside Open Land (NOL) and Outside Open Land (OOL) Areas at the Yankec Nuclear Power Station in Rowe, Massachusetts during the period of June 21 and 22,2006.

These suwey activities were requested and approved by die U.S. Nuclear Regulatoiy Cotnmission (NlIC). Enclosed are the in-process survey results documenting thcse survey activitics. The survey activities included gainnia surface scans and soil sampling within several sui-vep units in the Open Land Areas.

If you have any questions or comments, please &ect them to me at 865.576.0065 or J. Scott I(Lk at 865.574.0685.

Sincerely, U & C L Wade C. Adains Health Physicist/Droject Leader Survey Projects

\\VCA:db Enclosure c:

T. McLauglilin, NRC/NMSS/TYWN T-7E18 E. iibclquist, ORISE E. Ihox-Davin, NRC/Nh/ISS/T\\VFN 8A23 J. Kottan, NRC/Rcgion I File/1672 S. IGrk, ORISE Distribution approval and concurrencc:

Ini ti aIs Technical Management Team Mcmber Labomtory Manager Quality Manager Voice: 865.576.0056 Fax: 865.241.3497 E-ind: Adams\\V@orau.gov

IN-PROCESS INSPECTION SURVEY RESULTS FOR SELECTED INSIDE AND OUTSIDE OPEN LAND AREA SURVEY UNITS AT THE YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS INTRODUCTION Ilie U.S. Nuclear Regulatory CoiillTllssioii (NRC) requested that die Oak Ridge Institute for Science and Education (ORISE) perform in-process inspection surveys of the selected Inside Open Land

[(NOL) NOL-04-01 and NOL-05-01] and Outside Open Land [(OOL) 00L-09-01,00L-09-02, OOL-07-02 and OOL-07-03] Area survey units (SU) at die Yankee Nuclear Power Station (YNPS).

The in-process inspection sumeys mere perforliied during tlie period of June 21 and 22, 2006.

PROCEDURES In-process inspection surveys were performed iii accordance with a site-specific suivey plan that was submitted to and approved by die NRC (ORISE 2005a). The site-spccific sm-vey plan follon7s the guidance provided in tlie ORISE Survey Procedures and Quality Assurance Manuals (OlUSE 2004 and 200511).

NOL-04-01. NOL-05-01.00L-09-01, and OOL-09-02 Exeavatioiis Gamna surface scans were performed on up to 80% of accessible portions of die four SU soil excavations using sodium iodide (NaI) scinallation detectors coupled to ratemeters with audible indicators. Due to die elevated gainma activity levels associated with the nearby independent spent fuel storage installation (ISFSI), a lead shield cohnator was used to partially shield the NaI detectors during die gamma scans. Soil sainples were collected from five locations in each SU. Figures 1 tlirougli 4 depict the soil excavation survey units that were part of these survey activities. Locations where soil samples were taken are depicted on these figures.

OOL-07-02 and OOL-07-03 Excavations Gamna surface scans were performed 011 up to 50% of accessible portions of the two SU soil excavations using NaI scintillation detectors coupled to ratemeters with audible incltcators. This area had previously been backfilled by YAEC to support tlie construction of a parking area and vehicles were parked in rows knitbig gamma scan coverage. One soil sample was collected from tlie outer edge of SU OOL-07-03 from an area that was native soil. Figures 5 and 6 depict die soil excavation suivey units that were part of these suivey activitics. The soil sainple location is depicted on Figure 6.

SAMPLE ANALYSIS AND DATA INTERPRETATION Radiological data and sainple media were returned to ORISEs laboiatoiy in Oak Ridge, TN for analysis and interpretation. Radioanalyses were performed in accordance with the ORISE Laboratory Procedures Manual (ORISE 2006). Soil sainples were analyzed by ganuna spectlroscopy for tlie prknaiy radionuclides-of-concern [ROC (i.e., CO-60 and Cs-l37)]. However, spectra were also xeviewed for additional gainma-emitting fission and activation products associated with the Yarlkee Nuclear Power Station 1672\\Rcports\\2006-08-17 In-Process Inspection Survey Ilesults

YNPS and other identifiable total absorption peaks. Soil sample results were reported 111 units of picocuries per grain (pCi/g).

FINDINGS AND RESULTS Gaimna surface scans identified one location of elevated direct gainma radation on the soil surface in SU NOL-05-01; tlis activity was due to a discrete particle which was remediated by Yankee Atoinic Electric Company (YAK) personnel. ORISE requested that this particular soil sample be analyzed by tlie on-site YAEC radioanalytical laboratoq. The radioanalytical results for this sample were 66,100 pCi/g of Co-60 and 476 pCi/g of Nb-94; tlie Cs-137 concentration was below tlie detection sensitivity of tlie radioanalytical procedure. The ranges of radionuclide concentrations for the 21 soil samples collected by ORISE were -0.02 to 0.42 pCi/g for CO-60 and 0.00 to 1.17 pCi/g for Cs-137. A complete listing of the soil sample results is presented iU Table 1.

SUMMARY

ORISE conducted in-process suweys of selected open land SUs at YNPS dwring tlie period of June 21 and 22,2006. An in-process cotifirmatoiy survey was implemented because die licensee did not have final status survey (FSS) data available for review. YNPS personnel provided ORISE with

@eliminary soil sample results.while on site.

Gainma surface scans identified one location of elevated direct gamma radiation within tlie NOL-05-01 soil excavation. ORISE requested tliat YAEC personnel collect a soil sample from this location and had tlie sainple analyzed by die YAEC on-site laboratoq7. The YAEC analytical results excecded tlie site derived concentration guideline levels (DCGL's) as presented in Table 2 for Co-60 and Nb-94 and the site DCGb,,

as presented in Table 1 of a tecluical basis document ('IBD) that supports elevated iiieasureinent coinpadsons (EMC) for FSSs (YAEC 2005). ORISE collected 21 soil sainples from judgmentally-selected locations. Gamma spectroscopy results for tlie 21 samples indicated that the ROC's were well below die DCGL's.

The in-process confirniatoiy surveys deterinhied that detectable activity, DCGLs (as presented in the LIP, Appendur 6J at 8.73 irein/yr), was present in one soil sample collected by YAEC within Suivey Unit NOL-05-01. However, dus soil sample contained a discrete particle and the soil DCGL's do not address discrete particles. Currently, the NRC and ORISE are evaluating YAEC's TBD concerning discrcte particles in soil; this infortnation, which will be addrcssed in a later report to NRC, is needed to ascertain whether or not tlie SU is suitable for unrestricted release. All other soil samples inet die unrestricted release criteria in accordance with clean up criteria cited in the licensee's L".

excess of the soil Yaiikec Nuclear Power Station 1672\\Reporu\\2006-08-17 In-Process Inspection Suwcy Results 2

1672-OOY (2)

NOL-04-0 1 SAMPLING LOCATIONS

1. SURFACESOIL 42 N \\

NOT TO SCALE FIGURE 1:

Yankee Nuclear Power Station, Survey Unit NOL-04 Sampling Locations 1672\\Reports\\2006-08-17 In-Process Inspection S u n y Results Yankee Nuclear Power Station 3

1672-010 (1) 38 35 39 SAMPLJNG LOCATIONS

1. SURFACESOIL R 37 N

?\\

NOT TO SCALE FIGURE 2:

Yankee Nuclear Power Station, Survey Unit NOL-05 Sampling Locations Yankee Nuclear Power Station 4

1672\\Rcports\\2006-08-17 In-Proccss Inspection Survey Results

lb7L-011 ( I )

OOL-09-0 1 45 SAMPLING LOCATIONS

1. SURFACESOIL N i NOT TO SCALE FIGURE 3: Yankee Nuclear Power Station, Survey Unit OOL-09 Sampling Locations 1672\\Keports\\2006 17 In-Process Inspection S m c y Results 5

Yankee Nuclear Power Station

1672-012 (1)

OOL-09-02 H 52 SAMPLING LOCATIONS

1. SURFACESOIL N

\\I\\

NOT TO SCALE FIGURE 4:

Yankee Nuclear Power Station, Survey Unit OOL-09 Sampling Locations Yankee Nuclear Power Station 1672\\11eports\\2006-08-17 In-Process Inspcction Sunreg Results 6

OOL-07-02 N

NOT TO SCALE FIGURE 5: Yankee Nuclear Power Station, Survey Unit OOL-07 Surveyed Areas Yatlkcc Nuclear Powcr Station 1672\\Rcports\\2006-08-17 In-Process Inspccdon Survey Results 7

1672-014 (2)

SAMPLING LOCATIONS

1. SURFACESOIL I

... \\

\\

........ SURVEYED AREA N

NOT TO SCALE FIGURE 6: Yankee Nuclear Power Station, Survey Unit OOL-07 Surveyed Areas and Sampling Locations Yankee Nuclear Power Station 1672\\Rcportr\\2006 17 In-Process Inspection Survey Results 8

TABLE 1 RADIONUCLIDE CONCENTRATIONS I N SOIL SAMPLES COLLECTED FROM SELECTED INSIDE AND OUTSIDE OPEN LAND AREA SURVEY UNITS YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS Sample Locationa II 1672S0040 I

-0.02 rf: 0.03' i

0.01 rf: 0.02 1672S0041 O.OOd 5 0.03 0.02 k 0.03 1672S0042 0.42 k 0.12 1.17 k 0.16 1672S0043 0.01 k 0.02 0.02 rf: 0.02 ti 1672S0044 I

-0.01

• 0.03 1

0.01 k 0.02 Survey Unit NOL05-01 1672S0035 I

0.00

• 0.02 1

0.02 & 0.02 1672S0036 0.02 f. 0.02 0.11 rf: 0.03 1672S0037

-0.01 ? 0.03 0.00 k 0.02 1672S0038 0.01 k 0.03 0.04 & 0.02 I

1672S0039 I

0.09 rf: 0.03 1

0.08 5 0.02 1 Survey Unit 00L-09-01 I

167230045 I

0.01 & 0.06 1

0.06

• 0.05 1

0.57 5 0.06 1672S0046 0.01 5 0.02 1672S0047

-0.01 k 0.03 0.16 k 0.03 I

I 1

1672S0048

-0.02 k 0.03 0.03 2 0.03 1672S0049 0.01 0.03 0.07 2 0.03 Survey Unit OOL-09-02 1672S0050 0.03 rf: 0.04 0.08 rf: 0.03 167280051 I

0.04 k 0.03 I

0.02 k 0.03 1672S0052 I

-0.01 4 0.02 I

0.03 t 0.02 1672S0053 I

0.01 rf: 0.04 I

0.13 k 0.05 1672S0054 I

0.01 k 0.03 I

0.02 2 0.03 Survey Unit OOL-07-03 167280055 0.02

• 0.02 0.06 k 0.02

.Refer to Figures 1 through 6.

bThe LTP DCGL values are 3.0 pCi/g for Cs-I 37 acid 1.4 pCi/g for Co-60.

cUnccrtaicities represent the 95% confidence level, based on total propagated unccrtainties.

1672\\Reports\\2006-08-17 In-Process Inspection S u n q Results 9

Yankee Nuclear Power Station

TABLE 2 L

SUMMARY

OF SOIL DCGLs FROM TABLE I N FINAL STATUS SURVEY PLANNING WORKSHEET YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSSETTS

.Soil DCGL's based on nnnud doses 8.73 mrcm/yr (the 10 mrcm/yr DCGT, adiustcd for tire dosc contributions from sub-surface concrete StrUchlrCS and tritium in ground water.

Yankee Nuclear Powcr Station 1672\\Reports\\2006-08-17 In-Process Inspection Survey Results 10

REFERENCES Oak Ridge Institute for Science and Education (ORISE). Suvey Procedures Manual for thc Environmental Survey and Site Assessment Program. Oak Ridge, Tennessee; September 2,2004.

Oak Ridge Institute for Science and Education. Proposed-In-Process Suvey Plan for die Remaining Spent Fuel Pool and Northeastern Upper RCA Yard Excavations, Yankee Nuclear Power Station, Rowe, Massachusetts [Docket No. 50-29; RFTA No. 05-0081. Oak hdge, Tennessee; December 1, 2 0 0 5 ~

Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Environmental Suivey and Site Assessment Program. Oak Ridge, Tennessee; July 28,2005b.

Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Enviro&ental Suivey and Site Assessinent Program. Oak Ridge, Tennessee; April 18,2006.

Yankee Atoinic Electric Company (YAEC). Yankee Atoinic Elecuic Company (YAEC) License Teuinination Plan (LTP) for the Yankee Nuclear Power Station (YNPS). Revision 1. Rowe, Massachusetts; November 2004.

Yankee Atoinic Electric Company. Use of In-Situ Gainnia Spectrum Analysis To Perform Elevated Measurement Coinparisons In Support Of Final Status Suiveys. Rowe, Massacliusetts; November 2005.

SaiAcc Nuclear Pourer Station 1672\\Reports\\2006 17 In-Process Inspection Survey Results 11