ML070400400

YNPS-FSS-TBN01-00, Final Status Survey Report, TBN-01-13, Frequency Plot FSS Data Through Calculation of ALARA Action Level

ML070400400
Person / Time
Site:	Yankee Rowe
Issue date:	02/21/2005
From:	Erickson M Yankee Atomic Electric Co
To:	NRC/FSME
References
TBN-01-13 YNPS-FSS-TBN01-00
Download: ML070400400 (312)

Text

TBN-01-13 Frequency Plot FSS Data U) 12 0

10 I (1) a) 8 i (0

%106 0

LM 4

2 z

0 -

mI-

-790 -477 -164 149 462 775 1089 1402 Upper End Value (dpm/lOOcm2)

TBN-01 -13 SCATTER PLOT FSS DATA 8300 -

6300 -

E g4300-0.

'* 2300-0 Z 1ff 300 - 0'

• 6 6 0 0Activity (dpm/100cm2) k-% k' l ( k '- kl 441 ' k' k '~ k'

( k '~ 4 k k Mea

• ~~ *. ~ . . 3StDev SDCGLw Measurement Location Names

TBN-01 -13 Direct Measurement Values 2000 1500 N

E CL 1.

0

• ~ 00----------------------------------*

0-

-- ------I

1. . . ..-...- . . . . . . .1 . .

-1000 0 20 40 D IU* ,I I

+;1 LIIH 60 80 100

Retrospective Power Curve TBN-01-13 DeCIo FA -urviyed Suze Size-Survey Ura ID. Abhk Bfta Smy Ur 203 Ra84siucde: 1CO-60 Sta& Test- r1.05 :j 10.0 2CG160 ( WRS Test 04 Ff 16300 am F~-jI 14ic LOM54999 WO- 4 ah r IPtobaft WI&@ 9mysy UMrums M~ik d4VWkrV on Lhe graph to endteem as2 valua Tres Rw~y UnkComeennad m2rcf Sf DCGL) 05twItIll Wa C2 a -40TJFe'm- _JJJ 11 ad lT1J 1j% !43T4--tJ, [ 11 Pmu

Direct Measurement Locations TBN-01 -xx-xxx-F-FM (e.g.01-002)

RESULTS NET "M 43 SURFACE -thS[F RESUT NETCPM.' 6 13-00 1 13- 2SUAC.nool TBN-01-13 Turbine Building Slab Footprint Concrete Areas 11Completed By: I L. Dockins 111/08/05 11 NOTE :All sa mp Ie Ioca tions genera t e ý us ing Asue . . amp .e - an ý- angu Iar pattern Irom a ran om stad pointI.

PRELIMINARY DATA REVIEW FORM Survey Unit: TBN-01-14 Survey Unit Name: Turbine Building Survey Unit 1 - building surface Classification: 1 INSTRUCTIONS:

Survey Media: Concrete Type of Survey: Final Status Survey Verify the general survey unit information Le. apt Type of Measurement: Fixed Point (HP-1 00C) Instrument efficiency values. Enter the FSS data Number of Measurements: 20 Activity Column and select the appropriate "Surf 2

Applicable DCGLw (dpm/1OOcm ): 6.3E+03 "View Charts" command button below.

DCGL(emc) (dpm/10Ocm2): 2.6E+04 smooth surf efficiency (c/d): 6.0E-02 rough surf efficiency (c/d): 3.7E-02 BASIC STATISTICAL QUANTITIES Net Activity Net Activity w/outliers w/out outliers 2 2 (dpm/1 00cm ) (dpm/1 0Ocm )

Minimum Value: 347 347 Maximum Value: 2197 2197 Mean: 1165 1165 Median: 1110 1110 Standard Deviation: 446 446 Mean-3SD(statistical outlier): -174 V" Chart.

Mean+3SD (statistical outlier):

ACTIVITY CONCENTRATION (pCi/g)

Mean Ambient Net Activity Gross Bkg Net Surface Net Activity w/out outliers 2

Measurement ID Location (cpm/100cm2) (cpm/100cm ) (cpm/100cm2) Description (dpm/100cm2) fDCGL (dpm/100cm2) 1 TBN-01-14-001-F-FM 298 231.1 67 smooth 1110 0.18 1110 2 TBN-01-14-002-F-FM 262 231.1 31 smooth 513 0.08 513 3 TBN-01-14-003-F-FM 303 231.1 72 smooth 1193 0.19 1193 4 TBN-01-14-004-F-FM 297 231.1 66 smooth 1094 0.17 1094 5 TBN-01 005-F-FM 231.1 smooth 6 TBN-01 006-F-FM 317 231.1 86 smooth 1425 0.23 1425 7 TBN-01-14-007-F-FM 293 231.1 62 smooth 1027 0.16 1027 8 TBN-01-14-008-F-FM 290 231.1 59 smooth 978 0.16 978 9 TBN-01-14-009-F-FM 307 231.1 76 smooth 1260 0.20 1260 10 TBN-01-14-010-F-FM 312 231.1 81 smooth 1342 0.21 1342 11 TBN-01 011 -F-FM 282 231.1 51 rough 1366 0.22 1366 12 TBN-01-14-012-F-FM 287 231.1 56 smooth 928 0.15 928 13 TBN-01-14-013-F-FM 282 231.1 51 smooth 845 0.13 845 14 TBN-01-14-014-F-FM 282 231.1 51 smooth 845 0.13 845 15 TBN-01-14-015-F-FM 284 231.1 53 rough 1420 0.23 1420 16 TBN-01-14-016-F-FM 313 231.1 82 rough 2197 0.35 2197 17 TBN-01-14-017-F-FM 313 231.1 82 smooth 1359 0.22 1359 18 TBN-01-14-018-F-FM 252 231.1 21 smooth 347 0.06 347 19 TBN-01-14-019-F-FM 307 231.1 76 rough 2036 0.32 2036 20 TBN-01-14-020-F-FM 263 231.1 32 rough 857 0.14 857

TBN-01-14 Frequency Plot FSS Data 12 U) 0 10 -t (1) 8 -i Co 0

0 6

%I-_

.0 4 E 2 z

0 ---- I I I

347 810 1272 1735 2197 Upper End Value (dpm/lOOcm2)

TBN-01-14 SCATTER PLOT FSS DATA 7000 6000 5000 iZ 4000 E0 cL. 3000

<2000-1000 -I "

V 0 0 0 0-F

-1000

$ ?< ' k" 4' k < 1<k k' k< k" k , k 1< 'k , 1<

, k, <,K" k" C Activity (dpm/100cm2)

-V -V "r NV VN Nl NV V VMa

---

3StDev Measurement Location Names - DCGLw

TBN-01 -14 Direct Measurement Values 3000 2500 E

0 2000 -£! -.. - - - - - - - a - - --

0 C:

0 4- 15000 Co L-100 00 II l 0

0 20 40 Percentile 60 80 100

Retrospective Power Curve TBN-01-14 ft "

SwveY Unk ID:

wwwwc --6o -i: rsWafistcd Test-,

r- SfignTest LDedasMEwsi AMph& Faxs BetI RnyeqAd Savey Surq Ugt 20 ize DCGL 1630 r WRS Teff WM OCVaiw:

Ci LB=R 56-88.9 A/0- 1.3?7 Prsb~ balt the Swurve UnitPasses Mlick wuwhewv on ONe puk to lie I ' - - UsingwWOy alawd parm-te valim OL IM I True Survey Unk Cenuestatda peqstu @IDCGL)

Iftstartil 111 io

• in II-;I)-Tj 'Fez-V-JýýCIT I V- I tý'* IN" -11"0140 lbaw

Direct Measurement Locations TBN-01 -xx-xxx-F-FM (e.g.01-002) 0 meters 10 TBN-O1 -14 Turbine Building Slab Footprint E

Concrete Areas Completed By: L. Dockins 11/08/051 NOTE: All sample locations generated using Visual Sample Plan (tnangular pattern from a random start point).

PRELIMINARY DATA REVIEW FORM Survey Unit: TBN-01-15 Survey Unit Name: Turbine Building Survey Unit 1 -

building surface Classification: 1 Survey Media: Concrete Type of Survey: Final Status Survey Type of Measurement: Fixed Point (HP-1 OC)

Number of Measurements: 20 2

Applicable DCGLw (dpmn/100cm ): 6.3E+03 DCGL(emc) (dpm/100cm2): 2.6E+04 smooth surf efficiency (c/d): 6.OE-02 rough surf efficiency (c/d): 3.7E-02 BASIC STATISTICAL QUANTITIES Net Activity Net Activity w/outliers w/out outliers 2 2 (dpm/100cm ) (dpmi t00cm )

Minimum Value: 198 198 Maximum Value: 1821 1821 Mean: 863 863 Median: 911 911 Standard Deviation: 470 470 Mean-3SD(statistical outlier): -547 Mean+3SD (statistical outlier): 2274 ACTIVITY CONCENTRATION (pCi/g)

Mean Ambient Net Activity Gross Bkg Net Surface Net Activity w/out outliers 2 2 2 Location (cpm/rl00cm2) (cpm/1 00cm2) (cpm/l00cm ) Description (dpm/1 00cm ) IDCGL (dpm/1 00cm )

1 TBN-01 001-F-FM 275 263.1 12 Smooth 198 0.03 198 2 TBN-01 002-F-FM 284 263.1 21 Smooth 347 0.06 347 3 TBN-01 003-F-FM 283 263.1 20 Smooth 330 0.05 330 4 TBN-01 004-F-FM 317 263.1 54 Rough 1446 0.23 1446 5 TBN-01 005-F-FM 329 263.1 66 Smooth 1093 0.17 1093 6 TBN-01 006-F-FM 292 263.1 29 Smooth 480 0.08 480 7 TBN-01-15-007-F-FM 284 263.1 21 Smooth 347 0.06 347 8 TBN-01 008-F-FM 328 263.1 65 Smooth 1077 0.17 1077 9 TBN-01-15-009-F-FM 288 263.1 25 Smooth 413 0.07 413 10 TBN-01-15-010-F-FM 283 263.1 20 Smooth 330 0.05 330 11 TBN-01 011 -F-FM 299 263.1 36 Smooth 596 0.09 596 12 TBN-01-15-012-F-FM 296 263.1 33 Rough 883 0.14 883 13 TBN-01 013-F-FM 325 263.1 62 Smooth 1027 0.16 1027 14 TBN-01 014-F-FM 317 263.1 54 Smooth 894 0.14 894 15 TBN-01-15-015-F-FM 348 263.1 85 Smooth 1408 0.22 1408 16 TBN-01 016-F-FM 330 263.1 67 Smooth 1110 0.18 1110 17 TBN-01-15-017-F-FM 300 263.1 37 Rough 990 0.16 990 18 TBN-01 018-F-FM 331 263.1 68 Rough 1821 0.29 1821 19 TBN-01-15-019-F-FM 319 263.1 56 Smooth 927 0.15 927 20 TBN-01-15-020-F-FM 321 263.1 58 Rough 1553 0.25 1553

TBN-01 -15 Frequency Plot FSS Data Co 12 0

Cu 10 (1)

.0 8

0 0O- 6 0.

4 E 2 z

0 I I 198 430 661 893 1125 1357 1589 1821 Upper End Value (dpm/lOOcm2)

TBN-01 -15 SCATTER PLOT FSS DATA 8500 6500 E 4500-g a.

2500 20 8

A v V 8 8

• A 500 + 8 8

• ~ 8

• 8

-ilnn

• ** @ *.*

• k@ @ * *.@ *.,. * *@ **

• 4@ @ 4[ OActivity (dpmn/lO0cm2)

~~( '< 4-k1 44 k-% k'% k'% k k k k ' < ' k (___

Mean

• * ** * * *- '- - * *- - * *- *- - 3 StDev

-DCGLw Measurement Location Names

TBN-01 -15 Direct Measurement Values 3500 0

3000 E

0 o 2500 E

• I*

2000 I I 0

I- I c 1500 C, I II II I 0

lI I--

0

>. 1000 500 I I I I 0

0 20 40 Percentile 60 80 1(C

)0

Retrospective Power Curve TBN-01-15 Survey UntID:

- eciin -fmRqurdS eSz IoWi .d["- Uk Radimlide: FCo-60 Sasi@ et r.psinTs WR I5625 -9 r'Ii1.43

,.wFk as -- -

aA- kip o 1L4 . A 112 1- -. - 0 S m

Trm Sv" Unk*K~d 4wq~co fDGL nJi4 tIVTJFWdIMD_.ýITJI ýBJMJM S5ý2 25P

Direct Measurement Locations TBN-01-xx-xxx-F-FM (e.g.01-002) 0 meters 10 TBN-01 -15 Turbine Building Slab Footprint Concrete Areas 11Completed By: I L. Dockins 111/08/05 II NOTE : AMsamp .a Ioca .ons genera . a ý us Ing - sue - aI ampIa P,an k- angu ar pa. am 1.om a ran om sta po n ,

PRELIMINARY DATA REVIEW FORM Survey Unit: TBN-01-16 Survey Unit Name: Turbine Building Survey Unit 1 -

building surface Classification: 1 Survey Media: Concrete Type of Survey: Final Status Survey Type of Measurement: Fixed Point (HP-1 00C)

Number of Measurements: 20 2

Applicable DCGLw (dpm/10Ocm ): 6.3E+03 DCGL(emc) (dpm/tOcm2): 2.6E+04 smooth surf efficiency (c/d): 6.0E-02 rough surf efficiency (c/d): 3.7E-02 BASIC STATISTICAL QUANTITIES Net Activity Net Activity w/outliers w/out outliers 2 2 (dlm/1 00cm ) (dom/100cm )

Minimum Value: -62 -62 Maximum Value: 2528 2528 Mean: 1071 1071 Median: 1280 1280 Standard Deviation: 747 747 Mean-3SD(statistical outlier): -1171 IVM4etOJ sstatstica uii-uw ouhei IC ACTIVITY CONCENTRATION (pCi/g)

Mean Ambient Net Activity Gross Bkg Net Surface Net Activity w/out outliers 2

Measurement ID Location (cpml1 00cm2) (cpm/1 00cm) (cpm/1 00cm Description (dpm/10Ocm2) fDCGL (dpm/1 00cm2 1 TBN-01-16-001-F-FM 352 247.7 104 Smooth 1729 0.27 1729 2 TBN-01-16-002-F-FM 342 247.7 94 Rough 2528 0.40 2528 3 TBN-01 003-F-FM 333 247.7 85 Smooth 1414 0.22 1414 4 TBN-01 004-F-FM 333 247.7 85 Rough 2286 0.36 2286 5 TBN-01 005-F-FM 327 247.7 79 Smooth 1315 0.21 1315 6 TBN-01-16-006-F-FM 329 247.7 81 Smooth 1348 0.21 1348 7 TBN-01-16-007-F-FM 317 247.7 69 Rough 1857 0.29 1857 8 TBN-01-16-008-F-FM 336 247.7 88 Smooth 1464 0.23 1464 9 TBN-01-16-009-F-FM 270 247.7 22 Rough 597 0.09 597 10 TBN-01-16-010-F-FM 303 247.7 55 Rough 1482 0.24 1482 11 TBN-01-16-011 -F-FM 253 247.7 5 Smooth 88 0.01 88 12 TBN-01-16-012-F-FM 269 247.7 21 Smooth 353 0.06 353 13 TBN-01 013-F-FM 311 247.7 63 Smooth 1049 0.17 1049 14 TBN-01-16-014-F-FM 244 247.7 -4 Smooth -62 -0.01 -62 15 TBN-01 015-F-FM 250 247.7 2 Smooth 38 0.01 38 16 TBN-01-16-016-F-FM 260 247.7 12 Smooth 204 0.03 204 17 TBN-01-16-017-F-FM 267 247.7 19 Rough 517 0.08 517 18 TBN-01-16-018-F-FM 272 247.7 24 Rough 651 0.10 651 19 TBN-01-16-019-F-FM 296 247.7 48 Rough 1294 0.21 1294 20 TBN-01 020-F-FM 324 247.7 76 Smooth 1265 0.20 1265 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7 247.7

TBN-01-16 Frequency Plot FSS Data U) 12 -1 0

10 -I CL) 8 -i U) m0 0 6 4-

.0 4 -i E 2 z

0 I I

-62 308 678 1048 1418 1788 2158 2528 Upper End Value (dpm/1OOcm 2)

TBN-01-16 SCATTER PLOT FSS DATA 8500 -

6500 -

4500-C.

2500-00 8 8

• 500 +

_trKNN O Activity (dpm/100cm2)

Mean

-DCGLw Measurement Location Names

TBN-01 -16 Direct Measurement Values 3500 4

3000 E

o 2500 0~

E r-- ,. - - - ..-. ..- - .. - -.. -.. - .. - -..... - - ...- - - - - - -

2000 . , ,

0

.o I I I a c 1500 I I

I U

C:

0 II ,I 0

0 -".- *. ". ". ." -'.

S1000

.i0 0

500 0

0 20 40 Percentile 60 80 100

Retrospective Power Curve TBN-O1-16 3W t ja na bea" z20 Io~

41 F~h 300 ILIoa 15247.-9 Wa - 1.41

• At-ti 1],

20 .0 ý2 m _JL_ _ _ _jI S(S>13

Direct Measurement Locations TBN-01 -xx-xxx-F-FM (e.g.01-002) 16-001 16-002 16-003 16-004 16-005 16-006 16-007 16-008 16-011 16-012 16-013 16-014 16z015 0 meters 10 TBN-01-16 Turbine Building Slab Footprint

-I Concrete Areas IIcomplted By:I L. Dockins 111/08/05 II NOTE: All sam le locations enerated usin Visual Sam le Plan Itrian ular attem from a random start intN

PRELIMINARY DATA REVIEW FORM Survey Unit: TBN-01-17 Survey Unit Name: Turbine Building Survey Unit 1 -

building surface Classification: 1 Survey Media: Concrete Type of Survey: Final Status Survey Type of Measurement: Fixed Point (HP-100C)

Number of Measurements: 20 2

Applicable DCGLw (dpm/100cm ): 6.3E+03 DCGL(emc) (dpmlOOcm2): 2.6E+04 smooth surf efficiency (c/d): 6.0E-02 rough surf efficiency (c/d): 317E-02 BASIC STATISTICAL QUANTITIES Net Activity Net Activity w/outliers w/out outliers 2 2 (dpm/1 00cm ) (dpm/1 00cm )

Minimum Value: -58 -58 Maximum Value: 1462 1462 Mean: 613 613 Median: 589 589 Standard Deviation: 390 390 Mean-3SD(statistical outlier): -556 Mean+3SD (statistical outlier): 1782 ACTIVITY CONCENTRATION (pCi/g)

Mean Ambient Net Activity Gross Bkg Net Surface Net Activity w/out outliers 2 2 2 2 2 Measurement ID Location (cpm/IOOcm ) (cpm/100cm ) (cpm/IOOcm ) Description (dpm/1OOcm ) fDCGL (dpm/100cm )

1 TBN-01 001 -F-FM 288 246.5 42 Smooth 689 0.11 689 2 TBN-01-17-002-F-FM 247 246.5 1 Smooth 9 0,00 9 3 TBN-01-17-003-F-FM 275 246.5 29 Smooth 473 0.08 473 4 TBN-01-17-004-F-FM 243 246.5 -3 Smooth -58 -0.01 -58 5 TBN-01-17-005-F-FM 295 246.5 49 Smooth 805 0.13 805 6 TBN-01-17-006-F-FM 301 246.5 55 Rough 1462 0.23 1462 7 TBN-01-17-007-F-FM 264 246.5 18 Rough 470 0.07 470 8 TBN-01-17-008-F-FM 277 246.5 31 Rough 818 0.13 818 9 TBN-01-17-009-F-FM 274 246.5 28 Rough 738 0.12 738 10 TBN-01-17-010-F-FM 279 246.5 33 Smooth 539 0.09 539 11 TBN-01 011 -F-FM 329 246.5 83 Smooth 1368 0.22 1368 12 TBN-01-17-012-F-FM 291 246.5 45 Smooth 738 0.12 738 13 TBN-01-17-013-F-FM 265 246.5 19 Smooth 307 0.05 307 14 TBN-01-17-014-F-FM 281 246.5 35 Smooth 572 0.09 572 15 TBN-01-17-015-F-FM 269 246.5 23 Smooth 373 0.06 373 16 TBN-01-17-016-F-FM 283 246.5 37 Smooth 606 0.10 606 17 TBN-01-17-017-F-FM 272 246.5 26 Smooth 423 0.07 423 18 TBN-01 018-F-FM 281 246.5 35 Rough 925 0.15 925 19 TBN-01-17-019-F-FM 253 246.5 7 Smooth 108 0.02 108 20 TBN-01 020-F-FM 300 246.5 54 Smooth 888 0.14 888 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5 246.5

TBN-01-17 Frequency Plot FSS Data U) 12 -I 0

(U 10 -1 m

Ow L_

a1) 8 -i I) 0 0 6 I1 M-M L_

.0 4 E

z 2 0

-58 159 376 593 811 1028 1245 1462 Upper End Value (dpm/lOOcm2)

TBN-01 -17 SCATTER PLOT FSS DATA 8500 6500 E 4500 t 2500-9 p 0~

500 +

p *

• p 9 9

-1FRfln

,1500 S' 4 k' ' ' '4 ', ' '4 '4 '4 '4 '4 '4 0 Activity (dpm/100cm2)

S* ..

• s , , " .-. *

,* ' ,* ,* '*" , , cMean

,s

"'- - - - - '- ' '- '- - - 3 StDev Measurement Location Names

TBN-01 -17 Direct Measurement Values 3500 3000 E

g 2500 E

2000 0

4.-

r -- -- - - - - - - - - - - - - - - - - --

• 1500 C) 0

.. . .. .. j 0

>, 1000

-I - -- - - - -

500 0

0 20 40 Percentile 60 80 100

Retrospective Power Curve TBN-01-17 M-19MIAMME . mmu fkf ftbiuisd Sam*b S1 17~6300 9

FJ5751 A/a 1.41 Cbck a-twheeon gar Vk o SP&Ms LAW powercuv ydAg h~

1aumo asj-t~l 12 s JMT jf-- j WK I It5j>10

Direct Measurement Locations TBN-01-xx-xxx-F-FM 11h (e.g.01-002) 0 meters 10 TBN-01-17 Turbine Building Slab Footprint Concrete Areas IICompleted By: L. Dockins 111/08/05 II NOTE: All sample locations generated using Visual Sample Plan (triangular pattern from a random start point).

Report No.: YNPS-FSS-TBNO 1-00 4I Attachment C Instrument QC Records (CTRL + Click on the link)

ISOCS (RED) Detector ISOCS (BLUE) Detector Hand-held Instruments

Full Q.A. Report 8:20:16 AM Page 1 YANKEE ROWE RED ROVER QUALITY ASSURANCE REPORT a

m Iw Full Parameter Results Report 2/6/06 8:20:16 AM QA File: C:\GENIE2K\CAMFILE$\QA Red 6264.

Description:

Centroid @ 1274 keV&

Parameter Units: ch Parameter Type: Peak Search Lower Boundary: 5.0940E+003 Upper Boundary: 5,1020E+003 Value Flags Measurement Time Sample ID (ch LU :SD: UD : BS

• R 10/19/05 5:29:54 PM QC 101905 PM 4 7473E+C'03 Be:

10/20/05 5:21 :21 AM QC 102005 AM 5. 0988E+0 03 10/21/05 5:39:49 AM QC 1.02105 AM 5.0948E.+ 03 10/21/05 4:22:51 PM 5.1012E+0 03 10/22/05 6:45: 5'6AM QC102205 AM 5 0972E+0'03 10/22/05 4:08:29 PM QC 102005 PM 5. 0977E+0303: .:

10/24/05 5:26: 24 AM QC 102405AM 5. 0961E+C'03

.10/25/05 R 10/25/05 10/25/05 10/26/05 10/26/05 5:25:25 AM 5:39:55 AM 11:48:45 AM 5:18:-02 AM 6:36:.14 AM QC 102505 AM, QC 102'505 AM.2 QC102505AM3 QC 102605 AM.

QC 102605 AM 5,.0963E+0'03 5..0964E+0 03 5, 0981E+C 03 5 :.0946E+0 03

'03 6 :11:34 AM 5 ý.0 943E+0 R 10/27/05

.8 34 :22 QC 102705 AM 5. 0994E+C03 10/27/05 AM QC 102705 AM 2 '03 10/28/05 5:20:23 .AM QC 102805 AM 5. 0985E+0 03 10/28/o5 8.:22:46 AM 5. 0975E+0 03 R 10/28/05 2:52:08 PM 5' 0996E+0 03 R 10/28/05 5:33 :42 QC 02805 PM 5. 0995E+C'03 R 10/28/05 5:46: 35 PM QC 02805 PM 2 4.8a30E+0 03 Be:

P: 10/29/05 6.:02:16 AM PM QC 102905 AM 5. 0984E+0 03 10/29/05 6:16:17 AM QC 102905 AM2 5.0982E+0303 1o0/291/05 .3::48:54 PM QC 102905 PM 5. 1007E+0]03 10/31/05. 5:08:00 AM QC 103105 AM 5. 09.87E+0)03 10/31/05 8:27:38 AM 5. 10.06E+0303

.... 0l/31/oS 4:38:33 PM QC 103105PM 5. 1021E+0303 Ab R 11/1/05 5:17:19 AM QC 110105 AM 4.7073E+0)03 Be:

11/1/05 5:51:39 AM QC 110105 AM 5.0994E+0'03 R11/1/05 1:53.48 PM 5.1040E+0303 Ab 11/1/05 1:59:34 PM 5.1006E+0303 4:05:53 PM QC1O01OSPM 5.0996E+0'03 R 11/2/05 5:11:03 AM QC 110205 AM 5.39921E+0 *03 Ab R 11/2/05 5:31:41 AM QC 110205 AM2 50934E+0*03 Be:

11/2/05 5:41:09 AM QC 110205 AM2 5. 0977E+0303 11/2/05 8:58:01 AM QC 110205 AM3 5. 0965E+C)03 11/2/05 4 :45 :54 PM QC110205PM 5. 0977E+( )03 11/3/05 5:40:31 AM QC110305AM 5. 0953E+0)03 I

Full Q.A. Report 2/6/06 8:20:16 AM Page 2 11/3/05 5:31:28 PM QC 110305 PM 5.1018E+003 Value Flags Measurement Time Sample ID (ch LU :SD: UD :BS 11/4/05 5:42:05 AM QC 110405 AJA 5. 0962E+0 03 11/4/05 5:07:50 PM QC 110405 PM 5.0985E+0 03 11/5/05 5:43:19 AM QC110505 5.09633E+0 03 R 11/5/05 2:14:19 PM QC110505PM 5. 1050E+0 03 Ab 11/5/05 2:34:02 PM. QC110505PM2 5. 1055E+0 03 Ab R 11/7/05 5:17:06 AM QC 110705 AM 4 8852E+0 03 Be:

11/7/05 5:34:20 AM QC 110705 AM2 5. 0971E+0 03 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be ý Below)

SD = Sample Driven N-SigmaTest (In = Investigate, Ac = Action)

UD = User Driven NwSigma Test (In = Investigate, Ac = Action)

BS = Measurement Bias Test (In = Investigate, Ac = Action) 5"

Full Q.A. Report 2/6/06 8:21:03 AM Page 1 YANKEE ROWE RED ROVE R QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:21:03 AM QA File: C:\GENIE2K\CAMFILES\QA Red 6264.

Description:

Centroid @,86 keY Parameter Units: ch Parameter Type: Peak Search Lower Boundary: 3.4400E+002 Upper 9oundary: 3,4800E+002 Value Flags Measurement Time Sample ID (ch LU :SD: UD BS R 10/19/05 5i29:54 PM QC 101905 PM 3,.2289E+0 02 Be.

3.;4687E+0 10/20/05 5 :21:21 AM QC 102005 AM 02 10/21/05 5:39:49 AM QC102105 A4 3.4660E+0 02 10/21/05 4 :22: 51" PM 3.4700E+0 02 10/22/05 6:45:56 AM QC102205 AM 3A.4679E+0 02 10/22/05 4:08:29 PM QC 102005 PM 3.4681E+0 02 10/24/05 5:26:24 AM QC 102405AM 3.'4671E+0 02 R 10/25/05 5:25:25 AM QC 102505 AM 3.4674E+0 02 10/25/05 5:39:55 AM QC 102505 AM .2 3.:4678E+0 02 10/26/05 11:48:45 AM QC102505A,143 3.4695E+0 02 10/26/05 5:18; 02 AM QC 102605 AM 3:."4648E+0 '02 10/26/05 6:36:14 AM QC 102605 AM 3.ý4655E+0 '02 10/27/05 1- 6:11:34 AM QC 102705 AM 3.4647E+0'02 10/27/05 8:34 :22 AM QC 102705 AM 2 3.4681E+0'02 10/28/05 5:20:23 AM QC 102805 AM 3.4682E+0'02 10/28/05 8:22:46 AM 3.,4669E+0'02 R 10/28/05 2:52:08 PM 3.4683E+O'02 R 10/28/05 5:33 :42 PM QC 02805 PM 3. 3204E+O'02 Be R. 10/28/05 5:46:35 PM QC 02805 PM 2 3.32.05E+0'02 Be:

P 10/29/OS 6102 :16 AM QC 102905 AM 3; 4680E+C'02

• 10/29/05 6:16:17 AM QC 102905 AM2 3 , 4677E+O'02 S 10/129/O5 3:48:54 PM QC 102905 PM 3. 4688E+O'02 10/31/05 5:081 00 AM QC 103105 AM 3.4680E+0 '02 10/31/05 8:27:38 AM 3.4688E+ 0'02 R 10/31/05 4:38:33 PM QC !03105PM 3 . 4698E+0'02 R 11/1/05 5:17:19 AM QC 110105 AM 3-2014E+0'02 Be:

11/1/05 5:51:39 AM QC 110105 AM 3.4687E+0'02 P 11/1/05 1:53:48 PM 3. 4704E+C'02 1:59:34 PM 3..4689E+C 02 11/1/05 11/1/05 4:05: 53 PM QC110105PM 3 4684E+0'02

• 11/2/05 5:11:03 AM QC 110205 AM 3. 1986E+0'02 Be:

R 11/2/05 5:28:04 AM QC 110205 AM 2 3.1981E+0'02 Be:

P 11/2/05 5:31:41 AM QC 110205 AM2 3..4.640E+C'02 11/2/o5 5:41:09 AM QC 110205 AM2 3.4675E+0'02 11/2/05 8:58:01 AM QC 110205 AM3 3.4659E+C'02

• • 11/2/05 4:45:54 PM QC110205PM 3. 4670E+0'02 I

Full Q.A. Report 2/6/P6 8:21:03 AMP Page 2 11/3/05 5:40:31 AM QC110305AN 3.4660E+002 Value Flags Measurement Time Sample ID (ch ) LU : SD : UD  : BS 11/3/05 5:31:28 PM QC 110305 PM 3.4695E+002 11/4/05 5:42:05 AM QC a10405 AN4 3.46.61E+002 11/4/05 .5:07:50 PM QC 110405 PM 3.~4679E+002 11/5/05 5:43:19 AM QC110505 3. 4665E+00.2 R 11/5/05 2:14:19 PM QC110505PM 3 .4714Ei-002 11/5/05 2:34:02 PM QC110505PM2 3..4720E+.002 R 11/7/05 5:17:06 AM QC 110705 AM 3.'3219E+002 Be:

11/7/05 5:34:20 AM OC 110705 AM2 3..4670E+002 Flags Key: LU ý Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test. (In = Investigate, Ac = Action)

UD = User Driven N-Sigma Teat (In = Investigate, Ac = Action)

SS ý Measurement Bias Test (In.= Investigate, Ac = Action)

I

Full Q.A. Report 2/6/06 8:21:13 AM Page I YANKEE ROWE RED ROVER QUALITY ASSURANCE REPORT Pull Parameter Results Report 2/6/06 8:21:13 AM QA File: C:\GENIE2K\CAMFILES\QA Red 6264.

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Description:==

FWHM 0 1274.5 keV Parameter Units: keV Parameter Type: Peak Search User Mean: 1.9300E+000 User Std. Deviation: 5.5000E-002 Value Flags Measurement Time Sample ID (keV LU :SD :UD BS R 10/19/05 5:29:54 PM QC 101905 PM 2.0788E+Q00  : n n:

10/20/05 5:21:21 AM QC 102005 AM 1 9160E+( 00 10/21./05 5:39:49 AM OC 102105 AM 1.9439R+0 00 10/21/05 4:22:51 PM 1. 9016E+0 00.

10/22/05 6:45:56 AM QC102205 AM 1. 9530E+0 00 10/22/05 4:08:29 PM QC 102005 PM 1.9238E+0 00 10/24/05 5:26: 24 AM QC, 102405AM 1. 9597E+0 00 R 10/25/05 5:,25:25 AM QC 102505 AM 1. 9787E+0)00 10/25/05 5:39:55 AM QC 102505 AM 2 1. 9642E+0 00 10/25/05 11:48:45 AM QC102505AM3 1. 9912E+0 00

.10/26/05. 5: 18:02 AM QC 102605 AM 1. 8857E+0 00 10/26/05 6:36:14 AM QC 102605 AM 1.- 9360E+0 00 R 10/27/05 6: 11:34 AM QC 102705 AM 1.9473E+0)00

.10/27/05 8 :34 :22 AM QC 102705 AM.2 1. 9043E+0 00 10/28/05 5:20 :23 AM QC 102805 AM 1.8936E+0)00 *:

10/28/05 8:22:46 AM 1. 9098E+O)00 R 10/28/05 2:52: 08 PM 1.9256E+0 00 R 10/28/05 5:33:42 PM QC 02805 PM 1. 8298E+0)00 R 10/28/05 55:46:35. PM QC 02805 PM 2 2.1212E+0 00  : A:i R 10/29/05 6 :02 :16 AM QC 102905 AM 1.9394E+C)00 10/29/005 6:16:17 AM QC 102905 AM2 1.9725E+0 00 10/29/05 3:48:54 PM QC 102905 PM 1. 911,6E+0)00 c 10/31/05 5:08:00 AM QC 103105 AM 1.8899E+0)00 10/31/05 8:27:38 AM 1. 9236E+C00 10/31/05 4:38:33 PM QC 103105PM 1. 9082E+0)00 R 11/1/05. 5:17:19 AM QC 110105 AM 2.2140E+0 00  :  : A' 11/1/05 5:51:39 AM QC 110105 AM 1. 9507E+0 00  :

R 1/1/05 1:53:48 PM 1. 9554E+0 00 c:

11/1/05 1:59:34 PM 1 .,9178E+000  :

11/1/05 4: 05: 53 PM QC110105PM I. 9099E+0so0 R 11/2/05 5:11: 03 AM QC 110205 AM 1. 1367E+0 00  :  : A R 11/2/05 5:31:41 AM QC 110205 AM2 2.0300E+0 00 11/2/05 5:41:09 AM QC 110205 AM2 1,9421E+0 500 11/2/05 8:58:01 AM QC 110205' AM3 1. 8786E+0)00 11/2/05 4:45:54 PM QC110205PM 1.9235E+C00:

11/3/05 5:40:31 AM QC110305AM 1. 9040E+0)00

Full Q.A. Report 2/6/06 8:21:13 AM Page 2 11/3/05 5:31:28 PM QC 110305 PM I.9835E+000 Value Flags Measurement Time Sample ID (keV LU : SD : UD  : BS 1.1/4/05 5:42:05 AM QC 110405 AM 1.9012E+000 11/4/05 5:07:50 PM QC 110405 PM 1.9521E+000 11/5/05 5:43:19 AM QC110505 1.9565E+000 R 11/5/05 2:14:19 PM QCII0505PM 1.9005E+000 11/5/05 2:34:02 PM QC110505PM2 1.8786E+000 R 11/7/05 5:17:06 AM QC 110705 AM 2.0796E+000 11/7105 5:34:20 AM QC 110705 AM2 1.8846E+000 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD =-User Driven N-Sigma Test (In = Investigate, Ac = Action)

BS = Measurement Bias Test. (In = Investigate, Ac = Action)

Full Q.A. Report 2/6/06 8:21:22 AM Page 1 YANKEE ROWE RED ROVER QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:21:22 AM, QA File: C:\GENIE2K\CAMPILES\QA Red 6264.

Description:

Activity @ 86.5 keV Parameter Units: uCi Parameter Type: Energy line User Mean: 8.3600E-001 User Std. Deviation: 1.OOOOE-002 Value Flags Measurement Time Sample ID (uCi LU :SD: UD : BS RR 10/19/05 5:29:54 PM QC 101.905 PM ,6.8040E-0 01 Ac,:

10/20/05 5:21:21 AM QC 102005 AM 8.4783E-0 R 10/21/05 5:26:47 AM QC 1021.05 AM

~00 0 0000E+0)01 Ac:

10/21/05 5:39:49 AM QC 102105 AM 8.3208E-0 10/21/05 4:22:51 PM 8.3689E-0 01 01 10/22/05 6:45:56 AM QC102205 AM 8.3538E-0 10/22/05 4:08:29 PM QC 102005 PM 8-46832E-0 ~01 Ac:

10/24/05 5:26:24 AM QC 102405AM 8.4012E-C 0100:

1R0/24/05 4:19:22 PM 0 .0000E+0 300 Ac:

8 .8189E-0 301 S 10/25/.05 10/225/05 10/25/05 5:25:25 5:39:55 11:48:45 AM AM AM QC 102505 AM QC 102505 AM 2 QCI02505AM3 8 78515-0 301

8. 3640E-0 301 Ac:

Ac:

R 10/26/05 5:18:02 AM QC 102605 AM 8.3157E-0 301 10/2.6/05 6:36:14 AM QC 102605 AM 8.2983E-C301

• R 10/27/05 6:11:34 AM QC 102705 AM 8.4346E-0 301 10/27/05 8:34:22 AM QC 102705 AM 2 8. 3225E-0 301 R 10/27/05 5 :34:13 PM 0.OOOOE+0301 Ac:

10/28/05 5:20:23 AM QC 102805 AM 8 .41632-0 301 10/28/05 8:22:46 AM 8 .4053E-0 301 R 10/28/o5 2 :52 :08 PM 8.4057E-0 301 R 10/28/05 5:33:42 PM QC 02805 PM 7.7323E-0 301 Ac :

R 10/28/05 5:46:35 PM QC 02805 PM 2 7.2909E-0 301 Ac:

R 10/29/05 6:02:16 AM QC 102905 AM 8.4907E-0 301 190/29/05 6:16:17 AM QC 102905 AM2 8.4617E-0 301 10/29/05 3:48: 54 PM QC 102905 PM 8.4986E-0 301 10/31/o5 5 :08 :00 AM QC 103105AM 8.2571E-0 301

.10/31/05 8 :27:38 AM 8.3946E-0 301 10/31/05 4 :38 :33 PM QC 103105PM 8. 5152E-0 301 R 11/1/05 5:17:19 'AM QC 110105 AM 6.8129E-0 301 Ac:

11/1/05 5:51:39 AM QC 110105 AM 8.42162-0301  :

R 1.1/1/05 1:53:48 PM 7.3312E-0 301 Ac:

11/1/05 1:59:34 PM 8.3931E-0 301,

• *i/i/os 4 :05:53 PM QClloII sPM 8,4001E-C301 R 11/2/05 5:11:03 AM QC 110205 AM 6.5477E-C301 Ac:

R 11/2/05 5:28:04 AM QC 110205 AM 2 6. 8367E-C 301 Ac:

R 11/2/05 5: 31.:41 AM QC 110205 AM2 8.4141E-( 301 I

Full Q.A. Report 2/6/06 8:21:22 AM Page 2 11/2/05 5:41:09 AM QC 110205 AM2 8.3744E-001 Value Flags MeasurementTime Sample ID (uCi LU : SD : UD : BS 11/2/05 8:58:01 kM QC 110205 AM3 8.4967E-003 11/2/05 4:45:54 PM QC112052PM 8.52482-001 11/3/05 5:40:31 AM QCI10305AM 8.3795E-001.

11/3/05 5:31:28 PM QC 110305 PM 8.4289E-001 11/4/05 5:42:05 AM QC 110405 AM 8.6014E-001 :In 11/4/05 5: 07: 50 PM QC 110405 PM 8.4846E-001 11/5/05 5:43:19 AM QC110505 8.4312E-001 P. 11/5/05 2:14:19 PM QC110505PM 8..1558E-001 :in 11/5/05 2 :34 :02 PM QC110505PM2 8.2644E-001 R 11/7/05 5:17:06 AM QC 110705 AM 7.2'849E-001 AC:

11/7/05 5:34 :20 AM QC 110705 M42 8.3506E-001 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac Action)

UD = User Driven N-Sigma Test (In = Investigate, Ac Action)

BS = Measurement Bias Test (In ý Investigate, Ac = Action)

Full Q.A. Report 2/6/06 8:21:36 AMPg Page 1 YANKEE ROWE RED ROVER QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:21:36 AM QA File.: C:\GENIE2K\CAMFILES\QA Red 6264.

Description:

Activity @C 1274 keV Parameter Units: uCi Parameter Type: Energy line User Mean: 9.8800E-001 User Std. Deviation: 1.2000E-002 Value Flags Measurement Time Sample ID '* * (uCi LU :SD :UD :BS R 10/i9/05 5:29:54 PM QC 101905 PM 8.13128E-001 Ac:

10/20/05 5:21:21 AM QC 102005 AM 1.:0049E+000 R 10/21/05 5:26:47 AM QC 102105 AM 0.OOOOE+000 Ac:

10/21/05 5:39:49 AM QC 102105 AM 9.ý. :9198E-001 10/21/05 4:22:51 PM 9, 8651E-001 10/22/05 6:45:56 AM QC102205 AM ,- 10004E+000 10/22/05 4 :08:29 PM QC 102005 PM 1."0189E+00.0 :In

.10/24/05 5.:26:24 AM QC 102405AM 9,9177E-001 R 10/24/05 4:19:22 PM 0.O000OE+000 * . Ac:,

1 0/25/05 5:25:25 AM QC 102505 AM 1.0161E+000 In 10/25/05 5:39:55 AM QC 10.2505 AM"'2 1. 0228E+000 :In 10/25/05 11:48:45 AM QC102505AM3 .9,9213E-001 R 10/26/05 5:18:02 AM QC 102605 AM. 9.8598E-001 10/26/o5 6:36:14 AM QC 102605 AM 9.8983E-001 R 10/2,7/05 6:11:34 AM QC 102705 AM 9.9610E-001 10/27/05 8:34:22 AM QC 102705 AM 2 9.8647E-001 R 10/27/05 5:34:13 PM 0. 000E+000 Ac:

10/28/05 5:20:23 AM QC 102805 AM 9.-9556E-001 10/28/o5 8:22:46 AM 9.9172E-001 10/28/05 2:52:08 PM 9.8627E-001 R 10/28/05 5:33:42 PM QC 02805 PM 9,0731E-002 * . Ac:

R, 10/28/05 5:46:35 PM QC 02805 PM 2 8.9191E-001 Ac:

R 10/29/05 6:02:16 AM QC 102905 AM 9. 9423E-00i 10/29/05 6: 16:17 AM QC 102905 AM2 1.0013E+000 10/29/05 3:48:54 PM QC 102905 PMý 9.9516E-001 10/31/05 5:08 :00 AM QC 103105 AM 9.7332E-001 10/31/05 8:27:38 AM 9.7917E-001 10/31/05 4:38:33 PM QC 103105PM 9.9239E-001 R 11/1/05 5:17:19 AM QC 110105 AM 0.0:000E+000  : . Ac:

11/1/05 5:51:39 AM QC 110105 AM 9,9629E-001 R 11/1/05 1:53:48 PM 7.5129E-001 - . Ac:

11/1/05 1 :59:34 PM 9 -.8337E-001 11/1/05 4 :05:53 PM QC110105PM 9.8329E-001 R 11/2/05 5:11:03 AM QC 110205 AM 1.8853E-003 Ac:

R 11/2/05 5:28 :04 AM QC 110205 AM 2 0.0000E+000 Ac:

R 11/2/05 5:31:41 AM QC 110205 AM2 9,9059E-001 I

Full Q.A. Report 2/6/06 8:21:36 AM Page 2 11/2/05 5:41:09 AM QC 110205 AM2 9. 9690E-001 Value Flags Measurement Time Sample ID (uCi LU  : SD : UD : BS 11/2/05 8 : 58: 01 AM QC 110205 AM3 9. 9917E-001 11/2/05 4 :45:54 PM QC110205PM 9,.9685E-001 11/3/05 5:40:31 AM QC1I0305AM 9. 8781E-001 11/3/05 5:31:28 PM QC 110305 PM 1.0002E+000 11/4/05 5:42:05 AM QC 1.10405 AM 1.0O101E+000 11/4/05 5:07:50 PM QC 11.0405 PM 9.,9199E-001 11/5/05 5:43:19 AM QC1I0505 '9.9506E~-001 R 11/5/05 2:14 :19 PM QC1O1505PM 9 .7590E.-001 11/s/os 2:34:02 PM QCi10505PM2 9.,7699E-001 P 11/7/05 5:17:06 AM QC 110705 AM 8 .84052-001 Ac:

11/7/05 5:34:20 AM QC 110705 AM2 9. 8473E-001 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Siqma Test (In = Investigate, Ac = Action)

UD = User Driven N-.Sigma Test (In = Investigate, Ac = Action)

BS 1 Measurement Bias Test (In = Investigate, Ac = Action)

I

Full Q.A. Report 2/6/06 8:31.:38 AM Page I YANKEE ROWE BLUE ROVER QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:31:38 AM QA File: S:\(Stored) QC FILES\QA Blue 627

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Description:==

Centroid @ 1274 keV Parameter Units: ch Parameter Type: Peak Search Lower Boundary: 5.0940E+003 Upper Boundary: 5.1020E+003 Value Flags Measurement Time Sample ID Analyst (ch LU  : SD UD BS 10/20/05 5:11:13 AM QC 102005 AM 5.0976E+003 10/21/05 5:25:06 AM QC 102105 AM 5.09482+003 10/21/05 4:45:38 PM 5.0974E+003 10/22/05 6:53: 18 AM QC 102205 .AM 5.0941E+003 10/22/05 4:20:00 PM QC 102005 PM 5.0962E+003 0/24/05 5:27:44 AM QC 102405 AM 5.0952E+003 0/24/05 4:25:56 PM 5.0958E+003 0/25/05 5:19:26 AM QC 102505 AM 5.0955E+003 R 10/25/05 3:.45:39 PM QC 102505 PM 5.0973E+003 10/25/015 4:07:29 PM QC 102505 PM 5.0964E+003 R 10/26/05 5:16:25 AM QC 102605 am 5.0951E+003 10/26/05 6:03 :44 AM QC 102605 am 5.0949E+003 10/27/05 6:03:53 AM OC 102705 AM 5. 0962E+003.

R_10/27/05 5:43:44 PM 5 4394E+003 Ab R, 10/27/05 6:04:29 PM 5.4387E+003 Ab R 10/28/05 5:26:05 AM 5. 0988P+003 10/28/05 5:37 :55 AM 5. 0987E+003 10/28/os 5:24:52 PM QC 102805 PM 5. 0991E+003 10/29/05 5:30:53 AM QC 102905 AM 5. 09902+003 10/29/05 3:43:56 PM 5 .0994E+00.3 10/31/05 5:18:22 AM QC 103105 AM 5. 0994E+003 10/31/05 5.:04:31 PM QC103105PM 5.1003E+003 R 11/1/05 5:18:00 AM QC 110105 AM 5.0993E+003 11/1/05 5:49:19 AM QC 110105 AM 5.0992E+003 il/1/05 4:02:39 PM QC110105 5.1018E+003 11/2/05 5:13:08 AM QC 110205 AM 5.1004E+003 11/2/0.5 4:53 :40 PM QC1102.05PM 5.1008E+003 11/3/05 5:42:24 AM QC 110305 AM 5.09882+003 11/3/05 5:36:20 PM QC 110305 PM. 5.1001E+003 11/4/05 5:40:30 AM QC 110405 AM 5.0990E+003 11/4/05 4:24:03 PM QC 110405 PM 5.1008E+003 11/5/05 5:41:47 AM QC 110505 AM 5.1004E+003 11/5/05 11:37:47 AM QC110505PM. 5.1031E+003 Ab 1i/7/05 5:24:51 AM QC 110705 AM 5.1000E+003 11/7/05 5: 37:07 AM QC 11070.5 AM 5.0999E+003 8:27 :20 AM QC110705AM2 5.1002E+003

Full Q.A. Report 2/6/06 8:31:38 AM Page 2 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD = User Driven-N-Sigma Test (In = Investigate, Ac = Action)

BS = Measurement Bias Test (In = Investigate, Ac = Action)

Full Q.A. Report 2/6/06 8:36:48 AM Page 1 YANKEE ROWE BLUE ROVER QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:36:48 AM QA File: S:\(Stored) QC FILES\QA Blue 627

==

Description:==

Centroid @ 86 keV Parameter. Units: ch Parameter Type: Peak Search Lower Boundary: 3.4400E+002 Upper Boundary: 3,4800E+002 Value Flags Measurement Time Sample ID Analyst .(ch LU  : SD : UD BS 10/201/05 5: 11: 13 AM QC 102005 AM 3 4679E+00 2 10/21/05 5:25: 06 AM QC 102105 AM 3. 4662E+00 2 10/21/05 4:45:38 PM 3. 4678E+00 2 10/22/05 6: 53: 18 AM QC. 102205 AM 3. 4658E+00 2 10/22/05 4 :20 :00 PM QC 102005 PM 3 4671E+00 2 o0/24/05 5:27: 44 AM QC 102405 AM 3 .4665E+00 2

/24/05 4:25:56 PM 3;4668E+00 2 0/25/05 5:19:26 AM QC 102505 AM 3.466.7E+00 2 R 10/25/05 3:45:39 PM QC 102505 PM 3.4770E+00 2 10/25/o5 4;:07:29 PM QC 102505 PM 3.4704E+00 2 R 10/26/05 5:16:25 AM QC 102605 am 3.4672E+00 2 10/26/05 6:03:44 AM QC 102605 am 3.4674E+00 2 10/27/05 6: 03: 53 AM QC 102705 AM 3.4672E+00 2 R, 10/27/o5 5:43 :44 PM 3.2290E+00 )2 Be:

R 10/27/05 6:04 :29 PM 3.2290E+00 '2 Be:

.R 10/28/05 5:26:05 AM 3.4688E+00 '2 10/28/o5 5:37:55 AM 3.4686E+00 2 10/28/05 5:24 :52 PM QC 102805 PM 3 .4690E+00 )2 10/29/05 5:30:53 AM QC 102905 AM 3 .4687E+00 10/29/05 3 :43 : 56 PM 3 .4693E+00 )2 10/31/05 5:18 :22 AM QC 103105 AM 3 .4691E+00 )2 10/31/05 5:04 :31 PM QC103105PM 3 .4695E+00 2 R 11/1/05 5: 18 : 00 AM QC 110105 AM 3 .469.0E+00 2.

11/1/05 5:49:19 AM QC 110105 AM 3.4689E+00 12 11/1/05 4 : 02 :39 PM QC110105 .3.4704E+00 2 11/2/05 5:13 :08 AM QC 110205 AM 3.4697E+00 2 11/2/05 4 :53 :40 PM QC110205PM 3.4699E+00 '2 11/3/05 5:42:24 AM QC 110305 AM 3.4687E+00 2 11/3/05 5:36:20 PM QC 110305 PM 3.4695E+00 12 1 i1/4/05 5:40:30 AM QC 110405 AM 3.4688E+00 2 11/4/05 4 :24 : 03 PM QC 110405 PM 3.4700E+00 2:

11/5/05 5:41:47 AM QC 110505'AM 3.4698E+00 12

/5/05 11:37:47 AM QCl10505PM 3 .4712E+00 12:

/7/05 5:24:51 AM QC 110705 AM 3.4695E+0C32:

1/7/05 5:37:07 AM QC 110705 AM 3.4693E+00 )2:

11/7/05 8:27:20 AM4 QC110705AM2 3.4695E+00 32:

Full Q.A. Report 2/6/06 8:36:48 AM Page 2 Flags Key: LU Lower/Upper Bounds Test b (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD = User Driven N-Sigma Test (In = Investigate, Ac = Action)

BS := Measurement Bias Test (In = Investigate, Ac = Action)

Full Q.A. Report 2/6/06 8:36:59 AM Page 1 YANKEE ROWE BLUE ROVE R QUALITY ASSURANCýE RE PORT Full Parameter Results Report 2/6/06 8:36:59 AM QA File: S:\(Stored) QC FILES\QA Blue 627

==

Description:==

FWHM @ 1274.5 keV Parameter Units: keV Parameter Type: Peak Search User Mean: 1.8587E+000 User Std. Deviation: 4 .5186E-002 Value Flags Measurement Time Sample ID Analyst (keV LU : SD : UD BS 10/20/05 5: 11:13 AM QC 102005 AM 1,8343E+00 0 10/21/05 5 :25 :06 AM 1.8802E+00 QC 102105 AM 10/21/05 4:45:38 PM 1.8651E+00 10/22/o5 6-53:18 AM QC 102205 AM 1.8428E+00 4:20:100 PM 0 10/22/05 0/24/05 QC 102005 PM 1. 9008E+00 5:27 :44 AM 0 QC 102405 AM 1. 8755E+00 4 :25:56 PM 0 10/24/05 1. 9006E+00 0  : :Ifl 0/25/05 5 :19:26 AM QC 102505 AM 1. 8514E+00 0 0 Ac R 10/25/05 3:45:39 PM QC 102505 PM 2. 1256E+00 0  :  : AC:

.10/25/05 4:07:29 PM PM QC 102505 2. 0196E+00 0  :  :  :

R10/26/05 5:16:25 AM QC 102605 am 1..9689E+00 10/26/05 6:03:44 AM QC 102605 am 1.9208E+00 0 10/27/05 6:03 :53 AM QC 102705 AM 1.8609E+00 0 R 10/27/05 5:43 :44 PM 3.2714E-00 I  :  : Ac:

R 10/27/05 6:04:29 PM 1 .5522E+00 0  :  : Ac:

R 10/28/05 5:26:05 AM 1. 8563E+00 0 10/28/o5 5:37:55 AM 1. 8762E+00 0 10/28/05 5:24 :52 PM QC 102805 PM 1. 9249E+00 0 10/29/05 5:30:53 AM QC 102905 AM 1 .8772E+00 0 10/29/os 3:43:56 PM 1. 9249E+00 0 10/31/os 5:18:22 AM QC 103105 AM 1 .8542E+00 0 10/31/05 5:04:31 PM QC103105PM 1. 8671E+00 00  : :I R 11/1/05 5:18:00 AM QC 110105 AM 1 .8763E+00 0:

0  :  :

11/1/05 5:49:19 AM QC 110105 AM 1.8424E+00 00  :

11/1/05 4 :02 :39 PM QC110105 1. 8137E+00 0 11/2/05 5:13:08 AM QC 110205 AM i.8741E+00 11/2/o5 '4:53:40 PM QC110205PM 1. 8982E+00 0 11/3/05 5 :42:24 AM QC 110305 AM 1.8602E+00 0 11/3/05 5:36 :20 PM QC. 110305 PM I. 9214E+00 0 11/4/05 5: 40:30 AM QC 110405 AM 1. 92462+00 0 11/4/05 4 :24 :03 PM QC 110405 PM I. 8710E+00 0 11/5/05 5:41:47 AM QC 110505 AM 1. 8527E+00 0 "1/5/05 11:37:47 AM QC110505PM 1. 9032E+00 i1/7/O5 5:24:51 AM QC 110705 AM 1. 8735E+00 0 11/7/05 5:37:07 AM 0 QC 110705 AM 1. 8608E+00 11/7/05 8:27:20 AM QC1I0705AM2 1. 9355E+00

Full Q.A. Report 2/6/06 8:36:59 AM Page 2 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD = User Driven N-Sigma Test (In = Investigate, Ac = Action)

BS Measurement Bias Test (In = Investigate, Ac = Action)

Full Q.A. Report 2/6/06 8:37:09 AM Page 1 YANKEE ROWE BLUE ROVER QUALITY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:37:09 AM QA File: S:\(Stored) QC FILES\QA Blue 627

==

Description:==

Activity @ 86.5 keV Parameter Units: uCi Parameter Type: Energy line User Mean: 9.1400E-001 User Std. Deviation: 1.0000E-002 Value Flags Measurement Time Sample ID Analyst (uCi . LU: SD: UD BS 10/20/O5 5:11: 13 AM QC 102005 AM 9.1460EO-0 10/21/05 5:25: 06 AM QC 102105 AM 9.2165E-00 10/21/05 4:45:38 PM 9.1927E-00 10/22/05 6:53:18 AM QC 102205 AM 9.1355E-00 10/22/05 4:20:00 PM QC 102005 PM 8.8783E-00 'i  : :In 10/24/05 5:27:44 AM QC 102405 AM 9.1538E-00 0/24/05 4:25:56 PM 9.1442E-00 0/25/05 5:19:26 AM QC 102505 AM 9.1583E-00 R 1.0/25/05 3:45:39 PM QC 102505 PM 9. 3138E-00 10/25/05 4 :07:29 PM QC 102505 PM 9.4489E-00 i  :  : Ac:

R 10/26/05 5: 16:25 AM QC 102605 am 9 4894E-00 1Ii  ::  :: Ac ::Ac 10/26/05 6 :03:44 AM QC 102605 am 9 .4474E-00 )I  :  : AC 10/27/o5 6: 03 : 53 AM QC 102705 AM 9.0620E-00 R 10/27/05 5:43:44 PM 8 .2038E-00 1  : ,: Ac:

R 10/27/05 6: 04:29 PM 8.2499E-00 1  :  : :Ac R 10/28/O5 5:26: 05 AM 9.5558E-00 i  :  : Ac:

10/28/05 5:37: 55 AM 9.2954E-00 10/29/05 5: 24:52 PM QC 102805 PM 9.0236E-00 10/29/05 5:30 :53 AM QC 102905 AM 8.9289E-00 10/31/05 3:43:56 PM 9.1340E-00 )1  : :I ":

10/31/os 5:18:22 AM QC 103105 AM 9.0604E-00 1 5:04:31 PM QC103105PM 9.1504E-00 1I:

R 11/1/05 5:18:00 AM QC 110105 AM 9.3051.E-00 1i:

11/1/05 5:49:19 AM QC 110105 AM 9.322SE-00 1i:

11/1/0s 4:02:39 PM QC11I0105 9.1897E-00 1 11/2/05 5:13 :08 AM QC 1.10205 AM 9.0470E-00 1:  :  :

11/2/05 4:53:40 PM QCI10205PM 9. 1996E-00 1  :  :

11/3/os 5:42 :24 AM QC 110305 AM 9,1142E-00 1 11/3/05s 5:36 :20 PM QC 110305 PM 9.0652E-0.0 11/4/o5, 5:40:30 AM QC 110405 AM 9.0835E-00 11/4/05 4 :24:03 PM QC 110405 PM 9. 1671E-00 11/5/05 5:41:4.7 AM QC 110505 AA 9.0821E-00 ifl/sos 11:37:47 AM QC110505PM 8.2218E-00 17/1o05 5:24:51 AM QC 110705 AM 8.8677E-00 1  :  : A :

1i/7/05 5:37:07 AM QC 110705 AM 9. 1765E-00 1  :  :  :

11/7/05 8:27:20 AM QCI1070.5AM2 9. 1471E-00

Full Q.A. Report 2/6/06 8:37:09 AM Page 2 Flags Key: LU = Lower/Upper Bounds Test (Abt Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD = User Driven N-Sigma Test (In = Investigate, Ac = Actioni BS = Measurement Bias Test (In = Investigate, Ac = Action)

Full Q.A. Report 21eio6Q 8: 37: 20 AA Page I YANKEE ROWE BLUE R.OVE,.R QUALI TY ASSURANCE REPORT Full Parameter Results Report 2/6/06 8:37:20 AM QA File: S:\(Stored) QC FILES\QA Blue 627

Description:

Activity @ 1274 keV Parameter Units: uC.

Parameter Type: Energy line User Mean: 8.6900E-001 User Std. Deviation: 8.0000E-003 Value Flags Measurement Time Sample ID Analyst (uCi ) LU SD : UD  : BS 10/20/05 5:11:13 AM QC 102005 AM 8. 6931E-001 10/21/05 5:25:06 AM QC 102105 AM 8.6881E-001 10/21/o5 4:45:38 PM 8.7887E-001 10/22/05 6:53:18 AM QC 102205 AM 8.7051E-001 10/22/05 4:20:00 PM QC 102005 PM 8 5107E-001 :In D0/24/05 5:27:44 AM QC 102405 AM 8. 7300E-001 4-:25:56 PM 8. 6935E-001

<R 10/25/05 5:19:26 AM QC 102505 AM 8. 6510E-001 10/25/o5 3:45:39 PM QC 102505 PM 8. 6850E-001 R. 10/26/05 4:07:29 PM QC 102505 PM 8. 7281E-001 10/26/05 5:16:25 A4 QC 102605 am 8 7709E-001 10/27/05 6:03:44 AM QC 102605 am 8. 7010E-001 R 10/27/05 6:03:53 AM QC 102705 AM 8. 6830E-001 R 10/27/05 5:43:44 PM 1.4567E-003 Ac:

R 10/28/05 6:04:29 PM 1.3977E-003 Ac :

10/28/05 5:26:05 AM 8. 9361E-001 Ac:

10/28/05 5:37:55 AM 8. 8521E-001 :In 5:24:52 PM QC 102805 PM 8. 6164E-001 10/29/05 5:30:53 AM QC 102905 AM 8. 5379E-001 10/29/05 3:43:56 PM 8.7126E-001 10/31/05 5:18:22 AM QC 103105 AM 8.5831R-001 10/31/05 5:04:31 PM QC103105PM 8. 7167E-001 11/1/05 5:18:00 AM QC 110105 AM 8 7856E-001 5:49:19 AM QC 110105 AM 8.8645E-001 11/1/05 4:02:39 PM QCII0105 8.7211E-001 11/2/05 5:13:08 AM QC 110205 AM 8.6023E-001 11/2/05 4:53:40 PM QC110205PM 8.7959R-001 11/30 5:42:24 AM QC 110305 AM 8.7313E-001 11/3/05 5:36:20 PM QC 110305 PM 8.6822E-001 11/4/05 5:40:30 AM QC 110405 AM 8.6986E-001 11/4/05 4::24:0.3 PM QC 110405 PM 8.64-45E-001 11/5/05 .5:41:47 AM QC 110505 AM 8,5736E-001 "ik /5/o5 11:37:47 AM QC110505PM 8.0626E-001 Ac:

5:24:51' AM QC 110705 AM 8.3812E-001 Ac:

11/7/05 5:37:07 AM QC .110705 AM 8.7654E-001 11/7/05 8:27:2 0 AM QC110705AM2 8.6104E-001

Full Q.A. Report 8:37:20 AM Page 2 Flags Key: LU = Lower/Upper Bounds Test (Ab = Above, Be = Below)

SD = Sample Driven N-Sigma Test (In = Investigate, Ac = Action)

UD = User Driven N-Sigma Test (In = Investigate, Ac = Action)

BS = Measurement Bias Test (In = Investigate, Ac = Action)

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Report No.: YNPS-FSS-TBNO1-00 I Appendix A Final Status Survey Planning Worksheet Survey Area TBN-01, Units 1 through 17 (CTRL + Click on the link)

TBN-01-01 TBN-01-02 TBN-01-03 TBN-01-04 TBN-01-05 TBN-01-06 TBN-01-07 TBN-01-08 TBN-01-09 TBN-01-10 TBN-01-11 TBN-01-12 TBN-01-13 TBN-01-14 TBN-01-15 I

TBN-01-1 6 TBN-01-17

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 01 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-01-01-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

.1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. 0 1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted Fi warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. E]

OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. M 1.6 A final classification has been performed. [

Classification: CLASS I 0 CLASS 2 [] CLASS 3 LI DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

" Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

• Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

TBN-01-01 is a building surface survey unit of 76 M2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-01-00, Page 1 of 8

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-100C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw andDCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

" DCGLw : 6.3E+03 dpm/100cm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/1 00cm 2.

" The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-01 5-04 provides instrument efficiency factors (Fi) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

" Gross activity DCGLw (HP-100C): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMc is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M 2 . Per LTP App. 6S, the next highest Area of Source = 4 M 2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-100C):

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLRMc: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). If necessary, the DCGLEMc will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I m2.

DPF-8856.1 YNPS-FSSP-TBN-0 1-01-00, Page 2 of 8 Rev. 2

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGL,.Mc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on Im ) source area = Im 2, 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpml CM) (dpm/100 CM) 8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 1.1E+04 InvestigationLevel ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-0l18-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMc associated with a I m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the 1m2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/ 100 cm 2 .

• The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/100cm2 (Co-60) and 1.6E+04 dpm/i 00cm2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of I.7E+04 dpm/1 00cm 2. The ISOCS Investigation Level is conservatively calculated for a I m222 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMC.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

InvestigationLevel Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

InvestigationLevel SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-l08m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-I154, Eu-155.

MDCsfor ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Tablel above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-JOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-01-00, Page 3 of 8

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs- 137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/100cm 2 (Co-60) and 1.6E+04 dpm/1 00crn2 .(Cs-137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/1OOcm 2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 1.

Define the boundaries of the survey:

TBN-01 -01 is bounded by survey area SVC-01 to the east, NOL-01 and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01 -01 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type II (fl) error: 0.05 LBGR: 34123 dpm/100 cm2 6.0 Optimize Design:

Type of statistical test: WRS Test [] Sign Test [

Background to be applied: media-specific E] ambient E] none M If WRS test is specified, record background reference area location:

Basis including background reference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-01-00, Page 4 of 8 0

Final Status Survey Planning Worksheet INSTRUCTIONS I The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-01-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01-01-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-01-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-01-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-01-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements

• 4.2.1. Start with TBN-01-01-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-01-01-012-F-FM is to be recounted, use TBN-01-01-012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-01-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-01-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-01-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-01-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect I-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-01-016-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Sup ervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

O DPF-8856. 1 YNPS-FSSP-TBN-0 1-01-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once'per shift in accordance with DP-8869 and DP-887 I. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

• 6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6., Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMC.

7. Operation of the E-600 will be in accordance with DP-8535, with'QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading ineach elevated area, perform and record a 1-minute scaler reading using the E600/HP 100C.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OOC. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the'total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN-0 1-01-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform andrecord a I-minute scaler reading using the E600 with the HP-I OOC.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-01-00, Page 7 of 8 Y

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (1)Date/time of initial pre-survey briefing

/ QA Signature/Date: (I)-

(2)Date/time of daily pre-shift briefing

/ QA Signature/Date: (2).

(3)Date/time of commencement of HP- 100 measurements QA Signature/Date: (3).

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

FSI point(s) (y/n) NO (2)

(2)

/________

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by- Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by- Date FSS Project Manager DPF-8856. l YNPS-FSSP-TBN-01.-01 -00, Page 8 of 8 Rev. 2

Final Status Survey Planning Worksheet Page 1 of 5

. GENERAL SECTION Survey Area #: TBN-01 Surve Unit #: 02 Survey Unit Name: Circulating Water Discharge Line - South End - Y-shaped Piece FSSP Number: YNPS-FSSP-TBN-01 01 (Text and numbers that are new to Rev. 01 are in Bold)

PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records. Zl 1.2 ALARA review has been completed for the survey unit. Zl 1.3 The survey unit has been turned over for final status survey. El 1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. El 1.5 Activities conducted within area since turnover for FSS have been reviewed. El Based on reviewed information, subsequent walkdown: El not warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. El 1.6 A final classification has been performed. El Classification: CLASS I Zl CLASS 2 El CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01-02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length,'it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01 -02 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 02 has an internal surface area of approximately 96 m 2 including the entire, interior surface of the steel Y-shaped piece.

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line.

The first FSS survey consisted of 15 survey points laid out in a triangular grid pattern with a random start point. There were no points with measurements greater than DCGLw.

. DPF-8856.1 Page 1 of 5 YNPS-FSSP-TBN-01-02-01

After an intense rainstorm, a question was raised as to whether material from the surface may have been carried into the pipe. Berms were constructed around both of the openings. An area surveillance (YNPS-ASP-TBN01-02-01) was performed, in accordance with DP-8860, in an effort to determine if the radiological conditions had changed since FSS. Two survey points from that surveillance exceeded the mean plus two standard deviations of the original FSS data. This necessitated the performance of an investigative area surveillance (YNPS-ASP-TBN01-02-02).

Two of the new survey points had results greater than the criteria, so the FSS has to be redone.

This plan provides the guidance for the new FSS of this survey unit.

This plan includes a 100% beta scan and 15 fixed-point measurements with a different random start point from the original FSS. The gamma scan that was included in the original FSS is not being repeated because it was intended to find any cracks that might contain radioactive material.

None were found in the original FSS and there is no reason to think that would have changed.

The characterization that was done at the-time the original FSS plan was developed included the collection of background data for the HP- 100 and SPA-3, biased scans with the HP- 100 and SPA-3, and samples of the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner.

The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs-137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7' will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the possible intrusion of material from outside the Survey Unit did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as radioactive waste.

3.0. Identify the inputs to the decision:

Sample media: None Types of measurements:

(a) 100% beta scan, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern: Co-60 Initial characterization data for all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-I 37 and traces of other radionuclides were found too inconsistently in-sediment samples to be able to establish a less conservative nuclide DPF-8856.1 YNPS-FSSP-TBN-01-02-01 Page 2 of 5

mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data

• Quality Objective (DQO) process in accordance with procedure DP-8856.

Applicable DCGL: 7200 dpm/ 100 cm 2 (Co structure surface) (434 cpm, HP- 100)

DCGLe,,c: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M 2. The DCGLe... for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

0 Area Factor: AFCo-6 = 1.6 DCGLemc : AFxDCGL DCGLemc 11, 500 dpm/100 cm 2 (Co-60) (694 cpm, HP- 100)

Average

Background:

155.1 cpm (HP- 100) (based on background measurements taken 7/13/05) (no background will be subtracted)

Average Fixed Measurement: 189.4 cpm, HP-100 (based on original FSS)

Standarddeviation: 21.5 cpm, HP- 100 Surrogate DCGL: No surrogate DCGL will be used.

Investigation Level for fixed-point measurements: 11,500 dpm/100 cm 2 (694 cpm, HP-100) -or- any result that is 7200 dpm/100 cm 2 (434 cpm, HP-100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60.

Investigation Level for HP-I00 scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-I00 scan: 100 cpm to 200 cpm (based on background measurements taken 7/13/05) (no background will be subtracted)

• Radionuclides for analysis: (N/A)

GrossActivity DCGL: The DCGL for the HP-100 is based on the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/100 cm 2 to achieve less than 10 mrem/y. Using a total efficiency (ei x F) of 0.0602 for the HP-100, and its probe area of 100 cm 2, this comes to 434 cpm.

Efficiencies and MDC for HP-I00 Fixed PointMeasurements: The efficiencies come from YA-REPT-00-015-04.

Ei = 0.2413 (This is the 27c beta efficiency established for this detector at 0.5 inch)

E,= 0.25 (for beta emitters - 0.400MeVmax, e.g., Co-60)

MDCfixed (HP-100): = 1010 dpm/100 cm 2 (60.9 cpm, HP-100)

Scan coverage: HP-I 00 scans will be performed over the entire inside surface of the survey unit.

Scan MDCR (HP-I00) : 94.9 cpm Scan MDC (HP-I00)(fDCGLMC):0.193 QC checks and measurements: QC checks for the E-600/HP-100 will be performed in accordance with DP-8504.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 02 are as shown on the attached map. The unit includes the steel, Y-shaped section of Circulating Water Discharge line from ground level, including two vertical, 60-inch sections within the footprint of the Turbine Hall transitioning into the horizontal, 84-inch line north of the footprint at the interface with the concrete pipe.

5.0 Develop a decision rule:

. DPF-8856. I Page 3 of 5 YNPS-FSSP-TBN-01-02-01

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meei the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type II error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test P]

Basis including background reference location' No background will be subtracted.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

GENERAL INSTRUCTIONS

!. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

2. Mark the grid locations as described in Specific Instruction 2.

3. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

4. Fixed point measurement location designation:

a) Grid point locations: TBN-01-02-001-F-FM through TBN-01-02-015-F-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01 XXX-F-FM, with the next sequential number in place of the XXX.

5. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within '/2 inch of the surface.

6. Survey instrument: Operation and source checking of the E-600 w/HP-100 will be in accordance with DP-8534 and DP-8504. The instrument response checks shall be performed before issue and after use.

7. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-01 -02 through TBN-01 -08.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions I. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be small but distinct.

2. Perform the fixed-point measurements with the E-600/HP-100 in the scalar mode, collecting I-minute readings within 1/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the DPF-8856.1 YNPS-FSSP-TBN-0 1-02-01 Page 4 of 5

material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

3. Scan 100% of the surface with the HP-100 detector 1/2" from the surface at a rate no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for investigation and log the finding.

4. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA. notification point(s)* (yin) y Specify: QA Signature/Date:

1. Date/time of initial pre-survey briefing

2. Date/time of commencement of fixed measurements

3. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1.

2.

Prepared by Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager

. DPF-8856.1 Page 5 of 5 YNPS-FSSP-TBN-0 1-02-01

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION Survey Area #: TBN:0 I Survey Unit #: 03 Survey Unit Name: Circulating Water Discharge Line - Second unit from Turbine Hall FSSP Number: YNPS-FSSP-TBN-0 1-03-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records. Z]

1.2 ALARA review has been completed for the survey unit. I]

1.3 The survey unit has been turned over for final status survey. El 1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. R) 1.5 Activities conducted within area since turnover for FSS have been reviewed. Zl Based on reviewed information, subsequent walkdown: El not warranted El warranted If warranted, subsequent walkdown has been performed and 'documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. n 1.6 A final classification has been performed. Wl Classification: CLASS 1 Zl CLASS 2 E CLASS 3 E DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01 -02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01-03 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 03 has an internal surface area of approximately 94 M 2 .

The original characterization data consisted of a set of four sediment samples from ,the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of DPF-8856.1 YNPS-FSSP-TBN-0 1-03-00 Rev. Original Page 1 of 8.

the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs-137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern:Co-60 Initial characterization data for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-137 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design.of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan.

Applicable DCGL: 7200 dpm/100 cm2 (Co structure surface) (434 cpm, HP-100)

. DPF-8856.1 Rev. Original Page 2 of 8 YNPS-FSSP-TBN-01 00

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs will apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E1; Cs-137: 1.45E3; all in pCi/g.

DCGL,,,: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M 2 . The DCGLe,,c for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

Area Factor: AFc-6 = 1.6 DCGLemc = AFxDCGL DCGLer... = 11,500 dpm/100 cm 2 (Co-60) (694 cpm, HP-100)

Average

Background:

92.2 cpm (HP- 100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP-100)

Standard deviation: 860 dpm (51.9 cpm, HP- 100)

SurrogateDCGL: No surrogate DCGL will be used.

Investigation Level for fixed-point measurements: 11,500 dpm/100 cm 2 (694 cpm, HP- 100) -or- any result that is 7200 dpm/l100 cm 2 (434 cpm, HP-100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 Investigation Level for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad' Engineer.

Investigation Level for HP-I00 scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-I00 scan: 70 cpm to 120 cpm Radionuclidesfor analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCs for gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108m 0.25-1.3 Sb-125 1.1-5.5 Cs-134 0.17-0.86 Cs-137 0.30-1.5 Eu-152 0.35-1.7 Eu-154 0.33-1.7 Eu- 155 14-70 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs.

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL values. If it is impractical to achieve those, the 50% DCGL valUes must be achieved in the laboratory analyses of the DPF-8856. I YNPS-FSSP-TBN-0 1-03-00 Rev. Original Page 3 of 8

FSS soil samples.

MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1.1-5.7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP- 100 is based on the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/100 cm 2 to achieve less than 10 mrem/y. Using a total efficiency (ci x c,)

of 0.0602 for the HP-100, and its probe area.of 100 cm 2 , this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP- 100 background: 92.2 cpm, with a standard deviation of 23.0 cpm SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDCfor HP-100Fixed Point Measurements: The efficiencies come from YA-REPT-00-015-04.

j = 0.2413 (This is the 2nr beta efficiency established for this detector at 0.5 inch)

F, = 0.25 (for beta emitters - 0.400MeVmax, e.g., Co-60) 2 MDCfixed (HP- 100): = 790 dpm/100 cm Scan coverage: HP-I100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-]00) : 73.2 cpm Scan MDC (HP-I00)(fDCGLFMc):0. 149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply to investigations in this unit.

Scan MDCR) (SPA-3): Scan MDCR is calculated from the equation:

MDCR = I.38,1 LTP, equation 5-25 4X t where b = background counts in time t t= time detector is above localized contamination p = surveyor efficiency = 0.5

. DPF-8856 1 Rev. Original Page 4 of 8 YNPS-FSSP-TBN-01-03-00

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t = distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150 c/s x 1.12 s = 168 counts 1.38 li/i MDCR - = 22.58 c/s or 1355 cpm

ý-fx 1.12s Scan MDC (JDCGL) (SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = 1.04E-3 Background Determination:Background will be determined in the accordance with DP-8866, using the guidance for "Ambient Background Measurements."

QC checks and measurements: QC checks for the E-600/HP-100 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 03 are as shown on the attached map. The unit extends from the interface between the steel Y-shaped pipe and the concrete pipe to a point that is 13.98 feet below the bend in the 84" pipe. The upper boundary is easily recognized by the thick weld at the upper end of the liner.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type H error:.0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test Z],

Basis including background reference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

GENERAL INSTRUCTIONS DPF-8856.1 YNPS-FSSP-TBN-01-03-00 Rev. Original Page 5 of 8

Scoping/Characterization Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The following is a summary of the expected measurements but subject to change without requiring a revision V to this plan.

• .As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements- HP100:

• Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom of pipe and lengthwise in both directions, with 1 / 8 th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get, background at same point as HP-100 background.

a All points where beta readings were taken.

0 Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

d) Samples:

• Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

d Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-01 XXX (starting at 001)-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance with DP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into 1/2/2" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis. If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking care to extract chunks from both the inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-01 XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01-02-001-C-CBi.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

0 Chain of Custody form will be used in accordance with DP-8123 for the samples to be SDPF-8856.l YNPS-FSSP-TBN-01-03-00 Rev. Original Page 6 of 8

sent to an off-site laboratory.

e) Surface preparation: If the decision is made to perform FSS, the surface scale will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigation criteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point measurement location designation:

a) Grid point locations: TBN-01-03-001-FM through TBN-01-03-015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-0 I-03-XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within 1/2/ inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP- 100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue'and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-0 1-02 through TBN-01 -08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions

1. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of background measurements may be used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be small but distinct.

3. Perform the fixed-point measurements with the E-600/HP-100 in the scalar mode, collecting 1-minute readings within 1/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

4. Scan 100% of the surface with the HP- 100 detector '/2" from the surface at a rate no greater than 2" DPF-8856.1 YNPS-FSSP-TBN-0 1-03-00 Rev. Original Page 7 of 8

per second, listening for an increased count rate using earphones. Pause at any upscale reading and allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA notification point(s)* (yin) y Specify: QA Signature/Date:

1. Date/time of initial pre-survey briefing

2. Date/time of commencement of background readings 3: Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP-100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1.

2.

Prepared by Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by- Date FSS Project Manager YNPS-FSSP-TBN-0 1-03-00 O Rev. Original DPF-8856.1 Page 8 of 8

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION O Survey Area#: TBN-01 Surve Unit#: 04 Survey Unit Name: Circulating Water Discharge Line - Third unit down from the Turbine Hall FSSP Number: YNPS-FSSP-TBN-0 1-04-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records. []

1.2 ALARA review has been completed for the survey unit. []

1.3 The survey unit has been turned over for final status survey. I]

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. IZ 1.5 Activities conducted within area since turnover for FSS have been reviewed. Z Based on reviewed information, subsequent walkdown: Z] not warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. El 1.6 A final classification has been performed. IZ Classification: CLASS I Z] CLASS 2 El CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01 -02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01 -04 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 04 has an internal surface area of 100 M 2 .

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of DPF-8856.1 YNPS-FSSP-TBN-01-04-00 Rev. Original Page 1 of 8

the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear, samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner,;no Co-60 was found, although a trace of Cs-137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are thatrthe liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern: Co-60 Initial characterization data,for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-I 37 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan.

Applicable DCGL: 7200 dpm/100 cm 2 (Co structure surface) (434 cpm, HP-100)

. DPF-8856.1 Rev. Original Page 2 of 8 YNPS-FSSP-TBN-01-04-00

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs will apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E1 ; Cs-137: 1.45E3; all in pCi/g.

DCGLmj: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M 2 . The DCGLemc for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

Area Factor: AFCo°6 °= 1.6 DCGLemc = AFxDCGL DCGLemc = 11,500 dpm/ 100 cm 2 (Co-60) (694 cpm, HP- 100)

Average

Background:

92.2 cpm (HP-100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP-100)

Standarddeviation: 860 dpm (51.9 cpm, HP- 100)

SurrogateDCGL: No surrogate DCGL will be used.

Investigation Level forfixed-point measurements: 11,500 dpm/l100 cm 2 (694 cpm, HP-100) -or- any result that is 7200 dpm/100 cm 2 (434 cpm, HP-i00) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 InvestigationLevel for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad Engineer.

Investigation Level for HP-100 scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-100scan: 70 cpm to 120 cpm Radionuclidesfor analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCs for gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108m 0.25-1.3 Sb- 125 1.1-5.5 Cs-134 0.17-0.86 Cs-137 0.30-1.5 Eu-152 0.35-1.7 Eu-154 0.33-1.7 Eu-155 14-70 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs.

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL values. If it is impractical to achieve those, the 50% DCGL values must be achieved in the laboratory analyses of the DPF-8856.1 YNPS-FSSP-TBN-01 00 Rev. Original Page 3 of 8

FSS soil samples.

. MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1.1-5.7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP- 100 is based on the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/100 cm 2 to achieve less than 10 mrem/y. Using a total efficiency (E x F) of 0.0602 for the HP- 100, and its probe area of 100 cm 2 , this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP-100 background: 92.2 cpm, with a standard deviation of 23.0 cpm SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDC for HP-I00 Fixed PointMeasurements: The efficiencies come from YA-REPT-00-015-04.

E = 0.2413 (This is the 27t beta efficiency established for this detector at 0.5 inch)

E,= 0.25 (for beta emitters *- 0.400MeVma.,. e.g., Co-60) 2 MDCfixed (HP- 100): = 790 dpm/100 cm Scan coverage: HP-100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-I00):73.2 cpm Scan MDC (HP-I00)(fDCGLpm): 0A149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply to investigations in this unit.

Scan MDbCR) (SPA-3): Scan MDCR is calculated fromthe equation:

1.38,lb MDCR= LTP, equation 5-25 where b = background counts in time t t = time detector is above localized contamination p = surveyor efficiency = 0.5

.PDPF-8856.1 Rev. Original Page 4 of 8 YNPS-FSSP-TBN-01-04-00

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t= distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150 c/s x 1.12 s = 168 counts 1.38- 168 MDCR = = 22.58 c/s or 1355 cpm

-fix1.12s Scan MDC (fDCGL) (SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = 1.04E-3 Background Determination:Background will be determined in the accordance with DP-8866 , using the guidance for "Ambient Background Measurements."

QC checks and measurements: QC checks for the E-600/HP-100 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 04 are as shown on the attached map. The unit is 48.92 feet long. Its lower (northern) boundary is 131 feet from the Seal Pit.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error:0.05 Probabilityof type II error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test R1 Basis including background reference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

GENERAL INSTRUCTIONS Scoping/Characterization DPF-8856.1 YNPS-FS SP-TBN-01-04-00 Rev. Original Page 5 of 8

Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The following is a summary of the expected measurements but subject to change without requiring a revision O to this plan.

1. As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements - HP100:

• Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom of pipe and lengthwise in both directions, with I/ 8 th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get background at same point as HP-100 background.

• All points where beta readings were taken.

• Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

d) Samples:

• Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

• Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-01-02-XXX (starting at 001 )-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance with DP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into 1/2" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis. If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking care to extract chunks from both the inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-01-02-XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01-02-001-C-CBI.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

• Chain of Custody form will be used in accordance with DP-8123 for the samples to be sent to an off-site laboratory.

SDPF-8856.1 YNPS-FSSP-TBN-01-04-00 Rev. Original Page 6 of 8

e) Surface preparation: If the decision is made to perform FSS, the surface scale Will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigationcriteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point measurement location designation:

a) Grid point locations: TBN-01-04-001-FM through TBN-01-04-015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01-04-XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within 1/22 inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP-100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-0 1-02 through TBN-0 1-08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instiuctions I. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of background measurements maybe used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be smallbut distinct.

3. Perform the fixed-point measurements with the E-600/HP- 100 in the scalar mode, collecting I-minute readings within '/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark..

4. Scan 100% of the surface with the HP-100 detector 1/22" from the surface at a rate no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and DPF-8856.1 YNPS-FSSP-TBN-01-04-00 Rev. Original Page 7 of 8 V'

allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA notification point(s)* (y/n) y Specify: QA Signature/Date:

1. Date/time of initial ore-survev briefing

2. Date/time of commencement of background readings

3. Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1. _____________________

2.

Prepared by. Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by- Date_

FSS Project Manager

. DPF-8856.1 Rev. Original Page 8 of 8 YNPS-FSSP-TBN-01-04-00

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 05 Survey Unit Name: Circulating Water Discharge Line - Fourth unit down from Turbine Hall FSSP Number: YNPS-FSSP-TBN-0 1-05-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

.1 Files have been established for survey unit FSS records. l0 1.2 ALARA review has been completed for the survey unit. 171 1.3 The survey unit has been turned over for final status survey. 17 1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. Z]

1.5 Activities conducted within area since turnover for FSS have been reviewed. 71 Based on reviewed information, subsequent walkdown: Z1 not warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. El 1.6 A final classification has been performed. 71 Classification: CLASS 1 7] CLASS 2 El CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01 -02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01-05 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 05 has an internal surface area of 93 M2 .

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of DPF-8856.1 YNPS-FSSP-TBN-0 1-05-00 Rev. Original Page 1 of 8

the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs-i 37 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern:Co-60 Initial characterization data for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-137 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan.

Applicable DCGL: 7200 dpm/100 cm 2 (Co-60 - structure surface) (434 cpm, HP-100)

O DPF-8856.1 YNPS-FSSP-TBN-01-05-00 Rev. Original Page 2 of 8

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs will apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E!; Cs-137: 1.45E3; all in pCi/g.

DCGLem,: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M 2 . The DCGLemc for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

60 Area Factor: AFc°- = 1.6 DCGLemc = AFxDCGL DCGLemc = 11,500 dpm/ 100 cm 2 (Co-60) (694 cpm, HP- 100)

Average

Background:

92.2 cpm (HP-100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP-100)

Standarddeviation: 860 dpm (51.9 cpm, HP- 100)

SurrogateDCGL: No surrogate DCGL will be used.

Investigation Level for fixed-point measurements: 11,500 dpm/100 cm 2 (694 cpm, HP-100) -or- any result that is 7200 dpm/100 cm 2 (434 cpm, HP- 100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 Investigation Level for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad Engineer.

Investigation Level for HP-J00scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-i00 scan: 70 cpm to 120 cpm Radionuclidesfor analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCsfor gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108m 0.25-1.3 Sb-125 1.1-5.5 Cs- 134 0.17-0.86 Cs- 137 0.30-1.5 Eu-152 0.35-1.7 Eu- 154 0.33-1.7 Eu- 155 14-70 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs.

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL values. If it is impractical to achieve those, the 50% DCGL values must be achieved in the laboratory analyses of the DPF-8856.1 YNPS-FSSP-TBN-01-05-00 Rev. Original Page 3 of 8

FSS soil samples.

MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1.1-5.7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP-100 is based on the assumption that all of the activity is 2

Co-60. DCGLGA = 7200 dpm/l00 cmM to achieve less than 10 mrem/y. Using a total efficiency (F x E) of 0.0602 for the HP-100, and its probe area of 100 cm 2, this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP- 100 background: 92.2 cpm, with a standard deviation of 23.0 cpm SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDC for HP-I00 Fixed PointMeasurements:The efficiencies come from YA-REPT-00-015-04.

q = 0.2413 (This is the 271 beta efficiency established for this detector at 0.5 inch) c, = 0.25 (for beta emitters - 0.400MeVm.,. e.g., Co-60) 2 MDCfixed (HP- 100): = 790 dpm/100 cm Scan coverage: HP-100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-I00): 73.2 cpm Scan MDC (HP-I00)(fDCGLEMc):0.149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply to investigations in this unit.

Scan MDCR) (SPA-3): Scan MDCR is calculated from the equation:

MDCR = 1.38vi LTP, equation 5-25 where b = background counts in time t t = time detector is above localized contamination p = surveyor efficiency = 0.5

. DPF-8856.1 Rev. Original Page 4 of 8 YNPS-FSSP-TBN-01-05-00

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t= distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150c/sx l.12s= 168 counts MDCR 1.38- 168_ = 22.58 c/s or 1355 cpm Jp x 1. 12s Scan MDC (fDCGL)(SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = 1.04E-3 Background Determination:Background will be determined in the accordance with DP-8866, using the guidance for "Ambient Background Measurements."

QC checks and measurements: QC checks for the E-600/HP-1 00 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 05 are as shown on the attached map. The unit is 45.62 feet long. Its lower (northern) boundary. is 85.38 feet from the Seal Pit.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type 1I error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test 2 Basis including background reference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

GENERAL INSTRUCTIONS Scoping/Characterization DPF-8856. I YNPS-FSSP-TBN-0 1-05-00 Rev. Original Page 5 of 8

Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The

. following is a summary of the expected measurements but subject to change without requiring a revision to this plan.

1. As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements - HPI00:

a Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom of pipe and lengthwise in both directions, with 1 / 8 th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get background at same point as HP-100 background.

• All points where beta readings were taken.

• Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

d) Samples:

0 Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

• Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-0 I-02-XXX (starting at 001)-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance with DP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into /2" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis. If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking care to extract chunks from both the-inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-01-02-XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01-02-001-C-CB 1.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

• Chain of Custody form will be used in accordance with DP-8123 for the samples to be sent to an off-site laboratory.

SDPF-8856.1 YNPS-FSSP-TBN-0 1-05-00 Rev. Original Page 6 of 8

e) Surface preparation: If the decision is made to perform FSS, the surface scale will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigation criteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point riieasurement location designation:

a) Grid point locations: TBN-01 001 -FM through TBN-01 015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01 XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within 1/2 inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP-100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-01 -02 through TBN-01 -08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions

!. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of.

background measurements may be used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and'the x-axis having positive to the right and negative to the left as you face,the turbine hall. Marks should be small but distinct.

3. Perform the fixed-point measurements with the E-600/HP-100 in the scalar mode, collecting 1-minute readings within 1/2/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

4. Scan 100% of the surface with the HP- 100 detector '/2" from the surface at a rate no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and DPF-8856.1 YNPS-FSSP-TBN-0 1-05-00 Rev. Original Page 7 of 8

allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for. investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the 0 scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA notification point(s)* (yin) .Y.

Specify: QA Signature/Date:

1. Date/time of initial pre-survey briefing

2. Date/time of commencement of hack around readings

2. Date/time of commencement of background readings

3. Date/time of commencement of SPA-3 scan

3. Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

2.

Prepared. by Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager YNPS-FSSP-TBN-0 1-05-00

. Rev. Original DPF-8856.1 Page 8 of 8

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION Survey Area #: TBN-01 Survey Unit #': 06 Survey Unit Name: Circulating Water Discharge Line - Third unit up from Seal Pit FSSP Number: YNPS-FSSP-TBN-01 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

I. 1 Files have been established for survey unit FSS records. I]

1.2 ALARA review has been completed for the survey unit. 10 1.3 The survey unit has been turned over for final status survey. I]

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. []

1.5 Activities conducted within area since turnover for FSS have been reviewed. Zl Based on reviewed information, subsequent walkdown: Ml not warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. El 1.6 A final classification has been performed. 10 Classification: CLASS I Rl CLASS 2 E- CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01 -02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete; lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01 -06 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 06 has an internal surface area of 98 M 2 . It includes the uppermost of the three cooling tower nozzles, which is a 48-inch steel pipe.

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of DPF-8856.1 YNPS-FSSP-TBN-0 1-06-00 Rev. Original Page 1 of 8

background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs-I137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma, spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as

. radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern: Co-60 Initial characterization data for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-137 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan.

DPF-8856.1 YNPS-FSSP-TBN-0. 1-06-00 Rev. Original' Page 2 of 8

Applicable DCGL: 7200 dpm/l100 cm 2 (Co structure surface) (434 cpm, HP-100)

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs will apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E]; Cs-137: 1.45E3; all in pCi/g.

DCGL,,,,: The maximum area for any of the Survey Units in Survey Area TBN-01, is 100 M2 . The DCGLemc for all SurveyUnits is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

Area Factor: AFc- 6 0= 1.6 DCGLemc = AFxDCGL DCGLemc = 11,500 dpm/100 cm2 (Co-60) (694 cpm, HP-100)

Average

Background:

92.2 cpm (HP- 100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP-100)

Standarddeviation: 860 dpm (51.9 cpm, HP- 100)

SurrogateDCGL: No surrogate DCGL will be used.

InvestigationLevel forfixed-point measurements: 11,500 dpm/l00 cm2 (694 cpm, HP-100) -or- any result that is 7200 dpm/! 00 cm2 (434 cpm, HP- 100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 InvestigationLevel for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad Engineer.

InvestigationLevel for HP-100 scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-I00 scan: 70 cpm to 120 cpm Radionuclidesfor-analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCsfor gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108m 0.25-1.3 Sb- 125 1.1-5.5 Cs- 134 0.17-0.86 Cs- 137 0.30-1.5 Eu-152 0.35-1.7 Eu-154 0.33-1.7 Eu-155 14-70 (b) FSS: Any FSS concrete samples willbe analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs.

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL Values. If it is impractical to achieve those, the 50% DCGL values must be achieved in the laboratory analyses of the DPF-8856.1 Rev. Original Page 3 of 8 YNPS-FSSP-TBN-0 1-06-00 0

FSS soil samples.

MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1. 1-5;7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP- 100 is based on the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/100 cm 2 to achieve less than 10 mrem/y. Using a total efficiency (Fi x F-)

of 0.0602 for the HP- 100, and its probe area of 100 cm 2, this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP-100 background: 92.2 cpm, with a standard deviation of 23.0 cpm.

SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDCfor HP-I00 Fixed Point Measurements: The efficiencies come from YA-REPT-00-015-04.

F = 0.2413 (This is the 27r beta efficiency established for this detector at 0.5 inch) a, = 0.25 (for beta emitters 5 0.400MeVmax, e.g,, Co-60) 2 MDCfixed (HP-100): = 790 dpm/100 cm Scan coverage: HP-100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-]00) : 73.2 cpm Scan MDC (HP-I00)(fDCGLpMc): 0.149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply to investigations in this unit.

Scan MDCR) (SPA-3): Scan MDCR is calculated from the equation:

.MDCR = 1 .- 8 x LTP, equation 5-25 where b = background counts in time t t = time detector is above localized contamination p = surveyor efficiency = 0.5 DPF-8856. ! YNPS-FSSP-TBN-0 1-06-00 Rev. Original Page 4 of 8

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t= distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150 c/s x 1.12 s= 168 counts 1.38-v6--

MDCR - 1.38,56.2 = 22.58 c/s or 1355 cpm J7x 1. 12s Scan MDC (fDCGL) (SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = i.04E-3 Background Determination:Background will be determined in the accordance with DP-8866 , using the guidance for "Ambient Background Measurements."

QC checks and measurements: QC checks for the E-600/HP-100 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 06 are as shown on the attached map. The unit is 34.15 feet long in the main pipe. Its lower.(northern) boundary is 51.23 feet from the Seal Pit. It includes the uppermost cooling tower nozzle, which is a 48-inch pipe going off at an angle from the east side of the main pipe. The nozzle is approximately 27 feet long, including a vertical section at the end.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type H error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test E[ Sign Test R1 Basis including background reference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

DPF-8856.1 YNPS-FSSP-TBN-01-06-00 Rev. Original Page 5 of 8

GENERAL INSTRUCTIONS Scoping/Characterization Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The following is a summary of the expected measurements but subject to change without requiring a revision to this plan.

1. As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements - HP 100:

" Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom of pipe and lengthwise in both directions, with I/8th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get background at same point as HP-100 background.

• All points where beta readings were taken.

• Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

d) Samples:

• Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

• Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-0I-02-XXX (starting at 001)-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance with DP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into V2" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis., If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking care to extract chunks from both the inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-01-02-XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01-02-001-C-CBI.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

. DPF-8856.1 Rev. Original Page 6 of 8 YNPS-FSSP-TBN-0 1-06-00

• Chain of Custody form will be used in accordance with DP-8123 for the samples to be sent to an off-site laboratory.

e) Surface preparation: If the decision is made to perform FSS, the surface scale will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigation criteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point measurement location designation:

a) Grid point locations: TBN-01-06-001-FM through TBN-01-06-015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01 XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within /2 inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP-100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-01 -02 through TBN-01 -08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions

1. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of background measurements may be used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be small but distinct.

3. Perform the fixed-point measurements with the E-600/HP-l100 in the scalar mode, collecting I -

minute readings within '/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

DPF-8856.1 YNPS-FSSP-TBN-01-06-00 Rev. Original Page 7 of 8

4. Scan 100% of the surface with the HP-I100 detector '/2" from the surface at a rate no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA notification.point(s)* (y/n) y Specify: QA Signature/Date:

1. Date/time of initial pre-survey briefing

2. Date/time of commencement of background readings

3. Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1.

2.

Prepared by. Date FSS Radiological Engineer Reviewed by. Date FSS Radiological Engineer Approved by Date FSS Project Manager

.DPF-8856.1 Rev. Original YNPS-FSSP-TBN-0 1-06-00 Page 8 of 8

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 07 Survey Unit Name: Circulating Water Discharge Line - Second unit up from Seal Pit FSSP Number: YNPS-FSSP-TBN-01-07-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

.1 Files have been established for survey unit FSS records. 10 1.2 ALARA review has been completed for the survey unit. l]

1.3 The survey unit has been turned over for final status survey. Z 1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. Z]

Based on reviewed information, subsequent walkdown: Z] not warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. El 1.6 A final classification has been performed. Z]

Classification: CLASS 1 [] CLASS 2 El CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01 -02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01 -07 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 07 has an internal surface area of 64 M 2 . It includes the middle of the three cooling tower nozzles, which is a 48-inch steel pipe.

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of DPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 1 of 8

background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs- 137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ* Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as

. radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta measurements on a grid with a random start point.

Radionuclide-of-concern:Co-60 Initial characterization data for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL, Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-137 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan..

SDPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 2 of 8

Applicable DCGL: 7200 dpm/100 cm' (Co structure surface) (434 cpm, HP-100)

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs will apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E1; Cs-137: 1.45E3; all in pCi/g.

DCGLmL: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M 2 . The DCGLemc for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

Area Factor: AFc°-6° = 1.6 DCGLemc = AFxDCGL DCGLemc = 11,500 dpm/100 cm 2 (Co-60) (694 cpm, HP-100)

Average

Background:

92.2 cpm (HP- 100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP- 100)

Standarddeviation: 860 dpm (51.9 cpm, HP- 100)

SurrogateDCGL: No surrogate DCGL will be used.

Investigation Level forfixed-point measurements: 11,500 dpm/100 cm2 (694 cpm, HP-100) -or- any result that is 7200 dpm/1 00 cm 2 (434 cpm, HP-100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 Investigation Level for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad Engineer.

Investigation Level for HP-]00scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-100 scan: 70 cpm to 120 cpm Radionuclidesfor analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCs for gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108m 0.25-1.3 Sb- 125 1.1-5.5 Cs-134 0.17-0.86 Cs-137 0.30-1.5 Eu-152 0.35-1.7 Eu-154 0.33-1.7 Eu-155 14-70 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs. -

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL values. If it is impractical to achieve those, the 50% DCGL values must be achieved in the laboratory analyses of the DPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 3 of 8

FSS soil samples.

MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1.1-5.7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed usingMDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP- 100 is based on .the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/1 00 cm 2 to achieve less than 10 mrem/y. Using a total efficiency (Fi x F-)

of 0.0602 for the HP- 100, and its probe area of 100 cm 2, this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP-100 background: 92.2 cpm, with a standard deviation of 23.0 cpm SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDCfor HP-I00 Fixed PointMeasurements: T'he efficiencies come from YA-REPT-00-015-04.

F = 0.2413 (This is the 27t beta efficiency established for this detector at 0.5 inch)

, = 0.25 (for beta emitters < 0.400MeVmx, e~g., Co-60) 2 MDCfixed (HP- 100): = 790 dpm/100 cm Scan coverage: HP-100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-I00) : 73.2 cpm Scan MDC (HP-I00)(fDCGLpMc): 0.149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply to investigations in this unit.

Scan MDCR) (SPA-3): Scan MDCR is calculated from the equation:

MDCR = I.38t LTP, equation 5-25 4pxt where b = background counts in time t t = time detector is above localized contamination p = surveyor efficiency = 0.5 DPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 4 of 8

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t= distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150c/sx 1.12s= 168counts 1.381-*

MDCR 1.38,[x112 = 22.58 c/s or 1355 cpm

.j x 1.12s Scan MDC (fDCGL) (SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = 1.04E-3 Background Determination:Background will be determined in the accordance with DP-8866 , using the guidance for "Ambient Background Measurements."

QC checks and measurements:QC checks for the E-600/HP-100 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 07 are as shown on the attached map. The unit is 17.4 feet long in the main pipe. Its lower (northern) boundary is 33.83 feet from the Seal Pit. It includes the middle cooling tower nozzle, which is a 48-inch pipe going off at an angle from the east side of the main pipe. The nozzle is approximately 27 feet long, including a vertical section at the end.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey.

(c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type II error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test E Sign Test P1 Basis including background reference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples : 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

DPF-8856.1 YNPS-FSSP-TBN-0 1-07-00 Rev. Original Page 5 of 8

GENERAL INSTRUCTIONS Scoping/Characterization Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The following is a summary of the expected measurements but subject to change without requiring a revision to this plan.

1. As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements - HPI00:

• Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom'of pipe and lengthwise in both directions, with 1/8th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum-priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get background at same point as HP-100 background.

• All points where beta readings were taken.

• Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

d) Samples:

• Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

0 Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-0 I XXX (starting at 001)-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance withDP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into 1/2" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis. If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking care to extract chunks from both the inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-01-02-XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01-02-001-C-CBI.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

SDPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 6,of 8

• Chain of Custody form will be used in accordance with DP-8123 for the samp!es to be sent to an off-site laboratory.

e) Surface preparation: If the decision is made to perform FSS, the surface scale will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre'-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigation criteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point measurement location designation:

a) Grid point locations: TBN-01-07-001-FM through TBN-01-07-015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01 XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 W/HP-100. Detector should be within /2 inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP-l100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-0 1-02 through TBN-01 -08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions I. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of background measurements may be used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be small but distinct.

3. Perform the fixed-point measurements with the E-600/HP-100 in the scalar mode, collecting I-minute readings within '/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

DPF-8856.1 YNPS-FSSP-TBN-01-07-00 Rev. Original Page 7 of 8

4. Scan 100% of the surface with the HP-100 detector 1/22" from the surface at a rate.no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and allow the detector to stabilize. If the reading is more than 694 cpm above the established background, mark the location for investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the investigation level.

NOTIFICATION POINTS QA notification point(s)* (yin) y.

Specify: QA Signature/Date:

1. Date/time of initial nre-survev briefing

2. Date/time of commencement of back around readings readinL-s

2. ate/time of commencement of background

3. Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee.com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1.

2.

Prepared by Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by- Date FSS Project Manager YNPS-FSSP-TBN-01-07-00

. Rev. Original DPF-8856.1 Page 8 of 8

Final Status Survey Planning Worksheet Page 1 of 8 GENERAL SECTION Survey Area #: TBN-0 I Survey Unit #: 08 Survey Unit Name: Circulating Water Discharge Line - Unit closest to the Seal Pit FSSP Number: YNPS-FSSP-TBN-01 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records. I]

1.2 ALARA review has been completed for the survey unit. R1 1.3 The survey unit has been turned over for final status survey. Z]

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

0 1.5 Activities conducted within area since turnover for FSS have been reviewed. R]

Based on reviewed information, subsequent walkdown: R] not warranted H] warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. E OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. FE 1.6 A final classification has been performed. P]

Classification: CLASS I R1 CLASS 2 El CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 Statement of problem:

Survey Area TBN-01 is the turbine hall, which has been demolished except for the slab. The Circulating Water Discharge line, consisting of Survey Units TBN-01-02 through 08, is considered the basement of the turbine hall, even though it extends far beyond the footprint of the building. Because of its size, it is accessible to humans and therefore will be treated as a structure. For most of its length, it has an 84" inside diameter, consisting of concrete, lined with steel, a short section of bare concrete, and some solid steel pipe. The three Survey Units closest to the Seal Pit each include a 48" steel pipe that goes off at an angle, turns vertical and dead-ends at a horizontal blank flange. Units 02 through 08 may be surveyed simultaneously.

Survey Unit TBN-01 -08 consists of the part of the Circulating Water Discharge line shown on the accompanying drawing. Survey Unit 08 has an internal surface area of 100 M2 . It includes the lowermost of the three cooling tower nozzles, which is a 48-inch steel pipe.

The original characterization data consisted of a set of four sediment samples from the Survey Area that were taken in 1998 and found to contain Co-60. The Co-60 is assumed to be a component of the activity released through the licensed discharge pathway, which flowed into the circ water discharge line from the service water line. Additional characterization data were collected in conjunction with the development of this FSS plan and described herein.

The characterization that was done at the time this plan was developed included the collection of DPF-8856.1 YNPS-FSSP-TBN-01-08-00 Rev. Original Page 1 of 8

background data for the HP-100 and SPA-3, biased scans with the HP-100 and SPA-3, and samples of the sediment between the liner and the concrete pipe. The most challenging characterization location was the space between the steel liner and the concrete pipe. Coupons were cut out of the steel liner to allow direct, fixed-point measurements and smear samples of the concrete outside of the liner. The interior and exterior surfaces of the coupons were similarly analyzed. These showed no plant-derived activity. Samples of sediment from this annular space were collected and analyzed by gamma spectroscopy. A sample taken from the end of the liner showed measurable Co-60 and Cs-I137. At 9'7" up the pipe from the end of the liner, no Co-60 was found, although a trace of Cs-I137 was detected.

Since this was less than 10% of the DCGL for soil, this is considered clean. Two more coupons, further up the pipe showed no detectable plant-related radioactivity. All indications are that the liner is intact, that is, no leakage occurred through the liner into the annulus. Therefore, it was demonstrated that, except for the northernmost 9'7" of liner, FSS could be limited to the inside of the liner. The sediment behind the bottom 9'7" will be removed by removing that section of liner and cleaning the concrete pipe directly. A concrete core was taken from the unlined section of the concrete pipe and analyzed by gamma spec and sent for hard to detect analysis.

The problem at hand is to demonstrate that the years of plant operation did not result in an accumulation of plant-related radioactivity, in the structure, that exceeds the release criterion.

The planning team for this effort consists of the Radiation Protection Manager, Circ. Water Discharge Line Project Manager, FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the release criterion?

Alternative actions that may be implemented in this effort are investigation, remediation, or removal as

. radioactive waste.

3.0 Identify the inputs to the decision:

Sample media:

(a) Characterization: sediment samples from the space between the steel liner and the concrete pipe, concrete sample and smear samples. All samples were analyzed by gamma spectroscopy.

The smears .were also analyzed by beta and alpha counting. The concrete core will also be analyzed for all LTP hard-to-detect nuclides.

(b) FSS: Concrete samples as necessary to investigate areas of heightened SPA-3 response.

Otherwise, no samples will be taken.

Types of measurements:

(a) Characterization: judgmental beta scans, judgmental gamma scans, biased fixed beta measurements.

(b) FSS: 100% beta scan, biased gamma scans, fixed beta-measurements on a grid with a random start point.

Radionuclide-of-concern:Co-60 Initial characterization data for the all of the survey units in the pipe consist of four sediment samples, all of which contained Co-60 above DCGL. Additional characterization of the survey units in the pipe continued during the time that this plan was being developed. Cs-I 37 and traces of other radionuclides were found too inconsistently in sediment samples to be able to establish a less conservative nuclide mix. Because of its low beta energy, using Co-60 as the sole nuclide of concern is more conservative than mixes including any other nuclides identified. The design of this plan incorporates the FSS Data Quality Objective (DQO) process in accordance with procedure DP-8856 for the FSS portion of this plan.

SDPF-8856.1 YNPS-FSSP-TBN-0 1-08-00 Rev. Original Page 2 of 8

Applicable DCGL: 7200 dpm/ 100 cm 2 (Co structure surface) (434 cpm, HP- 100)

If concrete samples are analyzed as part any SPA-3 investigations, the Subsurface Partial Structures DCGLs *ill apply. These are: H-3: 1.35E2; C-14: 2.34E3; Co-60:

3.45E3; Ni-63: 6.16E4; Sr-90: 1.39E1; Cs-137: 1.45E3; all in pCi/g.

DCGLenc: The maximum area for any of the Survey Units in Survey Area TBN-01 is 100 M2 . The DCGLemc for all Survey Units is conservatively based upon this number. The number of fixed measurements taken on a grid with a random start point will be 15 for each unit. This meets the DQO requirements for FSS.

Area Factor: AFc'-60 = 1.6 DCGLemc = AFxDCGL DCGLemc = 11,500 dpm/l100 cm 2 (Co-60) (694 cpm, HP- 100)

Average

Background:

92.2 cpm (HP-I100)

Average Fixed Measurement: 1740 dpm assuming all Co-60 (104.9 net cpm, HP- 100)

Standard deviation: 860 dpm (51.9 cpm, HP-100)

Surrogate DCGL: No surrogate DCGL will be used.

Investigation Level forfixed-point measurements: 11,500 dpm/l00 cm 2 (694 cpm, HP-100) -or- any result that is 7200 dpm/100 cm 2 (434 cpm, HP-.100) and differs from the mean of the other results by greater than three standard deviations. This is based on 100% Co-60 Investigation Level for SPA-3 scan: >1.3 times background using an audible signal and earphones.

Investigation will be at the direction of the FSS Rad Engineer.

Investigation Level for HP-]OO scan: 11,500 dpm/100 cm 2 (694 cpm above established background, HP-100)

Expected background rangefor HP-IO0 scan: 70 cpm to 120 cpm Radionuclidesfor analysis:

(a) Characterization: All LTP nuclides with the focus on Co-60.

(b) FSS: Any concrete samples collected will be analyzed for all seven nuclides for which the LTP lists Subsurface Partial Structures DCGLs.

MDCs for gamma analysis of any sediment or concrete samples:

(a). Characterization: Sediment, soil and concrete samples will all be analyzed using the following MDCs, which are based upon soil DCGLs.

Nuclide 10 - 50% DCGL (pCi/g)

Co-60 0.14-0.70 Nb-94 0.25-1.3 Ag-108rm 0.25-1.3 Sb- 125 1.1-5.5 Cs-134 0.17-0.86 Cs-137 0.30-1.5 Eu-152 0.35-1.7 Eu-154 0.33-1.7 Eu-155 14-70 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs.

The desired MDCs in the laboratory analyses of the samples will be the 10% DCGL values. If it is impractical to achieve those, the 50% DCGL values must be achieved in the laboratory analyses of the DPF-8856.1, YNPS-FSSP-TBN-01 00 Rev. Original Page 3 of 8 0

FSS soil samples.

MDCsfor HTD nuclides: In addition to the MDC values listed above, the following MDC values will also be transmitted to the outside laboratory via the chain-of-custody form accompanying any samples:

(a) Characterization:

Nuclide 10 - 50% DCGL (pCi/g)

H-3 13-64 C-14 0.19-0.96 Fe-55 1000-5200 Ni-63 28-140 Sr-90 0.059-0.29 Tc-99 0.48-2.4 Pu-238 1.1-5.7 Pu-239 1.0-5.2 Pu-241 34-170 Am-241 1.0-5.2 Cm-243 1.1-5.5 (b) FSS: Any FSS concrete samples will be analyzed using MDCs that are no greater than 10% of the Subsurface Partial Structures DCGLs Gross Activity DCGL: The DCGL for the HP- 100 is based on the assumption that all of the activity is Co-60. DCGLGA = 7200 dpm/100 cm2 to achieve less than 10 mrem/y. Using a total efficiency (i.x E) of 0.0602 for the HP- 100, and its probe area of 100 cm2 , this comes to 434 cpm.

Background:

Based upon characterization data collected using Yankee Atomic Electric Company Sample Plan, Survey Location: Circulating Water Discharge Pipe, prepared by Dann Smith, dated 4/28/05.

HP-100 background: 92.2 cpm, with a standard deviation of 23.0 cpm SPA-3: 9000 cpm (approximated from limited data)

Efficiencies and MDCfor HP-IO0 Fixed Point Measurements:The efficiencies come from YA-REPT-00-015-04.

E = 0.2413 (This is the 27r beta efficiency established for this detector at 0.5 inch)

E, = 0.25 (for beta emitters < 0.400MeVmax, e.g., Co-60) 2 MDCflxed (HP- 100): = 790 dpm/100 cm Scan coverage: HP-100 scans will be performed over the entire inside surface of the discharge line.

SPA-3 scans will be biased as described in the General Instructions section.

Scan MDCR (HP-100): 73.2 cpm Scan MDC (HP-IOO)(fDCGLpMc): 0. 149 Note: MDCR/MDC values for the SPA-3 are not required when it is used as an investigation tool because this is over and above LTP requirements. The values calculated below assume distributed contamination, which may not apply.to investigations in this unit.

Scan MDCR) (SPA-3): Scan MDCR is calculated from the equation:

MDCR = 138,1 LTP, equation 5-25 17xt where b = background counts in time t t =time detector is above localized contamination p = surveyor efficiency = 0.5

. DPF-8856.1 Rev. Original Page 4 of 8 YNPS-FSSP-TBN-0 1-08-00

distance across contaminated area = 56 cm scan velocity = 50 cm/s BKG count rate 9000 c/m or 150 c/s (from characterization data) t= distance/scan velocity = 56 cm/50 cm/s = 1.12 s b= 150c/sx l.12s= 168counts 1.38 168 MDCR- 1.3 1s = 22.58 c/s or 1355 cpm l xl1. 12s Scan MDC (fDCGL) (SPA-3, concrete basement): MDC is calculated by dividing the MDCR by the efficiency determined in YA-REPT-00-015-04 for the SPA-3 with Co-60:

MDC = 1355 cpm/379 cpm/pCi/g = 3.58 pCi/g MDC(fDCGL) = 3.58/3450 = 1.04E-3 BackgroundDetermination:Background will be determined in the accordance with DP-8866 , using the guidance for "Ambient Background Measurements.'"

QC checks and measurements: QC checks for the E-600/HP-1 00 will be performed in accordance with DP-8504. QC checks for the E-600/SPA-3 will be performed in accordance with DP-8540. No split samples will be collected because samples are part of characterization or possible SPA-3 investigation.

4.0 Define the boundaries of the survey:

Boundaries of Survey Unit 08 are as shown on the attached map. The unit is 33.83 feet long in the main pipe. Its lower (northern) boundary is at the end of the pipe, where it enters the Seal Pit. It includes the lowermost cooling tower nozzle, which is a 48-inch pipe going off at an angle from the east side of the main pipe. The nozzle is approximately 27 feet long, including a vertical section at the end.

5.0 Develop a decision rule:

(a) If all the fixed measurements, including any investigation measurements resulting from scanning, show that the surface concentrations of radionuclides are below the average background plus the DCGL, reject the null hypothesis (i.e., the Survey Unit meets the release criterion).

(b) If the investigation levels are exceeded on any fixed measurement, perform an investigation survey, (c) If the average of the fixed measurements exceeds the DCGL, then accept the null hypothesis (i.e., the Survey Unit fails to meet the release criterion).

6.0 Specify tolerable limits on decision errors:

Null hypothesis: Residual plant-related radioactivity in the Survey Unit exceeds the release criterion.

Probabilityof type I error: 0.05 Probabilityof type II error: 0.05 LBGR: 3600 dpm 7.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test W]

Basis including backgroundreference location: The average, ambient background, determined in accordance with DP-8866, will be subtracted from the fixed-point measurements.

Number of samples :- 15 measurements on the grid established with a random start point. Biased measurements may be taken, as directed by the FSS Rad Engineer.

DPF-8856.1 YNPS-FSSP-TBN-01-08-00 Rev. Original Page 5 of 8

GENERAL INSTRUCTIONS Scoping/Characterization Note: A detailed Scoping/Characterization plan has been written for this phase of the project. The following is a summary of the expected measurements but subject to change without requiring a revision to this plan.

1. As soon as the space is accessible, perform the following scoping/characterization activities:

a) Beta scanning/fixed-point measurements - HP100:

• Get a background measurement, consisting of at least six measurements at a single, central location: detector aimed at walls, top, bottom of pipe and lengthwise in both directions, with 1 18 th inch Lucite over the detector.

• Scan known openings: service water discharge inlet area, vacuum priming line openings

• Scan selected points along bottom centerline, especially near welds, bends, other discontinuities, the section of bare concrete with no liner and any targets of opportunity that present themselves.

• Take fixed point, one-minute scalar measurements at several locations, especially at any places with upscale indications found by scanning, after scraping any scale off the surface that would interfere with the detector.

b) SPA-3:

• Get background at same point as HP-100 background.

• All points where beta readings were taken.

• Walking the length of the pipe with the probe - 3" above bottom centerline, no greater than 0.5 meter/second noting elevated readings.

c) Select locations for removal of the liner on the basis of the SPA-3 results or other bases. Have a section of liner, approximately 12" by 12" cut, removed and bagged at each of these locations.

It is expected that three such sections will be sufficient.

O d) Samples:

• Smears at points of interest (locations of fixed point measurements and under liner).

Count these in a gas flow proportional counter for both alpha and beta emitters and also with a gamma spectroscopy system.

• Sediment and scale samples, one-liter Marinelli, 1-4 samples, depending upon amount of sediment. Show the sampling locations on the survey map and assign sample numbers TBN-0 I-02-XXX (starting at 001)-C-SD (sediment).

• Concrete sample: at least one from the unlined section of pipe. Collect a core sample in accordance with DP-8121 and bag it immediately to minimize the exchange of tritium with the atmosphere. This core should penetrate at least one inch, but not through the full thickness of the pipe. Through penetration could be expected to cause an unmanageable problem with ground water. Slice each core into 1/22" slices, mark each slice with an arrow directed at the inside, label them and seal them in small bags.

Analyze these slices by gamma spectroscopy in-house and send them to the off-site lab for tritium analysis. If it is impractical to core-bore, concrete samples may be collected using a hammer and chisel, taking.care to extract chunks from both the inner and outer surfaces, bagging and labeling them accordingly. Use the following numbering system for concrete samples: TBN-0I XXX (starting with the next sequential number)-

C(for characterization) -CBN (for core-bore, Nth slice starting inside). A typical sample number would be TBN-01 001 -C-CB 1.

• All concrete and soil samples will be received and prepared in accordance with DP-8813. Any samples intended for tritium analysis should not be dried.

. DPF-8856.1 Rev. Original Page 6 of 8 YNPS-FSSP-TBN-0 1-08-00

• Chain of Custody form will be used in accordance with DP-8123. for the samples to be sent to an off-site laboratory.

e) Surface preparation: If the decision is made to perform FSS, the surface scale will have to be scraped off and all scrapings and sediment removed to facilitate the 100% scan.

Final Status Survey

2. Notify QA of date and time of the pre-survey briefing, commencement of background measurements, fixed-point measurements, scanning and any other scheduled activities subject to QA notification.

3. Mark the grid locations as described in Specific Instruction 2.

4. Walk the length of the pipe with a SPA-3 probe within 3" of the bottom centerline, no greater than 0.5 meter/second noting elevated readings. Scan the middle cooling tower nozzle in the same way with the SPA-3. Scan the bottom part of the 84" pipe in the unlined, concrete section, using a serpentine motion, in two bands, one on either side of the centerline. Make at least three passes on each linear meter, again at 0.5 meter/second. Mark any locations that are reproducibly above background on the pipe and show the approximate location and reading on the survey map. The FSS Rad Engineer will determine how to investigate any areas found above the investigation criteria.

5. Take 15 fixed-point measurements with the E-600/HP-100 at the grid locations indicated on the map, in addition to any biased measurements that may be requested by the FSS Rad Engineer.

6. Fixed point measurement location designation:

a) Grid point locations: TBN-01-08-001-FM through TBN-01-08-015-FM or as designated on the survey map.

b) Biased fixed measurement locations: Continuing the pattern TBN-01 XXX-FM, with the next sequential number in place of the XXX.

7. Scan 100% of the interior surface with an E-600 w/HP-100. Detector should be within /2 inch of the surface.

8. Survey instrument: Operation and source checking of the E-600 w/HP-100 will be in accordance with DP-8504. The instrument response checks shall be performed before issue and after use.

9. The job hazards associated with the FSS in the Survey Unit are addressed in the accompanying JHA for TBN-01 -02 through TBN-01 -08.

10. All personnel participating in this survey shall be trained in accordance with DP-8868.

Specific Instructions

1. Collect the ambient background readings at the locations indicated on the survey map in accordance with DP-8866. With the E-600/HP-100 in the scalar mode and covered with a 1/8-inch Lucite shield, direct the probe up, down, left, right, towards the turbine hall and towards the seal pit for a set of six, one-minute measurements at each of the four locations shown on the attached maps. One set of background measurements may be used for all seven units in the Circulating Water Discharge line, at the discretion of the FSS Rad Engineer.

2. Mark the grid locations for the fixed-point measurements according to the coordinates shown on the map. The coordinates are set up so that the y-axis runs along the bottom centerline of the 84" line, with zero generally being at the end closer to the seal pit and the x-axis having positive to the right and negative to the left as you face the turbine hall. Marks should be small but distinct.

3. Perform the fixed-point measurements with the E-600/HP-100 in the scalar mode, collecting 1-minute readings within '/2 inch of the surface. Even if the data is logged in the instrument, manually record each reading. At each grid location, set the probe against the surface just off the mark so that the material used to make the mark (e.g., paint) does not provide any shielding. To do this consistently, turn the probe so that the area counted is "down the pipe" from the mark.

DPF-8856.1 YNPS-FSSP-TBN-01-08-00 Rev. Original Page 7 of 8

4. Scan 100% of the surface with the HP- 100 detector 1/2" from the surface at a rate no greater than 2" per second, listening for an increased count rate using earphones. Pause at any upscale reading and allow the detector to stabilize. If the reading is more than694 cpm above the established background, mark the location for investigation and log the finding.

5. Investigate any locations marked during scanning by taking a one-minute fixed measurement, in the scalar mode, and logging the results, using the next consecutive sample location number and appending the letter "I" to the end.

6. The FSS Rad Engineer will investigate any fixed measurements that exceed the .investigation level.

NOTIFICATION POINTS QA notification point(s)* (y/n) y Specify: QA Signature/Date:

1. Date/time of initial pre-survev briefing

2. Date/time of commencement of background readings

3. Date/time of commencement of SPA-3 scan

4. Date/time of commencement of fixed measurements

5. Date/time of first scan measurements - E600/HP- 100 E-mail notification to trudeau@yankee.com with a copy to calsyn@yankee~com satisfies this step*

FSI point(s) (y/n) n Specify: Field Supervisor Signature/Date:

1.

2.

Prepared by- Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager YNPS-FSSP-TBN-01-08-00

. Rev. Original DPF-8856.1 Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 09 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-01 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted R warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown.

1.6 A final classification has been performed. [

Classification: CLASS I M CLASS 2 R CLASS 3 F]

DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

" Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

" Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

TBN-01 -09 is a building surface survey unit of 93 m2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-09-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS and FSSManager.

• Proect 2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed 'are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-1 00C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw and DCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

a DCGLw: 6.3E+03 dpm/lOOcm 2 at 8.73 mrem/y.

0 DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/1 00cm 2 .

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-0 15-04 provides instrument efficiency factors (ri) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

0 Gross activity DCGLw (HP-100C): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M 2 . Per LTP App. 6S, the next highest Area of Source = 4 M2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-100C)"

0 smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLEMC: Based on a contaminated source area of I m 2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than 1 m2.

. DPF-8856.

Rev. 2 YNPS-FSSP-TBN-01-09-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Level for ISOCS measurements DCGLw DCGLEMc (ISOCS Investigation Level based on source area = ISOCS (Based on Im2) *source area = Im2, 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2 ) at (dpm/g00 cm2 (dpmBld00 cm 8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 l.iE+04 InvestigationLevel ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-0l18-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a I m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the I m2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/100 cm 2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/lOOcm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/OOcm2 . The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMCo If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

Investigation Level Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMC (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i~e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCsfor ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMC. Refer to Table I above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-100Cis a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856. 1 YNPS-FSSP-TBN-01-09-00, Page 3 of 8 Rev. 2

N.

Final Status Survey Planning Worksheet SPA-3 DCGL:EMC: Refer to Attachment 2 for the following, which calculates:

" The SPA-3 Area Factors for Co-60 and Cs- 137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/1OOcm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs-137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/ 00cm2.

QC checks andmeasurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-8871.

Define the boundaries of the survey:

TBN-01 -09 is bounded by survey area SVC-01 to the east, NOL-01 and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01 -09 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.,

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (H 0), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (f8) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test Z Background to be applied: media-specific E] ambient R] none If WRS test is specified, record background reference area location:

Basis includingbackground reference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-09-00, Page 4 of 8

Final Status Survey Planning Worksheet INSTRUCTIONS

1. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and. OOL-02 are addressed in the accompanying JHA..

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-09-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01 123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-09-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-09-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. TBN-01-09-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-09-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-01 019-F-FM is to be recounted, use TBN-01 019-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01 013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-09-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01 013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-09-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect I-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01 019-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN-01-09-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

. 6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-887 1. Resolve flags encountered prior to survey.

6.2. Lay out'the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMc.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

@s 9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600/HP IOOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OOC. If the measurement confirms that the original measurement was.in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN-0 1-09-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP- IOOC.

DPF-8856.1 YNPS-FSSP-TBN-01-09-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet Worksheet Status Survey Final Planning NOTIFICATION POINTS QA notification* point(s) (y/n) YES

( I)Date/time of initial pre-survey briefing QA Signature/Date: (I)

(2)Date/time of daily pre-shift briefing

/ QA Signature/Date: (2)_

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)

/

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

FSI point(s) (y/n) NO (1)

(2)

• Voice mail or email notification tO Trudeau@yan keerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by .Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-09-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 10 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-0 I-10-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted nI warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. LI OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. [

1.6 A final classification has been performed. Z Classification: CLASS I M CLASS 2 CLASS 3 El DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

• Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

" Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

TBN-01 -10 is a building surface survey unit of 91 M2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-0 1-10-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Wroject Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-1OOC probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw and DCGLp.Mc: A single nuclide Co-60 is used in these calculations for conservatism.

9 DCGLw : 6.3E+03 dpm/100cm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to.Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in6.3E+03 dpm/1OOcm2.

0 The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-01 5-04 provides instrument efficiency factors (i) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

6 Gross activity DCGLw (HP-IOOC): smooth surface 379 cpm, irregular surface 232 cpm.

Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M2 . Per LTP App. 6S, the next highest Area of Source = 4 M 2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLpMc (HP-IOOC):

0 smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLEMc: Based on a contaminated source area of 1 m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-018-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I m2.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0I 00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on Im2) source area = Im 2, 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpm/ cm 2) (dpml cm 2 )

8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 1.1E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-0l18-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a 1m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the Im2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/IOO cm 2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/IOOcm 2 (Co-60) and 1.6E+04 dpm/1OOcm 2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/10 0cm 2. The ISOCS Investigation Level is conservatively calculated for a 1 m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMC.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

InvestigationLevel Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

InvestigationLevel SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCs for ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Table I above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-100C: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMC): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856. I YNPS-FSSP-TBN-01-10-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs-I137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/l 00cm 2 (Co-60) and 1.6E+04 dpm/1 00cm 2 (Cs- 137).

" Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm2.2 QC checks andmeasurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-8871.

Define the boundaries of the survey:

TBN-0 1-10 is bounded by survey area SVC-0 I to the east and other TBN-01 survey units to the north, south and west.

The survey of TBN-0I -10 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria').

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (fl) error: 0.05 LBGR: 3123 dpm/100 cm2 6.0 Optimize Design:

Type of statistical test: WRS Test E] Sign Test Z Background to be applied: media-specific E] ambient LI none M If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-10-00, Page 4 of 8

Final Status Survey Planning Worksheet INSTRUCTIONS I. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification. W

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Areas OOL-02 and TBN-0I are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3. I. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-10-100-F-G and increment as needed.

.4.1.2. For investigations, append terms as. follows.

4.1.2.1. For example, if ISOCS point TBN-01-10-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-10-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-0 1-10-123-F-I-SC-00 I for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-10-123-F-I-FM-001 for the first fixed.point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-0I-10-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-0l-l0-012-F-FM is to be recounted, use TBN-01-10-012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3. 1. For example, if fixed point measurement TBN-01 013-F-FM is to be investigated:

4.2.3. 1. 1. Use TBN-0I-10-013-F-I-G-00I for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-0I-10-013-F-I-SC-00I for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01 01 3-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect 1-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5. 1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-10-005-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either priorto or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN-01-10-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

. 6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance With DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-8871. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of I .3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the.ISOCS detector directly above each marker 2m from the surface to be. scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMc.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at .approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600/HP 1OOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-100C. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 19000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN 10-00, Page 6 of 8

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP- IOOC.

DPF-8856. I YNPS-FSSP-TBN-0 1-10-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (1)Date/time of initial pre-survey briefing

/ QA Signature/Date: (I)-

(2)Date/time of daily pre-shift briefing QA Signature/Date: (2)_

(3)Date/time of commencement of HP- 100 measurements QA Signature/Date: (3)

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

/

FSI point(s) (y/n) NO (I)

/

(2)

/

1.

• Voice mail or email notification to Trudeau@yan keerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by- Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-10-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 11 Survey Unit Name: Turbine Building Survey.Unit I - building surface FSSP Number: YNPS-FSSP-TBN 11 -00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. [

1.6 A final classification has been performed. [

I Classification: CLASS I M] CLASS 2 E] CLASS 3 F1 DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-0I has been reclassified to Class I. The reasons are due to the contaminating events listed above.

TBN-01-11 is a building surface survey unit of 100 M2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-1 1-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS roject Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information thatwill be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-100C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw andDCGLE.Mc: A single nuclide Co-60 is used in these calculations for conservatism.

• DCGLw : 6.3E+03 dpm/lOOcm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/1 00cm 2.

0 The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-01 5-04 provides instrument efficiency factors (Ei) for various source-to-detector distances. Thus efficiencies (HP-I 00C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-100C): smooth surface 379 cpm, irregular surface 232 cpm.

• *Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points.= 0.433L 2 = 2.5 M2 . Per LTP App. 6S, the next highest Area of Source = 4 M2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMc (HP-IOOC):.

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLpMc: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-018-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I m2

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0I 00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on I m2) source area = 1m2, 2m 90d collimated)

BldgSurface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpml cm) (dpm/100 cm 2 )

8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 l.7E+05 1.1E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMC as shown by Table I above (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a I m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the 1m 2 area at the edge of the field of view. Thus the'calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/100 cm 22.

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpmi/OOcm2 (Co-60) and 1.6E+04 dpm/1OOcm2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm 2. The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMC.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

Investigation Level Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCsfor ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Table 1 above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 7 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMC): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN-0 1-11-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs- 137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 mR calculated source area) for this survey unit.

• The SPA-3 DCGLEMc of 5.3E+04 dpm/1OOcm 2 (Co-60) and 1.6E+04 dpm/IOOcm 2 (Cs-137).

" Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm 2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 i.

Define the boundaries of the survey:

TBN II is bounded by survey area SVC-0I to the east, NOL-01 and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01-1 I will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete ýlab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (fl) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test Z Background to be applied: media-specific El ambient 0 none E If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

DPF-8856.1 YNPS-FSSP-TBN 1-00, Page 4 of 8 Rev. 2

Final Status Survey Planning Worksheet INSTRUCTIONS

1. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-1 1-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2. 1. For example, if ISOCS point TBN-01-1 1-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-1 1-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-1 1-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-1 1-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-11-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-01-1 1-012-F-FM is to be recounted, use TBN-01-11-012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01 01 3-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-1 1-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-0 1-11-01 3-F-I-SC-00 I for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-0I-1 I-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect 1-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-1 1-013-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN 11-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-887 1. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMc.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined areain square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600/HP IOOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP- 1OOC. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN-0I-I 1-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP-I OOC.

DPF-8856.1 YNPS-FSSP-TBN-01-1 1-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (I)Date/time of initial pre-survey briefing

/ QA Signature/Date: (1)

(2)Date/time of daily pre-shift briefing

/ QA Signature/Date: (2)

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)

/

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)

/

FSI point(s) (y/n) NO (I)

/________________

(2)

/

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by. Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0I-I 1-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 1 Survey Unit #: 12 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-0I 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses andcompletion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey. z 1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Mnot warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. M 1.6 A final classification has been performed. [

Classification: CLASS I M CLASS 2 F] CLASS 3 nI DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

• Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

" Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class I. The reasons are due to the contaminating events listed above.

TBN-01-12 is a building surface survey unit of 100 M2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN 12-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-100C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw andDCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

• DCGLw: 6.3E+03 dpm/lOOcm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),.,

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/100cm 2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPTý00-01 5-04 provides instrument efficiency factors (Ei) for various source-to-detector distances. Thus.

efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-I 00C): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M 2 . Per LTP App. 6S, the next highest Area of Source = 4 M 2 , yielding an AF =. 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-100C):

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLEMc: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I M2.

• DPF-8856.1 YNPS-FSSP-TBN-01-12-00, Page 2 of 8 Rev. 2

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on Im2) source area = Im 2, 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/l00 cm 2) at (dpm/l10 cm 2 (dpm!100 cm 2 )

8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs-137 2.2E+04 1.7E+05 1.1E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-0 18-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a tm 2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the I m2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm ' investigation level for Co-60 is sensitive enough to detect the DCGLEMc of 4.6E+04 dpm/100 cm2.

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/1OOcm2 (Co-60) and 1.6E+04 dpm/100cm2 (Cs-I137) yields a gross activity SPA-3 DCGLEMc of 1.7E+04 dpm/1OOcm 2 . The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMC.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

Investigation Level DirectMeasurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMC (i.e. smooth surface 910 cpm; irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag- 108m, Sb- 125, Cs- 134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCs for ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Table I above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP- IOOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN-0I 00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

" The SPA-3 Area Factors for Co-60 and Cs-137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/100cm2 (Co-60) and 1.6E+04 dpm/IOOcm 2 (Cs-137).

• Finally yielding a gross activity SPA-3 DCGLEMc of 1.7E+04 dpm/I00cm2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 I.

Define the boundaries of the survey:

TBN-01-12 is surrounded by other TBN-01 and OOL-02 survey units. The survey of TBN-01-12 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 10.0% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

• d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (/8) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test M Background to be applied: media-specific El ambient E] none M If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN 12-00, Page 4 of 8

Final Status Survey Planning Worksheet-INSTRUCTIONS

1. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification. W

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-12-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01-12-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-12-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-12-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-12-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-12-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-01 012-F-FM is to be recounted, use TBN-01 012-F-FM-RC.

• 4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-1 2-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-12-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-12-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-12-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect 1-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-12-020-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN-01-12-00, Page 5 of 8 Rev. 2

Final St*atus Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-887 1, with QC checks performed once per shift in accordance with DP-8869 and DP-887 1. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary such that it is perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclidesand compare values against the DCGLEMC.

7. The E-600 will be used as follows.

7.1. Operated in accordance with DP-8535.

7.2. Perform QC checks in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. if an ISOCS measurement needs to be investigated, perform it as follows.

9. 1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with

. audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600/HP I O0C.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OOC. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface and the map the outline (boundary) of areas with elevated activity.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

U DPF-8856.1 YNPS-FSSP-TBN-01-12-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP-I OOC.

DPF-8856.1 YNPS-FSSP-TBN-0I 00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (I )Date/time of initial pre-survey briefing L QA Signature/Date: (I)-

(2)Date/time of daily pre-shift briefing QA Signature/Date: (2)_

(3)Date/time of commencement of HP-I100 measurements QA Signature/Date: (3)_

/_ _

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

/

FSI point(s) (y/n) NO (I)

/

(2)

/

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by- Date FSS Radiological Engineer Reviewed by- Date FSS Radiological Engineer Approved by- Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-12-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 13 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-01 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1. 1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted DI warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. [

1.6 A final classification has been performed. Z Classification: CLASS 1 E CLASS 2 F CLASS 3 LI DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

• Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

• Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

TBN-01-13 is a building surface survey unit of 100 M2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-13-00, Page I of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS WProject Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-100C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

DirectMeasurements DCGL and DCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

• DCGLw: 6.3E+03 dpm/1OOcm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-0l: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/1 00cm 2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-0 15-04 provides instrument efficiency factors (Ei) for various source-to-detector distances. Thus efficiencies (HP-IOOC) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-IOOC): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 m2. Per LTP App. 6S, the next highest Area of Source = 4 M 2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLRMc (HP-1OOC):

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLEMC: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). If necessary, the DCGLEMc will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I M2.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN 13-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Levelfor ISOCS measurements DCGLw DCGLEMc (ISOCS Investigation Level based on source area = ISOCS (Based on Im2 ) source area = 1m2, 2m 90d collimated)

Bldg Surface NuBildgucme a Bldg Surface Bldg Surface Nu clid e (d p m/ 100 c m 2) a t d m1 0 C M )( p / 00 M2 2

8.73 mrem/y (dpmn/10 cm ) (dpm/100 cm 2)

Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 l. I E+04 InvestigationLevel ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a I m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m 2 for a 2m height above the surface) to the I m2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/l100 cm 2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/riOOcm 2 (Co-60) and 1.6E+04 dpm/1OOcm 2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dprfi/nOOcm 2. The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMCo If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

InvestigationLevel Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCs for ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Tablel above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-JOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN-01-13-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs-I137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 mz calculated source area) for this survey unit.

" The SPA-3 DCGLEMC of 5.3E+04 dpm/l 00cm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs-137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm 2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-8871.

Define the boundaries of the survey:

TBN-01-13 is bounded by survey area OOL-02 to the north and other TBN-0I survey units to the south, east and west.

The survey of TBN-01 -13 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceedsthe release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type 11 (8) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS. Test El Sign Test 0 Background to be applied: media-specific El ambient El none M If WRS test is specified, record background reference area location:

Basis including background reference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start joint.

. DPF-8856. 1 Rev. 2 YNPS-FSSP-TBN-0I 00, Page 4 of 8

Final Status Survey Planning Worksheet INSTRUCTIONS

1. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2. 1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4. 1. ISOCS 4.1.1. Start with TBN-01-13-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01 123-F-G is to be investigated:

4.1.2.1.1. Use TBN-0 1-13-I 123-F-I-G-00 I for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-13-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-13-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-13-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2. 1. If fixed point measurement TBN-01 012-F-FM is to be recounted, use TBN-01 012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3. 1. For example, if fixed point measurement TBN-01 013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-0I-13-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-13-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-13-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect I-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-13-015-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN 13-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the

• ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-887 1, with QC checks performed once per shift in accordance with DP-8869 and DP-8871. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum.of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMC.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600/HP IOOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OOC. If the measurement confirms that the Original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN 13-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600 with the HP- IOOC.

DPF-8856. I YNPS-FSSP-TBN-01-13-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (I )Date/time of initial pre-survey briefing QA Signature/Date: (1)

(2)Date/time of daily pre-shift briefing

/ QA Signature/Date: (2)

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)_

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

FSI point(s) (y/n) NO (i)

/_ _

(2)

./

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

W Prepared by- Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Dfa te FSS Project .Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-13-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 14 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-0 I- 14-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El

-OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. [

1.6 A final classification has been performed. [

Classification: CLASS 1 El CLASS 2 LI CLASS 3 L]

DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

• Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

• Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

" These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class I. The reasons are due to the contaminating events listed above.

TBN-01-14 is a building surface survey unit of 89 M2.

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-14-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Jroject Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediati~n and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-1OOC probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw and DCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

" DCGLw : 6.3E+03 dpm/1OOcm2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/1 00cm 2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-015-04 provides instrument efficiency factors (e,) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

" Gross activity DCGLw (HP-1OOC): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M 2 . Per LTP App. 6S, the next highest Area of Source = 4 MR, yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-IOOC):

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLEMc: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). If necessary, the DCGLEMc will be recalculated if an actual area 2

of elevated concentration is discovered with a source area greater than I m2

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-14-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEmc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on Im2 ) source area = Im 2, 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpml cm 2 ) (dpm/lOO cm 2 )

8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 1.1 E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-0l18-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMc associated with a I m 2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the I m2 area at the edge of the field of view. Thus the calculated2 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/l 00 cm .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/1 00cm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs- 137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/I 00cm 2. The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMc.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

Investigation Level DirectMeasurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

InvestigationLevel SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis:All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCsforISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Table I above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856. I YNPS-FSSP-TBN-0I-14-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

" The SPA-3 Area Factors for Co-60 and Cs-137,at the LTP App. 6Q Area ofSource of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

" The SPA-3 DCGLEMC of 5.3E+04 dpm/1 00cm 2 (Co-60) and 1.6E+04 dpm/1 00cm 2 (Cs- 137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 I.

Define the boundaries of the survey:

TBN-01-14 is bounded by survey areas NOL-01 and 06 to the southand other TBN-01 survey units to the north, east and west. The survey of TBN-0I -14 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct meas~urement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey: This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (,8) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test El Sign Test M Background to be applied: media-specific E] ambient R none M If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

O. DPF-8856.1 YNPS-FSSP-TBN-01-14-00, Page 4 Of 8 Rev. 2

Final Status Survey Planning Worksheet INSTRUCTIONS

1. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.W

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-14-100-F-G and .increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01 123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-14-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-0I-I4-123-F-I-SCý001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-01-14-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-14-001F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point. measurement TBN-01 016-F-FM is to be recounted, use TBN-01 016-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-14-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-14-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-14-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-14-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect I-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01 016-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample lo~ations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-.8856.1 YNPS-FSSP-TBN-01-14-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the

• ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-887 I. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMC.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of theelevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600/HP I OOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

.. 10.1.1. Perform a re-survey of the measurement location with the HP-100C. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2. 1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN-0 I- 14-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP- IOOC.

DPF-8856.1 YNPS-FSSP-TBN-0I-14-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (I )Date/time of initial pre-survey briefing

/ QA Signature/Date: (1)

(2)Date/time of daily pre-shift briefing QA Signature/Date: (2)

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)

/

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)

/

FSI point(s) (y/n) NO (I)

/

(2)

/

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by. Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-14-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 15 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-01 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

L. Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file. E 1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted L] warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. LI OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. N 1.6 A final classification has been performed. E Classification: CLASS I E CLASS 2 E] CLASS 3 MI DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

• Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

" Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

TBN-01-15 is a building surface survey unit of 100 m2 .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-15-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation,remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-IOOC probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

Direct Measurements DCGLw and DCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

S DCGLw : 6.3E+03 dpm/100cm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/IOOcm 2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as I". YA-REPT-00-015-04 provides instrument efficiency factors (ci) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-IOOC): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L 2 = 2.5 M2 . Per LTP App. 6S, the next highest Area of Source = 4 M2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-IOOC):

o smooth surface 910.cpm, irregular surface 562 cpm.

ISOCS DCGLM:mc- Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-"

REPT-00-018-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I M2.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-15-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLb:Mc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on I n2 ) source area = I m 2, 2m 90d collimated)

Bldg Surface 2 Bldg Surface Bldg Surface2 Nuclide (dpm/i100 cm ) at (dpml cm 2 ) (dpml cm )

8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs-137 2.2E+04 1.7E+05 1.1E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a 1m2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the lm 2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/100 cm2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/1O0cm2 (Co-60) and 1.6E+04 dpm/IOOcm 2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/10r0cm 2. The ISOCS Investigation Level is conservatively calculated for a'! m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMCo If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

InvestigationLevel Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMC (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

InvestigationLevel SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCs for ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMC. Refer to Table 1 above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-100C is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMC): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN-01-15-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs-137 at the LTP App. 6Q Area of Source of 4 mR (next highest relative to 2.5 m 2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/l 00cm 2 (Co-60) and 1.6E+04 dpm/lOOcm 2 (Cs-I137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/1 00cm 2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-8871.

Define the boundaries of the survey:

TBN-01-15 is bounded by survey area SVC-0i to the east, NOL-0I and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01 -15 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a. decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (H0), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (fl) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test [] Sign Test [

Background to be applied: media-specific [] ambient E] none E If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-15-00, Page 4 of 8

Final Status Survey Planning Worksheet INSTRUCTIONS I. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-15-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2. 1. For example, if ISOCS point TBN-01-15-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-15-123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-15-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. Use TBN-0I-I5-123-F-I-FM-00I for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-15-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2. 1. If fixed point measurement TBN-01-15-012-F-FM is to be recounted, use TBN-01-15-012"-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-15-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-15-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-15-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-15-013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect 1-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-15-013-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN 15-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

. 6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-887 I. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle .the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMC.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with

.audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600/HP IOOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OC. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

• DPF-8856.1 YNPS-FSSP-TBN-01-15-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600 with the HP-IOOC.

DPF-8856.1 YNPS-FSSP-TBN-01-15-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (l)Date/time of.initial pre-survey briefing

/ QA Signature/Date: (I)-

(2)Date/time of daily pre-shift briefing QA Signature/Date: (2)_

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)_

/

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)_

/

FSI point(s) (y/n) NO (1)

/

(2)

-I

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by- Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-15-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey Area #: TBN-01 Survey Unit #: 16 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-0 I 00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey'Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Onot warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. El OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. [

1.6 A final classification has been performed. [

Classification: CLASS 1 0 CLASS 2 El CLASS 3 L]

DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

" Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

• Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This includes the SFP excavation and the sweeper truck residues.

• These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class I. The reasons are due to the contaminating events listed above.

2 TBN-01-16 is a building surface survey unit of 72 M .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 YNPS-FSSP-TBN-01-16-00, Page 1 of 8 Rev. 2

Final Status Survey Planning Worksheet The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs.to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-I OOC probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many of the following calculations will be based on Co-60 for conservatism.

DirectMeasurements DCGLw and DCGLEMc: A. single nuclide Co-60 is used in these calculations for conservatism.

0 DCGLw : 6.3E+03 dpm/1OOcm 2 at 8.73 mrem/y.

0 DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/IOOcm2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as 1". YA-REPT-00-015-04 provides instrument efficiency factors (ei) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-100C): snrooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L2 = 2.5 m'. Per LTP App. 6S, the next highest Area of Source = 4 M 2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-100C):

o smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGL-Mc: Based on a contaminated source area of I m2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-018-05; see Attachment 4 for the calculations). If necessary, the DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I m2

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-16-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and Investigation Level for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area ISOCS (Based on I in2 ) source area = I M2 , 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpml cm) (dpm/lOO cm) 8.73 mrem/y Co-60 6.3E+03 .4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 1.I E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a I m 2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the I m 2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100.cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/100 cm 2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/1 00cm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs- 137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/1 00cm 2. The ISOCS Investigation Level is conservatively calculated for a I m22area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMC.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

Investigation Level Direct Measurements: The investigation level for the direct measurements is equivalent to the gross

.DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-I 25, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCsforISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMc. Refer to Tablel above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-IOOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN-01-16-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs- 137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m 2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/1OOcm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs-137).

• Finally yielding a gross activity SPA-3 DCGLEMc of 1.7E+04 dpm/I00cm'.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 I.

Define the boundaries of the survey:

TBN-01 -16 is bounded by survey area SVC-01 to the east, NOL-01 and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01 -16 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (H.), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type H (fl) error: 0.05 LBGR: 3123 dpm/100 cm2 6.0 Optimize Design:

Type of statistical test: WRS Test rZ Sign Test [

Background to be applied: media-specific LI ambient E] none Z If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-0 1-16-00, Page 4 of 8

Final Status Survey Planning Worksheet INSTRUCTIONS I. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible tobrief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3.1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4.1. ISOCS 4.1.1. Start with TBN-01-16-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2.1. For example, if ISOCS point TBN-01-16-123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01-16-123-F-I-G-'001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-01-16-123-F-I-SC-001 for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2,1.3. TBN-01-16-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-0i-16-001-F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2. 1. If fixed point measurement TBN-01 012-F-FM is to be recounted, use TBN-01 012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-16-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-01-16-013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-16-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01 013-F-I-FM-001 for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect 1-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5.1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-16-0177F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN-01-16-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-887 1, with QC checks performed once per shift in accordance with DP-8869 and DP-8871. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of i .3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMc.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600/HPI OC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-I OC. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2.1. Scan a radius around the direct measurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

DPF-8856.1 YNPS-FSSP-TBN-01-16-00, Page 6 of 8 Rev. 2

Final Status Survey Planning Worksheet 10.2.7. At the highest reading in each elevated area, perform and record a I-minute scaler reading using the E600 with the HP-I 0OC.

DPF-8856.1 YNPS-FSSP-TBN-0 1-16-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (I)Date/time of initial pre-survey briefing

/ QA Signature/Date: (1)

(2)Date/time of daily pre-shift briefing QA Signature/Date: (2)

(3)Date/time of commencement of HP- 100 measurements QA Signature/Date: (3)

/

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)

FSI point(s) (y/n) NO (1)

/

(2)

/

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by- Date FSS Radiological Engineer Reviewed by Date_____________

FSS Radiological Engineer Date Date Approved by Date FSS Project Manager

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-16-00, Page 8 of 8

Final Status Survey Planning Worksheet GENERAL SECTION Survey-Area #: TBN-01 _1Survey Unit #: 17 Survey Unit Name: Turbine Building Survey Unit I - building surface FSSP Number: YNPS-FSSP-TBN-01-17-00 PREPARATION FOR FSS ACTIVITIES Check marks in the boxes below signify affirmative responses and completion of the action.

1.1 Files have been established for survey unit FSS records.

1.2 ALARA review has been completed for the survey unit.

1.3 The survey unit has been turned over for final status survey.

1.4 An initial DP-8854 walkdown has been performed and a copy of the completed Survey Unit Walkdown Evaluation is in the survey area file.

1.5 Activities conducted within area since turnover for FSS have been reviewed. [

Based on reviewed information, subsequent walkdown: Znot warranted El warranted If warranted, subsequent walkdown has been performed and documented per DP-8854. E]

OR The basis has been provided to and accepted by the FSS Project Manager for not performing a subsequent walkdown. .

1.6&A final classification has been performed. Z Classification: CLASS I N CLASS 2 E] CLASS 3 E]

DATA QUALITY OBJECTIVES (DQO) 1.0 State the problem:

Survey Area TBN-01 is the remainder of a concrete pad, which is the structure remaining from the Turbine Building. The above-grade structural part of the Turbine Building has been demolished and removed. The remaining footprint includes the at-grade concrete floor slab.

Events and conditions during operations and decommissioning have introduced radioactive materials into the survey area.

Examples include the following.

" Contaminated drain piping was removed from under the concrete pad exposing soil underneath.

" Radioactive contaminated soil from various excavations were stored in the area, contaminating the concrete pad as well as exposed soil in cratered areas. This include~s the SFP excavation and the sweeper truck residues.

" These areas have been posted Radioactive Materials and Contaminated Areas.

The original HSA and surveys prompted a LTP MARSSIM Classification of 3. Since that time, TBN-01 has been reclassified to Class 1. The reasons are due to the contaminating events listed above.

2 TBN-01-17 is a building.surface survey unit of 88 m .

The problem is to determine if the residual plant related activity remaining in the concrete slab meet the release criterion.

DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-17O00, Page 1 of 8 0

Final Status Survey Planning Worksheet ,

The planning team for this effort consists of the FSS Project Manager, FSS Radiological Engineer, FSS Field Supervisor, and FSS Technicians. The FSS Radiological Engineer will make primary decisions with the concurrence of the FSS Project Manager.

2.0 Identify the decision:

Does residual plant-related radioactivity, if present in the survey unit, exceed the LTP release criteria?

Alternative actions that may be employed are investigation, remediation and re-survey.

3.0 Identify the inputs to the decision:

Inputs to the decision include various information that will be required in the decision making process:

Sample media: concrete Types of measurements: ISOCS gamma scans, fixed point measurements with an HP-100C probe and E-600.

Radionuclides-of-concern:All LTP-listed radionuclides are of concern, but many'of the following calculations will be based on Co-60 for conservatism.

DirectMeasurements DCGLw and DCGLEMc: A single nuclide Co-60 is used in these calculations for conservatism.

" DCGLw : 6.3E+03 dpm/1OOcm 2 at 8.73 mrem/y.

• DCGLsURR : Using the most conservative site mix of Hard-To-Detect nuclides (SFP-CB-02-01: IX Pit Concrete),

the DCGLsURR inferred to Fe-55 and Ni-63 is not significantly lower than the DCGL, resulting in 6.3E+03 dpm/100cm 2.

• The surface may contain pits and irregularity, which will increase the source-to-detector distance to as much as 1". YA-REPT-00-015-04 provides instrument efficiency factors (ei) for various source-to-detector distances. Thus efficiencies (HP-100C) are to be applied as follows: smooth surface 0.0603 c/d, irregular surface 0.0373 c/d.

• Gross activity DCGLw (HP-100C): smooth surface 379 cpm, irregular surface 232 cpm.

• Gross activity DCGLEMC is calculated as follows. Based on L = 2.4m in a triangular grid (see Sample Number Calculation Sheet), the triangular area between points = 0.433L2 = 2.5 m2. Per LTP App. 6S, the next highest Area of Source = 4 M2 , yielding an AF = 2.4 for Co-60. Thus the gross activity surrogate DCGLEMC (HP-IOOC):

0 smooth surface 910 cpm, irregular surface 562 cpm.

ISOCS DCGLF MC: Based on a contaminated source area of I m 2 (see Table 1) for use during ISOCS scans (ref YA-REPT-00-0 18-05; see Attachment 4 for the calculations). If necessary, the 2DCGLEMC will be recalculated if an actual area of elevated concentration is discovered with a source area greater than I in .

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-17-00, Page 2 of 8

Final Status Survey Planning Worksheet Table 1. DCGLw, DCGLEMc and InvestigationLevel for ISOCS measurements DCGLw DCGLEMC (ISOCS Investigation Level based on source area = ISOCS (Based on Im2) source area = Im2 , 2m 90d collimated)

Bldg Surface Bldg Surface Bldg Surface Nuclide (dpm/100 cm 2) at (dpm/100 cm2 (dpm100 CM) 8.73 mrem/y Co-60 6.3E+03 4.6E+04 2.9E+03 Cs- 137 2.2E+04 1.7E+05 1.1E+04 Investigation Level ISOCS: The investigation level for ISOCS scans is calculated from the DCGLEMc as shown by Table I above (ref YA-REPT-00-01 8-05; see Attachment 4 for the calculations). It is derived by multiplying the DCGLEMC associated with a I m 2 area by the ratio of the MDCs for the full field of view (i.e. 12.6 m2 for a 2m height above the surface) to the I m2 area at the edge of the field of view. Thus the calculated 2.9E+03 dpm/ 100 cm 2 investigation level for Co-60 is sensitive enough to detect the DCGLEMC of 4.6E+04 dpm/100 cm 2 .

The SPA-3 DCGLEMC calculated below of 5.3E+04 dpm/100cm 2 (Co-60) and 1.6E+04 dpm/100cm 2 (Cs-137) yields a gross activity SPA-3 DCGLEMC of 1.7E+04 dpm/100cm 2. The ISOCS Investigation Level is conservatively calculated for a I m2 area at the edge of the 12.6 m2 field-of-view. Thus it's detection capability is comparable to the SPA-3 DCGLEMc.

If other LTP-listed gamma-emitting radionuclides are identified in the ISOCS assays, the investigation level will be evaluated using the same criteria.

InvestigationLevel Direct Measurements: The investigation level for the direct measurements is equivalent to the gross DCGLEMc (i.e. smooth surface 910 cpm, irregular surface 562 cpm) or when any reading is above the gross DCGLw (i.e.

smooth surface 379 cpm, irregular surface 232 cpm) and is a statistical outlier.

Investigation Level SPA-3 Scans: The investigation level for SPA-3 scans is a reproducible indication above background using the audible feature with headphones.

Radionuclidesfor analysis: All LTP nuclides with the focus on Co-60.

ISOCS Nuclide Library: Library will include all of the following nuclides: Co-60, Nb-94, Ag-108m, Sb-125, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155.

MDCsfor ISOCS: The desired MDCs for ISOCS are equivalent to the DCGLEMC. Refer to Table] above. The derivation of MDCs is available via Attachment 3.

Scan Survey coverage: Portable ISOCS scans will overlap so as to provide a 100% coverage of the survey area.

MDCfor HP-IOOC: The Attachments 5.1 and 5.2 provide MDCR values by various background levels for both smooth and irregular surfaces. The expected ambient background for the HP-I OOC is a range of 200 - 400 cpm. Note that if the background exceeds 1000 cpm, notify the FSS Engineer.

SPA-3 Scan MDCR and MDC(fDCGLEMc): Refer to Attachment 2 for SPA-3 scan MDC values given a range of background values.

DPF-8856.1 YNPS-FSSP-TBN 17-00, Page 3 of 8 Rev. 2

Final Status Survey Planning Worksheet SPA-3 DCGLEMC: Refer to Attachment 2 for the following, which calculates:

• The SPA-3 Area Factors for Co-60 and Cs-I137 at the LTP App. 6Q Area of Source of 4 m2 (next highest relative to 2.5 m2 calculated source area) for this survey unit.

• The SPA-3 DCGLEMC of 5.3E+04 dpm/l 00cm 2 (Co-60) and 1.6E+04 dpm/1 00cm 2 (Cs-I137).

• Finally yielding a gross activity SPA-3 DCGLEMC of 1.7E+04 dpmll 00cm2.

QC checks and measurements: QC checks for the survey instruments will be performed in accordance with DP-8534.

Pre- and post-use instrument QC checks will be performed. QC checks for the ISOCS will be in accordance with DP-8869 and DP-887 1.

Define the boundaries of the survey:

TBN-0I-17 is bounded by survey area SVC-01 to the east, NOL-01 and 06 to the south, and other TBN-01 survey units to the north and west. The survey of TBN-01-17 will be performed during daylight hours when weather conditions will not adversely affect data acquisition.

The fixed-point measurement locations will be defined by a random-start systematic grid. The ISOCS scans are 100% of the concrete slab surface.

4.0 Develop a decision rule:

a. If all of the direct measurement data show that the plant-related results are below the DCGLw and the sum of fractions for these nuclides are less than unity, reject the null hypothesis (i.e. the Survey Unit meets the release criteria).

b. If the investigation levels are exceeded, then perform an investigation survey. This may include the use of a statistical test.

c. If the average of the FSS direct measurement is below the DCGLw, but some individual measurements exceed the DCGLw, then apply a statistical test as the basis for accepting or rejecting the null hypothesis.

d. If the average concentration exceeds the DCGLw then accept the null hypothesis (i.e. the Survey Area does not meet the release).

5.0 Specify tolerable limits on decision errors:

Null hypothesis: The null hypothesis (Ho), as required by MARSSIM, is stated and tested in the negative form: "Residual licensed radioactive materials in the Survey Unit exceeds the release criterion.

Probabilityof type I (a) error: 0.05 Probabilityof type I (fl) error: 0.05 2

LBGR: 3123 dpm/100 cm 6.0 Optimize Design:

Type of statistical test: WRS Test LI Sign Test Z Background to be applied: media-specific Rl ambient E] none Z If WRS test is specified, record background reference area location:

Basis including backgroundreference location (if WRS test is specified): N/A Number of direct measurements: Twenty direct measurements will be taken, with the triangular grid laid out from a random start point.

DPF-8856.1 YNPS-FSSP-TBN-01-17-00, Page 4 of 8 Rev. 2

Final Status Survey Planning Worksheet INSTRUCTIONS I. The FSS Field Supervisor is responsible to notify QA of date and time of the pre-survey briefing, commencement of direct measurements and any other activities subject to QA notification.

2. The FSS Field Supervisor is responsible to brief on the Job Hazards Assessment.

2.1. The job hazards associated with the FSS in Survey Area TBN-01 and OOL-02 are addressed in the accompanying JHA.

3. Locate and mark the measurement points at the locations shown on the attached map(s).

3. 1. If a measurement location is obstructed such that the measurement can not be collected, select an alternate location in accordance with DP-8856.

4. Designation of survey points including investigations are as follows.

4. 1. ISOCS 4.1.1. Start with TBN-01-17-100-F-G and increment as needed.

4.1.2. For investigations, append terms as follows.

4.1.2. 1. For example, if ISOCS point TBN-01 123-F-G is to be investigated:

4.1.2.1.1. Use TBN-01 123-F-I-G-001 for the first ISOCS investigation survey of ISOCS point number 123.

4.1.2.1.2. Use TBN-0 1-17-123-F-I-SC-00 I for the first SPA-3 investigation scan of ISOCS point number 123.

4.1.2.1.3. TBN-01-17-123-F-I-FM-001 for the first fixed point investigation measurement of ISOCS point number 123.

4.2. Fixed Point Measurements 4.2.1. Start with TBN-01-17-001 -F-FM and increment the fixed point measurement number as needed.

4.2.2. For fixed point recounts, append "-RC" as follows.

4.2.2.1. If fixed point measurement TBN-01-17-012-F-FM is to be recounted, use TBN-01-17-012-F-FM-RC.

4.2.3. For investigations, append terms as follows.

4.2.3.1. For example, if fixed point measurement TBN-01-17-013-F-FM is to be investigated:

4.2.3.1.1. Use TBN-0i 013-F-I-G-001 for the first ISOCS investigation survey of fixed point measurement 013.

4.2.3.1.2. Use TBN-01-17-013-F-I-SC-001 for the first SPA-3 investigation scan of fixed point measurement 013.

4.2.3.1.3. Use TBN-01-17-013-F-I-FM-00I for the first fixed point investigation measurement of fixed point measurement 013.

5. Collect I-minute fixed point direct measurements at 20 locations in accordance with DP-8534.

5. 1. Consider using the shielded HP-100 probe to reduce the effect of background gamma radiation.

5.2. One direct measurement (TBN-01-17-012-F-FM) will be counted twice.

5.2.1. Compare the results in accordance with DP-8864.

5.3. The direct measurement locations may be identified using GPS.

5.4. Each location will be marked either prior to or at the time of the sampling on the surface as well as a map.

5.5. The FSS Radiological Engineer or FSS Field Supervisor will guide the FSS Technician to the sample locations.

5.6. Record each fixed-point measurement "as read" (cpm) on the attached Form I (even if it was logged).

DPF-8856.1 YNPS-FSSP-TBN-01-17-00, Page 5 of 8 Rev. 2

Final Status Survey Planning Worksheet

. 6. Scan 100% of the concrete pad using ISOCS at a 2m height with a 900 collimator at the locations specified on the ISOCS map.

6.1. Operation of the Portable ISOCS will be in accordance with DP-8871, with QC checks performed once per shift in accordance with DP-8869 and DP-887 I. Resolve flags encountered prior to survey.

6.2. Lay out the grid by placing parallel rows of markers forming a square pattern at a maximum distance of 2.6m apart and a maximum of 1.3m from the edge of each surface area (add additional scan points closer than 2.6m apart as necessary).

6.3. Using the 90 degree collimator, position the ISOCS detector directly above each marker 2m from the surface to be scanned.

6.4. Angle the detector as necessary perpendicular to the scan surface.

6.5. Perform an analysis in accordance with DP-8871 using a preset count time sufficient to meet the MDAs referenced in the survey plan.

6.6. Review the report ensuring that the MDAs have been met.

6.7. Review the report for identified nuclides and compare values against the DCGLEMc.

7. Operation of the E-600 will be in accordance with DP-8535, with QC checks performed in accordance with DP-8540.

8. All personnel participating in this survey shall be trained in accordance with DP-8868.

9. If an ISOCS measurement needs to be investigated, perform it as follows.

9.1. Scan the entire ISOCS footprint with a SPA-3 at approximately 2" - 3".per second in rate-meter mode with audible on.

9.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

9.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

9.4. Measure the total area of each outlined area in square centimeters.

9.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

• 9.6. Indicate the highest reading on the map for each elevated area.

9.7. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600/HPI OOC.

10. If a direct measurement needs to be investigated, perform it as follows.

10.1. Conduct a first-level investigation.

10.1.1. Perform a re-survey of the measurement location with the HP-100C. If the measurement confirms that the original measurement was in fact above the investigation level, conduct a second-level investigation.

10.2. Conduct a second-level investigation.

10.2. 1. Scan a radius around the directmeasurement location equal to half the distance between measurement locations, i.e. 1.3 meter radius. Use a SPA-3 at approximately 2" - 3" per second in rate-meter mode with audible on.

10.2.2. If the SPA-3 background exceeds 17000 cpm, contact the FSS Engineer.

10.2.3. Mark on the surface the outline (boundary) of areas with elevated activity. Identify each outlined area on a survey map.

10.2.4. Measure the total area of each outlined area in square centimeters.

10.2.5. Indicate on the map and the actual location the highest identified activity among all of the elevated areas.

10.2.6. Indicate the highest reading on the map for each elevated area.

. DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-17-00, Page 6 of 8

Final Status Survey Planning Worksheet 10.2.1. At the highest reading in each elevated area, perform and record a 1-minute scaler reading using the E600 with the HP-IOOC.

DPF-8856.1 YNPS-FSSP-TBN-01-17-00, Page 7 of 8 Rev. 2

Final Status Survey Planning Worksheet NOTIFICATION POINTS QA notification* point(s) (y/n) YES (1)Date/time of initial pre-survey briefing

/ QA Signature/Date: (1)

(2)Date/time of daily pre-shift briefing

_/ QA Signature/Date: (2)

(3)Date/time of commencement of HP-100 measurements QA Signature/Date: (3)

(4)Date/time of first ISOCS measurement QA Signature/Date: (3)

FSI point(s) (y/n) NO (1)

(2)

/

• Voice mail or email notification to Trudeau@yankeerowe.com and copy to Calsyn@yankeerowe.com.

Prepared by -Date FSS Radiological Engineer Reviewed by Date FSS Radiological Engineer Approved by Date FSS Project Manager

.*DPF-8856.1 Rev. 2 YNPS-FSSP-TBN-01-17-00, Page 8 of 8

Report No.: YNPS-FSS-TBNO1-00 S

Appendix B YA-REPT-00-015-04 Instrument Efficiency Determination for Use in Minimum Detectable Concentrations Calculations in Support of the Final Status Survey at Yankee Rowe p

ReportNo.: YNPS-FSS-TB.NObOO0 TECHNICAL REPORT TITLE PAGE 4

COPY Instrument Efficiency Determination for Use in Minimum Detectable Concen.tration Calculations in Support of the Final Status Survey at Yankee Rowe Title YA-REPT-MO015-44 REV 0 Technical Report'Number I

Approvaly, r\ (Print & Sign Name) rcarer: Date: I, Review

.. Date: (CC).-_

Approver (Co *zant.Manager): Date: /-6 /7/c0 '

YA-REPTAM00015-04 Rev, 0 'Page 1 of 26 E

Report No.: YNPS-FSS-TBN0I-00 TABLE OF CONTENTS Page 1.0 Executive Summary; ................... ................................. 4 2.0

Introduction:

........................................ .... ................ 4 3.0 Calibration Sources: ............................ . 4.

4.0 Efficiency Determ ination .................. ................................... ............. 6 4.1 Alpha and Beta Instrument Efficienicy (ei): ......................... ...... ;......................... 6 4.2 Source to Detector Distance Considerations: .................................. .......... 7 4.2.1 Methodology .................... ......................................... 7 4.3 Source (or Surface) Efficiency (c,) Deternination: ........... ................ 8 5.0 Instrument ConversionFactor (E) (Instrument Efficiency for Scanning):............................. 9.

6.0 Applying Efficiency Corrections Based on the Effects of Field Conditions for Total Effieiency:...9 7.0

Conclusion:

..................................... ........................................... 10 8.0

References:

....... ............  ! .. .............................. .............. . 11 Tables Table3.1 Nuclides and Major Radiations: Approximate Energies ...... ....................... 5 Table 4.1 Instrument Efficiendies (q)........ ........................ . . 7 Table 4.2 Source to Detector Distance Effects on Instrument Efficiencies for a* I Emitters: ....... 8S Table 43 SourceEfficiencies as listed in ISO 1703-4: ................. ................ 8 Table 5.1 Energy Response and Efficiency for Photon Emitting Isotopes:- ............ ...... 9 Appendix APPENDIX A MicroShield, SPA-3 Soil scan -28cm radius IpCi/cm3 Coý60 ......... ... 12 APPENDIX B Microsoft Excel Co-60 Calculation Sheet ..................... ........ ................. 13 APPENDIX C Micro Shield, SPA-.3 Soil scan - 28 cm radius IpCi/cm3 Nb-94............. 14 APPENDIX D Microsoft Excel Nb-94 Calculation Sheet........ .......................... ........... .15 YA-REPT-60-015-64 Rev. 0 Page 2 of 26.

,1-

Report No.: YNPS-FSS-TBNOI1-00 APPENDIX E MicroShield, SPA-3 Soil scan -28 cm radius IpCi/cm3 Ag-I08m ................. 16 0

APPENDIX F Microsoft Excel Ag-108m Calculation Sheet.,............................ 17 APPENDIX G MicroShield, SPA-3 Soil scan - 28 cm radius IpCi/cm3 Sb.- 25..... .............. 18 APPENDIX H Microsoft Excel Sb- 125 Calculation Sheet ............................................ 19 APPENDIX I MicroShield, SPA-3 Soil scan -28 cm radius. IpCi/cm3 Cs-4134 .................... 20 APPENDIX I Microsoft Excel Cs- 134 Calculation Sheet................... ......... 21 APPENDIX K MicroShield, SPA-3 Soil scan -28 cm radius t pCi/cmn3Cs-37 ................ 22 APPENDIX L Microsoft Excel Cs- 137 Calculation Sheet....... ......... ......... ............23 APPENDIX M MicroShield, SPA-3 Soil scan -28cm radius I pi/cni3 Cs-137................ 24 APPENDIX N Microsoft Excel Cs-137 Calculation Sheet ..... ........................ 25

,APPENDtXO CalculatedEnergy RIesponse ............... ....... .. .......... ....... 26 0

YA-REPT-OOwO15-04 Rev, 0 Page'3 of 26

Report No.: YNPS-FSS-TBNOI-00 1.0 Executive Summary:

The minimum detectable concentration (MDC) of the field survey instrumentation is an important factor affecting the quality of thefinal status survey (FSS). The efficiency of an instrument inversely impacts the MDC value. The objective of this report is to determine the instrument and source efficiency values used to calculate MDC. Several factors were considered when determining these efficiencies and are discussed in the body of this report. Instrument efficiencies (Q), and source efficiencies (Es), for alpha beta detection equipment under various field conditions, and instrument conversion factors (El), for gamma scanning detectors were determined and the results are provided herein.

2.0

Introduction:

Before performing Final Status Surveys of building surfaces and land areas, the minimum detectable concentration (MDC)must be calculated to'establish the instrument sensitivity. Table 5.4 of the License Termination Plan (LTP) [8.6] lists the avalable instrumentation and nominal detection sensitivities; however for the purposes of this basis document, efficiencies for the 100cm 2 gas proportional and the 2"x2" Nal (Tl)detectors will be determined. Efficiencies for the other instrumentation listed in the LTP shiall be determined on an as needed basis. The. 100cm2 gas proporional probe will be used to. perform surveys (i.e.,fixed point mcasurenieents), A 2" x2"'NalI(Tl) detector will be used to performrgamma surveys (iLe., sdrface scans) of portions of land areas and possibly supplemental structural scansat the Yankee Rowe site: Although surfice scans.and fixedpoint measurements can be performed using the same instrumentation, the calculated MDCs will be quite different. MDC is dependent on many factors and may include but is not limited to:

• instrument efficiency

-,background

. .integration time "surface type "source to detector geometry

-source efficiency A significant factor in determining an instrument. MDC is the total efficiency, which is dependent on the insthrment efficiency, the sourceefficiency and the type and energy0of the radiation. MDC values are inversely affected by efficiency, as efficiencies increase, MDC values will decrease. Accounting for both the instrument and source components of the total efficiency provides:for amorie accurate assessment of surface activity,.

3.0. Calibration Sources:

For accurate measurement of surface ,activity it is desirable that the field instrumentation .be calibrated with source standards similar to the type and eneigy ofthe anticipated contamination. The nuclides listed in Table 3.1 illustrate the nuclides found in :soil and building suiface area DCGL results that are listed in the LTP.

Instrument response varies with incident radiations and energies;, therefore, instrumentation selection for field surveys must be modeled on the expected surface activity,. For the purposes of this report, isotopes.

with maxbeta energies less than thatofC-14 (0.158 MeV) will be:considered difficult todetect (reference table3.l). The detectability of radionuclides with max beta energies less than 0.158 Mev, utilizing gas.

proportional detectors, will býe negligible at typical source'to detector distances of approximately 0.5 YA-REPT-00-015-04 Rev. 0 Page 4 of 26

Report No.: YNPS-FSS-TBNO 1-00 inches. The source to detector distance of 1.27 cm (0.5 inches) is the distance to the detector with the 0 attached standoff (DP-8534 "Operation and Source Checks of Propoitional Friskers")[8.5]. Table.3A provides a summary of the LTP radionuclides and their detectability using Radiological Health:Handbook

[8.4] data.

Table'3.1 Nuclides and Major Radiations. Approximate Energies.(Reference 8.4)

Nuclide a Energy 4,4_ (MeV) Average Photon Energy (MeVI a Delectable A Detectabte ¥ (MeV) Ep w/Gas W1Gas Detectable.

H-3 0.018 I0.005 (Nev) Proportional Proportional wI Nal 2x2" c-14 .o,158 0049 Fe-55 0.23 (0.004%)

bremsstrahlung Co-0 0.314 0.094 1,173ý(100%), 1.332 .

Ni-63 0.066 0.017 1__(100%) _ __

Sr-90 0'544 '0.200

_ _2.245 CY-90) .0-931 Nb-94 0.50 0.156 0.702 (100%), 0.871 T-7 T (100%)

Tc-99 0.295 0.085 Ag- 1.65 (Ag- 0.624 0:434(0.45%), 0,511 108m 108) (Ag- (0.56%)

108) 0:615 (0.18%), 0.632 CIJ7%)

Sb-125 0,612 0.084 0.6., 0.25, 0A.1, 0.468 - .

0.68, 0.77i 0.92,. 1.10, 1.34:

Cs-134 1.453 0.152 0.57,(23%),0.605 (98%)

• 4 0,796 (99%), 1.038 0(1 0%) '... .. .

(1,09%)

(3.4%)

Cs,137 Eu- 52

.1.167 1.840

• 0.195 0.288 0;6.2(85%).B.137m'X-

• _____rays_______

0.122(37%), 0.245'?8%)

0.344 (2%,0.779'(14%)

4 4'

6 0.965(15%), 1.087(12%)

,_00o1" 1113 (141), 1.40o8(22%)

Eu-154 1.850 (10%). 0.228 Eu-155 0.247: 0.044 0.087 (32%), 0*105 (20%)

Pu-238 5.50 (72Y9) ,0.099 (8E-3%)

5.46(28%) 0.150 (1,E3%)

0..O77(5E-5%)

Pu-239 5.16 (08%) U0039 (0.007%), 0.052 -4 5.1'1 (11%)

___________ ___(0.005%)*,

(0.20%),.0.129 Pu-241 4.90 0&021 0.005 0.145 (1:6E-4%)

(0.0019%)

4:85

__ __ (o.o0 o03 ) ___ __...........

Am-241 5,49 (85%) 0,060 (36%),0,101

____15,44 (1 j%) _______o.04%)... I____

-Cm-243 6,06(6%) .0.209(4%), 0,228 (12%),

I 5,99 (6%) 0.278 (14%)

5.79(73%)

5.74

___ _ _ _ _ __ __ _ __51% ___ _ _

YA-REPT-O0-O15-04 Rev. 0 Page5 of 26 I

Report No.: YNPS-FSS-TBNO1-00 NUREG- 1507 and ISO 7503-1 provide guidance for selecting calibration sources and their use in determining total efficiency. It is common practice. to calibrate instrument efficiency for a single beta energy; however the energy of this.reference source should not be significantly greater than the beta, energy ofthe lowest energy to be I.measured.

Tc-99 (0.295 MeV max) and Th-23.0 (4.68. MeV at 76% anid 4.62 MeV at 24%) have been selected as the beta andalphacalibration standards respectively, because their energies conservatively approximate the beta and alpha energies of the plant specific radionuclides.

4.4) Efficiency Determination:

Typically, using the instrument 47t efficiency exclusively provides a good approximation of surface activity. Using these means for calculating the efficiency often results in an under estimate of activity levels in the field. Applying both the instrument 2U efficiency and.the surface.. efficiency components to determine, the total efficiency allows for a more accurate measurement due to consideration of the actual characteristics of the source surfaces. ISO 7503-1 [8.2),recommends that the total surface activitybe caleulated using:

- Rsit- R8 where:

Ai is the total surface activity in dpm/cm.,

Rs5 a is the gross count rate' of the measurement, in cpm, SRB is the background count rate in cpm,,

ej is the instrument or detector 2at efficiency Ec:is the efficiency of the source.

Wis the area of the detector Window (cm) 4.1 Alpha and Beta Instrument Efficiency (Qi:

lnistrumient efficiency (9i) reflects instrument characteristics and counting geometry, such as source.

construction, activity distribution, source area, particles incident on the detector per unit time and therefore source to detector geometry. 'Theoretically the maximum value of zi is L0, assuming all the emissions fromthe source are 2n and that all emissions from the source are.deteted. The.ISO.7503-1 methodology for determining the instrument:efficiency-is similar to the historical 4,r approach; however

,the detector response, in cpm, is divided by the 2- surface emission rate of the calibration source. The instrument efficiency is calculated by dividing the net count rate by the 2z surface emission rate (q 21)

(includes absorption in detectorwindow,.source detector geometry). The instrument efficiency is expressed in. ISO'7503-1, by:.

YA-REPT-00-015-04 Rev. 0 Page6. of 26 S

Report No.: YNPS-FSS-TBNO1-00 Rs,-R q0 where:

Rs+a is the gross count rate of the measurement in epm, RD is the background count rate in cpm, q 2:is the2-n surface emission rate in reciprocal seconds Note that both the 2n surface emission rate and the source activity are usually stated on the certification sheet prov ided by the calibration source manufacturer and certified as NationallInstitute of Standards and Technology (NIST) traceable. Table 4.1 depicts *instrumentefficiencies that have been determined during calibration using the 2ar surface emission rateof:&e source.

Table 4.1 Instrument Efficiencies.(&i)

.Source Emission Active Area of Effective Area 109 cm2 Gas Proportional Source (cm) of Detector HP-100 Instrument Efficiency (zi)

(Contact)

Tog99 fl 15.2 100 cm2 0.4148 Th-230 ýa 15.2 1Do cm 0.5545 4.2 Source to Detector Distance Considerations:

A major fact&raffecting instrumentefficiency is source to, detector distance.. Consideration must begiven to this distance when selecting, accurate instrument efficiency. The distance fromlthe source to.the detector shall to be as close,as practicable to geornetric conditions that exist in the field. A range of source to detector distances has been chosen, taking into account site:specificsurvey:conditions. In an effort to-minimii. the error associated with geometry, instrument efficiencies have been determined for source to detectordistances representative of those survey distances expected in the-field. The results shown in TableW4.2*ilustrate the imposing reduction in detector response with increased distance from the source. Typicaliy this source to detector distance will be 0.5.inches fbr fixed point mneasurements and 0.5 inches for scan surveys on flat surfaces, however they may differ.for other surfaces. Table 4.2 makes provisions for the selection of source to detector distances for field survey conditions of up to 2 inches.. If surfacec onditions dictate the placement of the detector at distances greater than 2 inches instrument efficiencies will b!e determined on an as needed basis.

4.2.1 Methodology

The practical application of choosing the proper instrument efficiency may be determined by averaging the' surface variation (peaks and valleys narrower than the length. of the detector) and adding 0.5 inches, the spacing that should be maintained between the detector and the highest. peaks of the surface. Select the source'to detector distanee from Table 4,2 that best reflects this pre-determined geometry.

YA-REPT-00-015-,04 Rev. 0 'Page 7 of 26

Report No.: YNPS-FSS-TBNO 1-00 S Table 4.2 Source to Detector Distance Effects on Instrument Efficiencies for -.3,Emitters Source to Detector Instrument Efficiency (co, Distance (cm)

Tc-99 Th-230 Distributed Distributed, Contact 0.4!48 0.5545 1,27 (0.5 .in) 0.2413 0.1764 2.54,(1 in) :0.1490 0.0265 5.08 (2 in) 0.0784 0.0002 4.3 Source (or Surface) Efficiency (C) Determination:

Source efficiency (8-), reflects the physical characteristics of the surfaceand any surface coatings. The source efficiency is.the ratio between the number of particles emerging from~surface and the total number of particles released within the source. The source efficiendcy accounts for attenuation and backscatter. a'a is nominally .0.5 (no self-absorption/attenuation, nobaeklscatter)-backscatter increases: the value, self-absorption decreases the value. Source efficiencies may either be derivedexperimentally or simply selected :from the"guidance coritained in ISO17503-1. ISO 7503-1 .takes a conservative approach by recommending the use.6f factors to correct for alpha and beta self-absorption/attenuation when' determining surface activity. However, this approach may prove to be too conservative for radionuclides with max beta energies that are marginally lower than 0.400 MeV, such as Co-60 with a p3max of 0.314 MeV. In this situation, it may be moreappropriate towdetermine the source efficiency by considering the energies of other beta emitting radionuclides. Using this approach itjs possible to determine :weighted average source efficiency. For exampile, a source efficiency of 0,375 may be calculated based on a 50/50,

.-mix of Co-60 and Cs137. The source efficiencies foruCo-60 and:Cs-137 are 0.25 and 0.5: respectively, 5efficiencysince the radionuclide fraction for Co-60 *nd Cs-'I37 is 50% for each, the weighted, average source, for the.minx may be calculated in the following manner:

(0.25X03.)+ (0.5X.5) = 0,375 Table 4.3 lists guidance on s6urce efficiencies from ISO 7503:1.

Table 4.3 Source Efficiencies as listed in ISO 7503-1

> 0.400 MeVm,* ::-5 0.400 MeV,,,,

Beta emitters £p'=,0.5 c,= 0.25 Alpha~emittersý &=0.25 c = 0.25.

It should be noted that source efficiency is:not typically addressed for, gamma detectors as the value is effectively unity, YA-REPT-00-015-04 Rev. 0 Page 8,of26 p

Report No.: YNPS-FSS-TBNO1-00 II 5.0 Instrument Conversion Factor (E) (Instrument Efficiency for Scanning):

Separate modeling analysis (MicroshieldT. ) was conducted using the common gamma emitters with a concentration of I pCilg of uniformly distributed contamination throughout the volume. MicroShield is a comprehensive photon/gamma ray shielding and dose assessment program, which is widely used throughout the radiological safety community. An activity concentration of I pCi/g for the nuclides was entered as the source term. The radial dimension of the cylindrical source was 28 cm, the depth was 15 cm; and the dose point above the surface was 10 cm with a soil density of 1.6 g/cm3 . The instrument efficiency when scanning, Et, is the product of the modeled exposure rate (MicroShieldTM) in mRhr'/pCilg forand the energy response factor in epm/ml/hr as derived from the energy response curve provided by Eberline Instruments (Appendix O)% Table 5.1 demonstrates the derived efficiencies for the major gamma emitting'isotopes listed in Table 3.1.

TABLE 5,1 Energy Response and Efficiency for Photon Emitting Isotopes Isotope Calculations for E1 EJ Set appeadixA throntb L , (cpmtpCi/g)

Co-60 See Appendix AandB 379 Nb-94 See AppendixC andD '416 Ag-I0im SeeAppendix E and F 637 Sb-125 See Appendix Gand H 210 Cs7I34 See Appendix I and J 1506 Cs137 SeeAppeqdixgKandL 1188 Eu-I52 See Appendix Mand N l 344 When perfomiing gamma scan measurements on'soil-suifacis the effective source to-detector geometry 'is as close as is reasonably possible (less than 3 inches).

II 6.0 Applying Efficiency Corrections Based on the Effects of Field Conditions for Total.

Efficiency:

The .total efficiency for any given condition can now be calculated from.theproduct of the instrument efficiency zi.and the sourceefficiency Ps,

ý=6i x as The following example illustrates the.process of determining total efficiency. Forthis example we will assume the following:

o-Surface'activity.readinigs need to be made in the Primary Auxiliary Building ,PAB) on the concrete wall surfaces using the E&600 and C-! 00 gas proportional detector.

• Data obtained from characterization results from the PAB indicate the presence of beta emitters with energies,greaterthan 0.400 Mev.

• The source (activity on wall) to detector distance is 1.27 cm (0.5 in detector standoff). To calculate the'total efficiency., ct, refer to Table 4.2 "Source to Detector DistanceEffects:on Instrument Efficienciesmfor a- O Emitters" to obtain the appropriate si value.

• Contamination on all surfaces-is distributed relative to the effective detector area.

YA-REPT-00-015-04 Rev. 0 Page 9 of 26

Report No.: YNPS-FSS-TBNO 1-00

• When perfoinning fixed point measurements with gas proportional instrumentation the effective source to detector geometry is representative of the calibrated geometries listed in Table 4.2 "Source to Detector Distance Effects on Instrument Efficiencies for ct- fi Emitters".

• Corrections for temperature and pressure are not substantial.

In this example, the value for q1 is 0.2413 as depicted in Table 4.2 "Source to Detector Distance Effects on Instrument Efficiencies for a- f3Emitters". The F, value of 0.5 is chosen refer to Table 4.3 "Source Efficiencies as listed in ISO 7503-1". Therefore the total efficiency for this condition becomes ew,-= si x C, 0,2413 x 0.5 = 0.121 or 12.1%.

7.0 Conclusion; Field conditions may significantly influence the usefulness of a survey instrument. When applying the instrument and source efficiencies in MDC calculations, field conditions must be considered. Tables have been constructed to assist in the selection of appropriate instrument and source efficiencies.: Tatble 4.2:

"Source to Detector Distance Effects on Instrument Efficiencies-for u-0 Emitters" lists instrument efficiencies (oi at Various source.to detector distances for alpha and beta emitters. The appropriate ej.

value should be applied, accounting for the field condition, i.e. the relation between the detector and the surface to be measured.

Source efficiencies shall be selected from Table 4.3 "Source Efficiencies as listed in ISO 7503-17. This table lists conservative r, values that correct for self-absorption and attenuation of surface activity.

Table 5.1 "Energy Response and Efficiency for PhotonErmitting Isotopes' lists, E values that apply to scanning MDC calculations,. The MicroshieldTM model code was, used to determine instrument efficiency assuming contamination conditions and detector geometry cited in section 5.6.2.4.4 "IMDCs for Ciamma Scans of Land Areas" of the. License Termination Plan:J8.6],

Detector and source conditions :equivalent to those modeled herein may directly apply to the results of this report-YA-REPT-00-015-04 Rev. 0 Page 10,of 26 i

Report No.: YNPS-FSS-TBNO 1-00 8.0 References I

8.1 NUREG-1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions," i998 8.2 ISO 7503-1, "Evaluation of Surface Contamination - Part 1: Beta Emitters and Alpha Emitters," 1988-08-01.

8.3 ISO 8769, "Reference Sources for the Calibration of Surface Contamination Monitors-Beta-emitters (maximum beta energy greater 0.15MeV) and Alpha-emitters," 1988-06-15.

8.4 "Radiological Health Handbook,"Revised Edition 1970.

8.5 DP-8534, "Operation and source Checks of Portable'.Friskers".

8.6 Yankee Nuclear Plant Site License Termination Plan, ReVO,, November 2003.

I YA-REPT-00-015-04 Rev. 0 Page 11of26 I

Report No.: YNPS-FSS-TBNOI-00 S APPENDIX A MicroShield v6.02 (6.02-00253)

Page :I File Ref DOS File :SPA3-EFF-Co-60.ms6 Run Date Date September 10, 2004 By Run Time 8:56:50 AM Checked Duration 00:00:00 Case

Title:

SPA3-EFF-Co-60

Description:

SPA-3 Soil scan - 28 cm radius lpCifcm3 Co-60 Geometry:'8- Cylinder Volume - End Shields Source Dimensions:

Height 1s5o cm (5,9 in)

Radius 28.0 cm (11.0 in) lose Points V A X y z

1. 1.v 0cm 25 Cm 0cm 0.0 in 9.8 in 0.0 in Shields Shield N Dimension Material Density 3

source 3.69e+04 Cm Concrete 1.6 Air Gap Air 0.00122

,Source Input : Grouping"Method'- Actual Photon Energies S

3 3 Nu.tide curies becquerels pCi/cm Bql/csn Co-60 316945e-OOB 1.367Oe+003 1.O000oe-O06 :3.70004-0021 Buildup : The material reference is - Source Integration Parameters Radial 20 Circumrerential :10 Y Direction (axial) 10 Results Energy Activity Fluence Rate Fluence 2Rate Exposure Rate Exposure Rate MeV/cmz/sec

• mR/hr.

MeV Photons/sec MeV/cm tsec mR/fir No Buildup With Buildup No Buildup With Buildup 0.6938 2.23,0e01 1t.59Oe-05 s.055e-o6 1.748e-08 3.070e-08; L.1732 1.367e+/-03 l098e-01 1;.669e-Oi 1 .962e-04 2 982e-o4 1.3325 1,367e+03 1.293e-01 ,.904e-01 2.244e-04 3.303e-4 Totals 2.734e+03 2.3g1e-01 ,3.573e-O1 4.205e-04 &286e-04 YA-REPT-00-O 15-04 Rev. 0 Page 12 of 26

Report No.: YNPS-FSS-TBNOI-O0 APPENDIX B

.YA-REPT-0O-O 15-04 Rev. 0 Page 13.of 26

Report No.: YNPS-FSS-TBNO 1-00 is APPENDIX C MicroShield v6.02 (6.02-00253)

Page :I File Ref DOS File :SPA3-EFF-Nb-94.ms6 Date Run Date September 16, 2004 By Run Time 3:22:38 PM Checked Duration 00:00:00 Case

Title:

SPA38EFFTNb-94

Description:

SPA-3 Soliscan -:28 em radius lpCVcm3 Nb-94 Geometry: 8 - Cylinder.Volume- End Shields.

Source Dimensions:

Height I5.0 Cm (5.9 In).

Radius 28.0 cm (iO0 in)

Dose Points A X Y z V n 25cm 0cm in, 9.8 in 0,0 in

• Shields Shield N Dimension Material Density Source 3. 69e+04 cma Concrete. 1.6 Air Gap Air 0,00122 Source rnput,: Grouping Method - Adtual Photon Energies 5

,Nuclide curies becquerels pCi/cm. Bq/cm, Nb-94 316945e-00S 1.3670e+*003. 1000e-006 3.7000e-002 Buildup : The material reference is - Source Integration Parameters Radial 10.

Circurnferential 10 Y Direction (axial)

Results Energy Act'ivity Fluence Rate Fluence Rate Exposure Rate Exposure Rate eeV/cn/*sec mR/hr mR/hr Mev Photons/sec ,N0 Bui1/Sp With Buildup No Buildup. With Buildup

ýNoBuildup 1:.861e-Z0 0.0023 9.067e-02 1.391e-10 1.430e-10 .1.913e-10 0.0174 4,834e-01 8.762e-09 9. 21e-09 ý4*729e-10 4,927e-10 0.0175 9.260e-61 1719e-0:. L792e-08 9*9104e-10 :9.491e-10 8.8356e-09 2:925e-10 3.085e-10

ý0.0196 2,726e-01 7..924e-06 0.7026 1L367e+03. 5.643e-02: 9.872e-02 1.088e704 1.904e-04 0.87ii 1,367e+03 7.464e-02 1.228e-01 1.405e-04 2,312e-04 Totals 2,736e+03 1.311e-01 2.216e-o" 2.493e-04 4,216e-04 YAhREPTw00-01 5-04 Rev. 0 Page 14 of 26 S

Report No.: YNPS-FSS-TBNO 1-00 APPENDIX D a

0 YA-REPT-00-015-04 Rev:O Page 15 of 26 I

0

Report No.: YNPS-FSS-TBNO1-00 S APPENDIX E MicroShield v6.02 (6.02-00253)

Page :1 File Ref DOS File :SPA3-EFF-7A97108m.ms6 Date Run Date  :.September 16, 2004 Run Time By 3:30;40 PM Checked Duration 00:00:00 Case Trile: SPA3-EFF-Ag-108m Description SPA-3 Soil scan - 28 cm radius lpCi/cm3 Ag-108rn Geometry: 8 - Cylinder Volume - End Shields Source Dimensions:

Height 15:0 cm (5.9 in)

Radius 28.0 cm (11.0 in)

Dose Points V A X Y z

1. 1 0crm '25cni 0 cm 0.0. in " 9.8 in 0.0 in

,Shields Shield N Dimension Mated al Density 3

Source 3.69e+04 cm' Concre'te 1,6 Air Gap, Air 0.00122 Source Input-, Grouping Method,- Actual .Photon Energies 3 2 Nuclide curies becquerels pCI/cm Bq/ cm Agi08rm 3.6945e'008 1.3670e+003 1.000Oe-006 3;7000e'002 S Radial Buildup The material reference is - Source

'Integration Parameters

.20 Circumferential 10 Y Direction (axlal) 10 Results.

Energy Activity . Fluence 2Ratle Filuence Rate 2

Exposure Rate. Exposurei Rate NOV Photons/se.

en MeV/cm No Buildup /sec MeV/Cm lsec mR/hr mR/hr With Buildup No Buildup With, Buildup 0.0028 6.580e+01 A.2S2e-o7 *1.287e-07 1.351e-W07 1.388e-07 0.003 7.853e+00 I.56se-08 1,6126-08, 1.65,7e.-0 0.021 2A491e+02 9.S34e-06 I.015e-OS* 2.424-07 .3.007.e-07 0.0212 4.727e+02 1,..862e-OS I .985Q-OS: 5.389e107 S0.022 7.024e+00 31202e-07 3.434e-07, 8.233e-09 8.'831e-09, 0.0222 I 330e+01" 6.251e-07 6.714e-07 1.568e-08. 1.68se&08 0.0238 .,501e+02 9.273e-706. i.0 1 e-'DS 1,863e-07 2;029e-07 0,0249 4.289e+00 3,145e-07 3.464e-ý07 5.492e-09 6.050e-09 0:0304 2.902e-04 4,431e-1* 4.230e-13 0.0792 6.687e+01 2.008e- 04 4.802e-04 3.190e-07 7,629e-67 0.43'39 1.229e+03 2705e-;02. 5.514e-02 5.294e-05 1.07ge-04 0.6144 1.236e+03 4.282e,02 7.808e-02 8.347e-05 1.522e-04 0.7229 1.237e+03 5.300e-02 9.1946-02 1.019e-04 1'.768e.04 Totals 4.768e+03 L231e..OI ý2,157e-01 2.398e-04 4.369e-04 YA-REPTO00-015-04 Rev. 0 Page 16 of026 a

Report No.: YNPS-FSS-TBNOI-00

.APPENDIX F a

0 YA-REPT-00-0 15-04 Rev. 0 Page 17 of 26 0

Report No.: YNPS-FSS-TBNO1-00 a APPENDIX G MirclShield .v6.02 (6.02-00253)

Page File Ref DOS File :SPA3-EFF-Sb1 25.ms6 Date Run Date Scptcrnber 16. 2004 By Run Time 3:34:07 PMK 00:00:00 Checked Duration Case

Title:

SPA3-EFF-Sb- 125

Description:

SPA-3 Soil sanc a - 28 m dius I pCi/cm3 Sb-c,25 Geometry: 8-*]Cylirder Volume - End Shiclds Tkithi 25.0c (.19 m.

ilR.iI t] .0 i4 V

.5 V C Aici-m 5-C 14m Pif Atbo - -MIJU , E $,

145,051.

I 3'.7~LOW 710~2 Rc4~ 110j~~tv ti~n -ti.S...

rs~sr 51t41 V Dso~'.ss5, S pholousooVs 3FlumcueRate NotBuildup, Results Flen. Rat~e

.With Buildup Esposere ttal uItR/hr Buildup Exspsure 1661e mR/br N4 wiqh Buildup:

6-7624101 1.756".7 1,42Se-07 L.749,,+022 ,2.6866-07 46 3.262e-02 3,922C-03 4. 1e-z-7 5.067e-"7 0.117"1 12,221e.03 0,1591 5.6308-06 1.997c-07 1,634c.05 1,918"s0

.5.778"S5'

• 0.1172 1.096C407 1,49%450 1.505"s0 3.610c-05:

3.5624+00 2.3805"55 0 I 63 9

$,701o-00 .4.23 5s->

U2081 74364"09 1:5.164t-016 0.5279 9 Stls.Os 5.G51c-05:

0.321, 3.870%-01 09.3804 4,009e-.00 6,40; 4. 130ls00, 1T03-O 6.78 0479 4 68457e.06

2. 3e0+.2 0 0.435 4,028e-03 4.946e.05 J. 060e.02 ,3.13C-07 4

((.463

(.77662.02<

0,63$0 6,86.4e*01 0,6714 41271e-03, I.3' I,916c,+03.

YA-REPT-00015-014-Rev. 0 Page' 18 of 26 S

Report No.: YNPS-FSS-TBNO1-00 APPENDIX H 0

YA-REPT-00015-04 Rev. 0 Page 19 of 26 0

Report No.: YNPS-FSS-TBN01-00 APPENDIX I MicroShield v6.02 (6.02-00253)

Page :1 File Ref DOS File :SPA3- EFF'C%- 134.ms6 Date Run Date September 16, 2004 By Run Time 3:39:09 PM S00:00:00 Checked Duration Case

Title:

SPA3-EFF-Cs- 134

Description:

SPA-3 Soil scan - 28 cm radius lpCi/cm3 Cs-134 Geometry: B - Cylinder Volume - End Shields Source Dimensions:

Height 15.0 cm (5.9 in)

Radius 28.0 cm (110 in)l I0lose Points Y A X Y z 1.! 0cm 25 cm SOcm 0.0 in 9.8 in 0.0 In

(

Shields Shield N Dimension Material Density Source 3.69a+04 cm2 concrete L.6 Air Gap Air 0.00122 Source Input". Grouping Method - Actual Photoin Energles

,curies becouereis, pCtIcms 2 Nudide Sooq/cm Cs&i34 3,6945e-008 I,3670e+/-003 1.0000e7006 3.7000e-ý002 Buildup : The matrrial reference is -Source Integration Parameters Radiall 20 circumferenlial t0 Y Direction (axial) 1o Results Enegy Acivty Fluence Rate Fluence 2Rate Exposure Rate .Exposureý Rate Enegy ctiity Mew/cm/ae MeVfcmn /sec .. mR/hr .mR/hr

• No Phton/Se NoBuildup WithBulildup No Buildup. With Buildup 0.0045 1.222e+-00 3.658e-09 3.700e09q 2 *5076-09 2.577e-ý09 0.03i8 2.9.31e+00 5.27ig-07 6.386e-07 4.391e-09 5,32 e-09 0,6322 S.407e-i00 1. 1014e.06, 1.236ew()6 S.157e-09 9.943ewO9 0.0364 1.968i+-00 5.61le-07 7.321e-07 3. 18se-09 4.16Ge-09 0.2769 4-839e-01 5.93ie-06 1-391e-05, - 113e-08 '2.61.0e-08 0.4753 Ji.96e4+01 4.950e-04 9.86&e-04: 9-7 12e-07 1.924ew06 0.5632 1.146eo+02ý 3.54Se'03I 6.648e6-03 6.940e-0 6 1.302e7OS 1.295e-05* 2 42le-05.

0,5693 2.109e+02: 6.61 ge-03 1.23e'02'

-8.836e-05S 0,6047 1.334e-e03 4.529e-02 8.3006.02 1,1619e-04 0.7958 1A.67e+03 5.668e-02 9.564e-02 1.07ge-04 1,820eý-04 0.801.9 1.1 .93e+i.0 5.852 e-03 9.MSe-03 1.113e-05 1.874e.0S 1.0386 1.367e+01 9.377e-G4 1.472e-03 1;717e-06 2.696e-06.

1.1679 2.461e4.01 i.964e-03 2.990e-03 3.514e-06 5.349e-06 1.3652 4.IS~e+01 4.055e.03 ý5;936e-O3 6.993e-06 1.024e-05 Tot .als 3.058e4 03 1.254e-01 2.lBge -6 2.405e-04 4.202e-64 "YA-REPT.00-015-04 ReV.'0 Page 20.of 26 I

Report No.: YNPS-FSS-TBNO1-00 APPENDIX J

~32 ~ 52 9 0&~444 1;0 23l icosf36te EjCUai 556 22E 3i89 6, I2 H, Fý, 41t 233 7T ~

209 ~ G 273, 2 71E1bL-C) 5I7 COO

.1758 ýI36~ 4' 6 CE0115 At 802 P C12 E,7FC',S 1 .'9,11 Re 0 Pag 21 of 26

Report No.: YNPS-FSS-TBNOI-00 APPENDIX K MicroShield v6.02 (6.02-00253)

Page :1FileRef DOS File ;SPA3-EFF-Cs-137.ms6 Date I Run Date September 10, 2004 By 8: 52: 18 AM Cecked Run Time Duration 00:06000 Case Title. SPA3-EFF-Cs-137

Description:

SPA-3 Soil scan - 28 cm radius lpCi/cr/3 Cs-137 and Daughters Geometry: 8 -.Cylinder Volume:- End Shields Source Dimensions:

.Height 15. 0 cl (5.9 in)

Radius 2M.0cm (11.0 in)

Dose Points A ýX y z 0:cm 25cým b.crri 0.0 10 9.8 in 0oin Shields Shield N Dimension Material Density Source 3.69e+04 cm; Concrete .1.6 A*rGap Air 0.00122 Source input: Grouping Method ActualPhoton Energies Nudide curies becquerels iico, Sq/cm, Ba-137m 3A4950e-o08 i.2932e-:003 9..46ooe-007 '350b26-02 7

Cs.137 3.6945e-,008 I.36?Oe+0ý03, 11.bofoe-006 3ý. 600e-002.

Buildup : Thematerial reference is -Source Integration Parameters Radial 20 CIrcumferential 10 Y Di1rection (axial) 10 Results Ei Fluence 5Rate Fluence Rate Exposure Rate Exposure Rate*

Energy hAcivity n MeVfcm /sec .MeV/sec/sec mR/hr mR/hr

. NogBuildup With Buildupi No Buildup With Buildup 0o0045 .. 342Q0o1 4.020e-08 '41133e-0o 2.75e-08: 2M833e-08 0.0318 2.677e+01 4.815e-06 5.834 e-06 4,0t1e-08 4.860e-08 0-0322 4.939e+01 9,260e-06 1129e-o5 7.452eý-08 6.084e-08 0,0364 1.797e+01 5.126e-06 6.688e-06 2.912e-08 38o00e-08 0.6616 11*4le+03 4.442e-02 7,913e-02 8.61ie-05 1.534e-04 Totals 1t271e+03. 4.444e-02 .7.91Se-02 8,628e-05 1.536e04 YA-REPT-00-0 15-04 Rev. 0 Page 22 of 26 I

Report No.: YNPS-FSS-TBNO 1-00 I

APPENDIX L I

YA-REPT-0O0-05-04 Rev. 0 Page.23 of 26 I

U]

Report No.: YNPS-FSS-TBNO1-00

• APPENDIX M Micr0Shield v6.02 (6.02-00253)

Page: :1 File Ref DOS File :SPA3-EFF-Eu-152,ms6 Date Run Date Octobe, 7; 2004 Run Time 11:25;11AM Checked Duration 00:00:00 Case

Title:

SPA-3-EFF-Eu-152

Description:

SPAI3 Seil scan - 28cm radius 1.pCicrm3 Eu-t-52 Geometry; 8 - Cyllnder Voiume - End Shields Source Dimensions:

Height 15.0 cm R.9. ...

..NP Radi.s D................

Poi .....

IDose Povints V A X v .z

1. 1 0.0n 25 cm 0cm' 0.0 In 9.8 gn 0.0 in I

Shields:

Shield H Dimension l4aterial Density Source. 3.69e+04 cml. Concrete 1.6:

,Ail Gap Air- 0;00122 soern Input; Creeping Method - Standard rnndicas lineber of Gioups:2 -2.

Lwevwe Energy Cutoff i 0.01S photons, 0'o61aa ,nduiied Ubrviiy iGrwae 0

Nudide ca-les becrgueri pClftmb Bqkcn Co12 1,945e-009 l.267oa0q,00 1.OlOWe-09 .70e-Buildup-s~he material reference Is - source A0dial' 10.

Y Ditection15s151 Results Exposure Fluence Rate Rate Exposure Rate Energy Activity Fluence Rate MeV/cm3/iec MoVfcni~/se, mR/hr mRR/hr NevPotan/sec Mei' Pheatfleee No tuildup With Buildup NO With Buildup Buildup 2.1460-06 1.790e-07 1 8410 07 6.01S 2.077e+02 2,087e-06. 1.918 e-0 3 131e-04 0.04 4,331e6-04. 1;385L-06 1 507e 04* 2.467e-04 4.014e-07' 6.572e-07 0.05 2.0 220+02 3.8820o+02 8 AI7e-03 3,118e-03 't.819e-06 4.770e-06 1.024e+02 2.097e-03 .448e-06 3,7000-06 0.3. 5 0290-03 .1510:02 ý91540e ý06 2.184e-05 3,8960+02 04 3.555e-03 3.314e-06 6.926e006 7.7 11e+00 3.9846-04 4.010e007 7,819e-07 0.6 11948e-03 31579e-03 3.802e-06 6.985e-06

2. 434e+02 .14*90e-02' 2.005e.02 2;263e 05 3.834-05

.08 1.0 3 .620e-02 6.0580e02 7.042e-05 1.117e-04 1.5. 8.411e-05

.17 le+02, 3,4906-02 4.999C-02 S.871e-05 Totals 3.376a+03 9.635"42 1556e-01 1;740*-04 2,81 7e-04

'YA-REPT-00-01 5-04 Rev, 0 Page 24 of 26 0

Report No.: YNPS-FSS-TBNO1-00 APPENDIX N D

, 0 C 6

YA-REPT-0O-0i 5-04ý Rek. 0 Page 25 of 26

Report No.: YNPS-FSS-TBNOI1-00 APPENDIX 0 Calculated Energy Response (Eberline Instruments)

CPMJmR/h YNPS-FSS-TBN01-00 No.:

Report 100000000 h I19+/-Ei+/-IiI+/-"i .I+/-I 10000000 E f1I x

_.F IJ B+/-1+/-EE*NJI I I+/-IE 1+/-11 I Iý N 1000.000:

I II* II ill x

. I I I1 J I I ItI1 1I 1 II 10000 1'0 1O( E G 1000 10000 ENERGY (key)

YA-REPT-00-015-04 Rev. 0 Page 26 of 26 S

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Report No.: YNPS-FSS-TBNOI-00 S

Appendix C YA-REPT-00-018-05 Use of In-Situ Gamma Spectrum Analysis To Perform Elevated Measurement Comparisons In Support of Final Status Surveys S

Report No.: YNPS-FSS-TBN01-00 a

Use Of In-Situ Gamma Spectrum Analysis To Perform Elevated Measurement Comparisons In Support Of Final Status Surveys YA-REPT-00-018-05 0

Approvals (Print & Sign Name)

Preparer: Greg Astrauckas/Signature :on file Date: 10/10105 Preparer: Gordon Madison, CHP/Signature on file Date: 10/11/05 Reviewer: Jim Hummer,. CHP/Signature on file Date: 10/18/05 Approver (FSS Manager):.

Dann Smith, CHP/Signature on file Date: 11/4/05 Rev. 0 a

Report No.: YNPS-FSS-TBNO1-00 WaP YA-REPT-00-018-05 Rev. 0 Technical Report YA-REPT-00-018-05, Rev. 0 Use Of In-Situ Gamma Spectrum Analysis To Perform Elevated Measurement Comparisons In Support Of Final Status Surveys TABLE OF CONTENTS 1.0 R epo rt ......................................... ........................................................ ................... 2 1.1 Introduction .............................................................................................. 2 1.2 D iscussio n ............................................................................................ . . 2 1.2.1 Detector Description ......................................................... 22..............

1.2.2 Traditional Approach .................................................................. 3 1.2.3 Innovative Approach .................................................................. 4 1.2.4 Investigation Level ................................................................... 4

.1.2.5 D etector Sensitivity ......................................................................... 8 1.2 .6 A rea C overage ...................................... .............. 88..............................

1.2.7 MoistureContent in the Soil Matrix ........................... 9 1.2.8 Discrete Particles. in the Soil Matrix. .......................... 10 1.2.9 Procedures and Guidance Documents ........................................... 10 1.2.10 Environmental Background ...................................................... 11 1.2.11 Q uality C ontrol ....................................................................... 11 1.2.12 Data Collection .... ................................... 12

.1.2.13 Efficiency Calibration.. ......... ............. ......... ......... 13 1.2.14 Data Management .............. ....... ..... ... 13 1.3. Coficlusions/Reconmiendations .......................................................... 14 1.4 References .................... ................................. ................................ 14 Attachments Attachment 1, ISOCS Detector System Photos ............................. ;......................... 15 Attachment 2, Field-Of-View Characterization ............................... 16 Attachment 3, Typical Grid Pattern For In-Situ Gamma Spectroscopy ................. 18

- 1-

Report No.: YNPS-FSS-TBN01-00 YA-REPT-00-018-05 Rev. 0 1.0 REPORT 1.1 Introduction The ISOCS In-Situ Gamma Spectrum detector system manufactured by.Canberra Industries is being employed to perform elevated measurement comparison (EMC) surveys in support of the Final Status Surveys at YankeeAtomic's Yankee Rowe facility. This system uses an HPGe detector and specialized efficiency calibration software designed to-perform in-situ:.gamma-spectroscopy assays. The ISOCS system will primarily be employedto evaluate survey units for elevated measurement comparisons. The ISOCS system can obtain a static measurement at a fixed distance from a pre-determined. location. Count times can be tailored to achieve required.

detection sensitivities. Gamma spectroscopy readily distinguishes background activity-from plant-related licensed radioactivity. This attribute is particularly beneficial Where natural radioactivity introduces significant investigation survey efforts. Additionally, background subtraction-or collimation can be employed where background influences are problematic due to the presence of stored spent fuel (ISFSI).

This technical report is intended to outline the technical approach associated with the useof ISOCS for implementing a MARSSIM-based Final Status Survey with respect to scanning surveys for elevated measurement comparisons for both open land areas and building surfaces. While the examples and discussions in this report primarily address open land areas, the same approach.and methodology will be appliedwhen deriving investigation levels, grid spacing and-measurement spacing for evaluating building surfaces.

I Validation of the ISOCS softwareýis beyond the scope of this technical report.

Canberra Industries has performed. extensive, testing and Validation on both the MCNP-based detector characterization process and the ISOCS calibration algorithms associated with the calibration:software. The full MCNP method has been shown to be accurate to within 5% typically. ISOCS results have been-compared to both.full MCNP and to 119 different radioactive calibration sources. In general, ISOCS is accurate to within 4-5% at high energies and 7-11% at 1 standard deviation for low energies. Additionally, the ISOCS technology has been previously qualified it Yankee Atomic Technical Report YA-REPT-00-022-04, "Use Of Gamma Spectrum Analysis To Evaluate Bulk Materials For Compliance With License Termination Criteria."

1.2 Discussion 1.2.1 Detector Description Two ISOCS-characterized HPGe detectors manufactured by Canberra.

industries have been procured. Each detector is a reverse-electrode HPGe Report No.: YNPS-FSS-TBNO 1-00 S YA-REPT-00-018-05 Rev. 0 detector rated at 50% efficiency (relative to a Nal detector). Resolution for these detectors is 2.2 keV @ 1332 keV. As the project progresses,. other ISOCS detectors (e.g., standard electrode coaxial), if available,.may be used to increase productivity, The key element regarding the use of other types of ISOCS detectors is that'specific efficiency calibrations willbe developed to account for each detector's unique characteristics.

The HPGe detector is mounted on a bracket designedlto hold the detector /

cryostat assembly and associated collimators. This bracket may be mounted in a wheeled cart or in.a cage-like frame. Both the wheeled cart and frame pe-mit.the detector to be oriented (pointed) over a full range from a horizontal to vertical position. The frame's design allows the .detector to be suspended above the ground. Photographs of the frame-mounted system are presented.

in Attachment 1. Duringevaluations of ClassI areas for elevated radioactivity, the detector will generally be outfittedwith the 90-degree collimator. Suspending the detector,at 2 2meters above the target surface..

yields a nominal field-of-view of 12.6 mi The InSpector (MCA) unit that drives the signal chain and the laptop computer that runs the acquisition software (Genie-2000) are mounted either in the frame or on the wheeled cart. These components are battery powered.

Back-up power supplies (inverter or UPS) are available to support the duty cycle. A Wireless network has been installedathe site so that ihe.laptop computers used to run the sy.stems can be completely controlled from any workstation at the.facility. This configuration also enables the savingof data files directly to a centralized file server. Radio communication will be used to coordinate system operation.

1.2.2 Traditional Approach With respect to Class I Survey Units, small areas of elevated activity are evaluated via the performance of scan surveys. The size of the potential area of elevated activity affects the DCGLEmc and is typicallydetennined by that area bounded by the grid points used for.fixed measurements. This area in turn dictates the area factor(s) used for deriving the .associated'DCGLEMc.

These scan surveys are traditionally conducted with hand-held field instruments that have a detection sensitivity sufficiently.low to identify areas of localized activity above the DCGLEMC. Occasionally, the detection sensitivity of these. instruments is greater than the DCGLEMC. In order to increase the DCGLENIc to the point where hand-held instrumnentation can be reasonably. employed, the survey design is augmented to require additional fixed-point measurements. The effect of'these additional measurement points is to tighten the~fixed measurement grid spacing, thus reducingthe area applied to deriving the DCGLEMc and increasing the detection sensitivity criteria.

Report No.: YNPS-FSS-TBNO1-00 YA-REPT-00,018-05 Rev. 0 Background influences (from the ISFSI) and natural terrestrial sources further impact the sensitivity of these instruments. To address these. impacts, the fixed-point grid spacing would again need to be reduced (requiring even more samples) in order to increase the DCGLEMC to the point where hand-held instrumentation can be used. Generally, the collection of additional fixed measurements (i.e. samples) increases. project costs.

Survey designs for Class 2 and Class 3 survey units are not driven by the elevated measurement comparison because areas of elevatedactivity are not expected. In Class 2 areas; any indication of activity above the DCGLw requires further investigation. Similarly, in Class 3 areas, any positive indication of licensed radioactivity also requires.further investigation.

Because the DCGLEMc is not applicable to0Class 2 or Class 3 areas, adjustments to. grid spacing do not occur. However,.the increased field-of-view associated with the in-situ gamma spectroscopy system improves the efficiency of the survey's implementation.

.1.2.3 Innovative Approach In-situ assays allow fixed-point grid spacing to be uncoupled fromthe derivation.of .applicable investigation levels. In contrast to dte traditional approach where the DCGLEmc (based on grid size) determinesboth investigation levels and detection sensitivities, theuseof this technology provides two independent dynamics as follows:.

• Detection sensitivity is determined by the DCGL~mc associated with the (optimal) fixed-point grid.spacing:

• Investigationrlevels are based on the detector's field-of-view and adjusted for.the smallest, area of concern (i:e.. 1.m2 ).

1.2.4 Investigation Level Development of the investigation (action) levels applied to in-situ assay results is a departure from the traditional approach for implementing a MARSSIM survey. Examples are~provided for both open land areas (i.e. soil) and for building surfaces, however the approach for both is identical.

To supportthe use of in-situ spectroscopy to evaluate areas of elevated activity the HIPGe detector's field-of-view was characterized. Attachment 2 presents data from the field-of-view characterization for a detectorconfigured with a 90-.degree collimator positioned 2 meters fromthe target surface.

Alternate configurations will be, evaluated in a similar mamier, before being employed. As exhibited in.Attachment 2, when the detector ispositioned at 2 meters abovethe target surface the field-of-view has a radius of at least 2.3 Report No.: YNPS-FSS-TBNO1-00 I YA-REPT-00-018-05 Rev. 0

• meters. This value was rounded down to 2.0 meters for implementation purposes, introducinga conservative bias (approximately 9%) in reported results. The example provided in this technical report assumes a 2-meter source-to-detector distance, yielding a nominal field-of-view surface area of 12.6 In2 .

Occasionally, alternate source-to-detector distances (using the 90-degree collimator) may be employed, particularly in a characterization or investigation capacity. In such cases, the detector's field-of-view will be calculated by setting the radius equal to the source-to-detector distance, thereby maintaining the conservative attribUte previously described. If alternative collimator configurations-are used to perform elevated measurement comparisons, then specific evaluations will be documented in theform of atechnical evaluation or similar. Associated investigation levels will be derived'using the same approach and methodology outlined below in this section.

After the detector's field-of-view is determined, an appropriate investigation level is developedlto account for a potential one-meter square area of elevated activity. DCGLEMC valuesfor a one-square meter area are presented in Table:

I TABLE 1, SOIL DCGLEMc FOR 1 M2 Soil Soil DCGLrmc DCGLw DCGLw Area Factor for I m1 (pCi/g) (pci/g) for I mi2 (pCi/g)

(NOTE 1) (NOTE 2) (NOTE 3) (NOTE 4)

C0-60 3.8 1.4 I1. 15 A -108m 6.9 2.5 9.2 23 Cs-134 4ý7 1.7 16 28 Cs-137 -82 3.0 22 66 NOTE I - LTP Table 6-1 NOTE2.-Adjusted to 8.73 mRem/yr NOTE 3- LTP Appendix 6Q NOTE 4 - Soil DCGL], (adjusted to 8.73 mRem/yr) for a I W area tm2 The DCGLEMc values listed in Table i do notaccount for a~sburce positioned at the edge of the field-of-view. Therefore, the lm2DCGLEMc values are adjusted via a correction factor. To develop this correction factor; a spectrum free of plant-related radioactivity was analyzed, using two different efficiency calibrations (i.e. geometries). The first scenario assumes radioactivity uniformly distributed over~the detector's 12:6 m2 field-of-view.

The second scenario assumes radioactivity localized over a 1 m2 situated at the edge of the detector's field-of-view. The resultant MDC values were compared to characterize the difference in detection efficiencies between the two scenarios. As expected, the condition with localized (1 m2 ) radioactivity at the edge of the detector's field-of-view yielded higher MDC values. The ratio between the reported MDC values for the two,scenarios is used as a correction factor. This correction factor is referred to as the offset geometry S

ReportNo.: YNPS-FSS-TBNOI-00 YA-REPT-00-018-05 Rev. 0 adjustment factor. The investigation levels for soils presented in Table 2 were calculated as follows:

Nuclide Investigation Level (pCi/g) = (DCGLEMC)

• CF Where: DCGLEMc = (DCGLw or DCGLsuRR)

• AF(I mu,and CF = Mean offset geometry adjustment factor TABLE 2, SOIL INVESTIGATION LEVEL DERIVATION INVESTIGATION lDC DCGLEMc LEVEL 2

pCi/g MDC pCi/g RATIO for 1m pCi/g (NOTE 1) (NOTE.2) (NOTE 3) (NOTE 5) (NOTE 6)

Co-60 0.121 1.86 .0.0651 15 1.0 Ag-108m 0.184 2.82 0.0652 23 1.5 Cs-134 0.189 2.90 0.0652 28 1.8 Cs-137 0.182 2.78 0.0655 66 4.3 Offset Geometry Adjustment Factor 0.0653 (NOTE 4)

NOTE I - Assumed activity distributed over bel 2.6 am'field-of-view.

I n area situated (off-set) at the edge ofthe detector's field-of-NOTE 2- Efficiency calibration modeled for *ao view. The model assumes that all activity is distributed within the I in'.

NOTE 3 - Ratio - (12-6 m' MDC - I m' MDC).

NOTE4 - Tlbemeanvalue of the ratios is applied as the off-set geometry adjustment factor.

NOTE 5 - DCGLErc values for I m2 (froomTable 1)

NOTE 6- Investigation levels derived by applying ofthe off-set geometry adjustment factor (e.g. 0.0653). to the.

DCGLEMc for a I mi area for each.radionuclide.

With respect to building surfaces,.the development of the investigation level is identical to thatfor soil surfaces. The one-meter square DCGLEMc for building surfaces are presented in Table 3.

2 TABLE 3, BUILDING .SURFACE DCGLEMc FOR 1 M DCGLEMc Bldg DCGLw Bldg DCGLw Area Factor For I mi 2

(dpnl00ml) (dpm/00cm') For I m (dpm/I 0n')

(NOTE 1) (NOTE 2) (NOTE 3) (NOTE 4)

Co-60 18,000 6,300 7.3 46,000 Ag7108m 25,000 8,700 7.2 62,600 Cs-134 29,000 10,000 7.4 74,000 Cs-137 63,000 22,000 7.6 167,000 NOTE 1- LIP Table 6-1 NOTE 2- Adjusted to 8.73 mRemI/yr NOTE 3- LTP Appendix 6S NOTE 4- Building DCGL- (adjusted to 8.73 mRemi'yr) for a I mWarea Using the same approach described:for soils, a correction factor to account for efficiency differences due to geometry considerations is developed the one-meter square DCGLEMc. ISOCS efficiency calibrations for activity distributed over the detector's field-of-view and for activity within one-square meter located at the edge of the detector's field-of-view were developed. The MDC values for these two geometries were: compared to characterize the. difference in detection efficiencies. As expected, the condition with localized(1 m2)

II

Report No.: YNPS-FSS-TBNOI-00 S YA-REPT-00-018-05 Rev. 0 radioactivity at the edge of the detector's field-of-view yielded higher MDC values. The ratio between the reported MDC values. for the two scenarios is.

used as the offset geometry adjustment factor. The MDC values, the associated ratios, and the derived investigation level for building surfaces are presented in Table 4.

TABLE 4, BUILDING SURFACE INVESTIGATION LEVEL DERIVATION BUILDING 2 SURFACE 12.6 m t mz Im' 12.6ml DGLF DOGLEMc INVESTIGATION MDC MDC For I ml 'LEVEL, (dprm/100cnr') (dpm/il00cm2) RATIO (dpm/00Ocm') (dpm]100cm-)

(NOTE Il (NOTE:2) (NOTE 3) (NOTE 5) (NOTE 6)

Co-60 785 12,400 10:0633 46,000 2,900 Ag-108rn 839 13,000 .0.0645 62,600 3,900 Cs-134 900 14,200 0.0634 74,000 4,700 Cs- 137 922 14,600 .0.0632 167,000 1 10,600 Offset Geometry Adjustment.Factor 0.0636 (NOTE 4)

NOTE I - Assumed activity distributed over the 12.6 mr field-of-view.

NOTE 2 - Efficiency calibration modeled for a I in area situated (off-set) at the edge of the detector's field-of-view. The model assumes that all activity is distributed within the Lmi.n NOTE 3 -Ratio = (12.6 m2 MDC + 1 mzMD).

NOTE 4 -The meat value of the ratios is applied as the off-set geometry adjustment factor.

NOTE 5 - DCGLCMc values for I M2 (from Table 3)

NOTE 6 - Investigation levels derived by applying of the off-set geometry adjustment factor (e.g. 0.0636) to the, one-square meter DCGLEMC.

In summary, effective investigation levels for both open land areas (i.e: soils) and for building surfaces can be derived and applied to in-situ gamma spectroscopy results. Note the' MDC values associated with the,,detector's field-of-view were well below the derived investigation levels.

The investigatiotn levels presented in Table 2 and Table 4 do not address the use of:surrogate DCGLs. Use of Surrogate DCGLs will be addressed in Final Status Survey Plans, particularly where it is necessary.to evaluate non-gamma emitting radionuclides on building surfaces. When surrogate DCGLs are employed, investigation levels will be developed on.a case-by-case basis using the approach Outlined in this document. Similarly, the offset geometry adjustment factor presented in Table 2 and Table 4 wilI vary for different geometries. Although unlikely, if different geometries are employed, this value will be detenrined on a case-by-case basis using the methodology reflected in Table 2 and will be documented in the applicable Final Status Survey Plan.

For both open land areas and.for building surfaces, when an investigation level is encountered, investigatory protocols will be initiated to evaluate the presence of elevated activity and bound the region.as necessary. Such evaluations may include both hand-held field instnimentation as well as the in-situ HPGe detector system. After investigation activities are completed, 7.

Report No.: YNPS-FSS-TBN01-00 YA-REPT-00-018-05 Rev. 0 subsequent (follow-up) scanning evaluations will most likely be conducted using the in-situ gamma spectroscopy system.

1.2.5 Detector Sensitivity For Class 1 scan surveys, the,minimum detectable concentration is governed by the DCGLEMc associated with the grid, area used to locate fixed-point measurements. The system's count time can be controlled to achieve the required detection sensitivity. Therefore, the grid spacing for the fixed-point measurements can be optimized thus eliminating unnecessary increases to the number of fixed-point measurements while ensuringthat elevated areas between fixed measurement. locations can be identified and evaluated.

Based on preliminary work, it.has been determined that a count time of 900 seconds will yield an acceptable sensitivity for many areas on the site. This count time provides MDC values well below the investigation levels presented in Table 2 and Table 4. Count times will be adjusted as necessary as survey unit-specific investigation levels are derived or where background conditions warrant to.ensure that detection sensitivities are below the applicable investigation level. Since each assay report includes a report of the MDC.

values achieved during the assay, this information is, considered technical support that required MDC values were met.

1.2.6, Area Coverage Based on the nominal 12.6 m2 field-of-view, a.3-meter spacing: between each

.survey point will result in well'over 100% of the survey-unit to be evaluated for elevated activity. This spacing convention typically employs a grid pattern that-is completely independent from the grid used to locate fixed-point miIeasurements. Anexample of the grid pattern and spacing is presentedin Attachment 3.

Alternate spacing conventions maybe appliedon.a case-by-case basis. For instance, spacing may be decreased when problematic topographies are encountered. Note that decreased grid spacing in this context is not associated.

to the fixed-point measurements. Occasionally'it may be necessary to position thedetector at one meter or less from the target surface to evaluate unusual (e.g. curved) surfaces orto assist in bounding areas of elevated activity. In.

cases where 'it may be desirable to increase the field-of-view via collimator or source-to-detector distances, grid-spacing conventions (and applicable

.investigation levels) will be determined using the approach described in this document.

I i,

Report No.: YNPS-FSS-TBNO1-00 YA-REPT-00-018-05 Rev.' 0 1.2.7 Moisture Content in the Soil Matrix In-situ gamma spectroscopy of open land areas is inherently subject to various environmental variables not present in laboratory analyses. Most notably is the impact that water saturation has on assay results. This impact has two components. First, the total activityresult for the assay is assigned over a larger, possibly non-radioactive mass introduced by the presence of water.

Secondly, water introduces .a self-absorption factor.

The i ncrease in sample mass due to the presence of water is addressed by the application of a massimetric efficiency developed by Canberra Industries.

Massimetric efficiency units are defined as [counts per second]/[gammas per.

second per grarn of sample]. Mathematically, this is the product of traditional efficiency and the mass of the sample. When the efficiency is expressed this way, the efficiency asymptotically approaches a constant value as the sample becomes very large (e.g. infinite). Under these conditions changes in sample size, including mass variations from excess moisture, have little impact on the counting efficiency. However, the massimetric efficiency does not

.completely address.attenuation characteristics associated with water in the soil matrix.

To evaluate the extent, of self-absorption, (traditional) counting efficiencies were compared for two densities.. Based on empirical data associated with the monitoring wells, typical nominally dr' in-situ soil is assigned a density of 1.7 g/cc. A density of 2.08 g/cc, obtained from a technical reference publication by Thomas J. Glover, represents saturated soil. .A density of 2.08 g/cc accounts for a possible water contentof 20%. A summary of this comparison is presented in Table 5.

TABLE 5, COUNTING EFFICIENCY COMPDARISONS Efficiencies Deviation due to density keV 1.7 gcc 2.08 g/cc increase (excess moisture) 434 3.3 E-6. 2.7 E-6 -18:7%

661.65 2.9 E-6 2.4 E-6 -17.5%

1173.22 2.5.E-6 2.1 E-6 -B5.4%.

1332.49 2.4 E-6 2.1 E-6 -14.8%

In cases when the soil is observed to contain more than "typical" amounts of water, potential under-reporting. can be~addressed in one of two manners. One way is to adjust the investigation level down by 20%. The second way is to reduce the sample mass by 20%. Either approach achieves the same objective: to introduce a conservative mechanism for triggering the investigation level where the presence of water may inhibit counting efficiency. Thse specific mechanism to be applied will be prescribed in implementing procedures.

Report No.: YNPS-FSS-TBNO 1-00 YA-REPT-00-018-05 Rev. 0 The presence of standing water (or ice or snow) on the surface of the soil being assayed will be accounted for in customized efficiency calibrations applied during data analysis activities.

1.2.8 Discrete Particles in the Soil Matrix Discrete particles are not specifically addressed in the License Termination Plan. However, an evaluation was performed assumingall.the activity in the detector's field-of-view, to a depth of 15 cm, was situated in a discrete point-source configuration. A concentration of 1.0 pCi/g (Co-60), corresponding to the investigation level presented in Table 2, correlated to a discrete point-source of approximately 3.2 piCi. This activityvalue is considered as the discrete particle of concern. Since the presence of any discrete particles will most likely be accompanied by distributed activity, the investigation level may provide an opportunity to detect discrete particles below 3.2 ýtCi.

Discrete particles exceeding this magnitude would readily be detected during characterization or investigation surveys. The MDCs associated with hand-held field. instruments used for scan surveys are capable of, detecting very small areas of elevated radioactivity that could be present in the form of discrete point sources. The ininimum. detectable particle activity for these scanning.instruments and methods correspond to a small fraction of the.TEDE limit provided in 10CFR20 subpart E. Note that the MDC values presented in Tabl6 2 are significantly lower than those published in Table. 5-4 of the License Termination Plan.

Whenthe investigation.level in aClass 1 area.is observed, subsequent investigation surveys will be perforned to include the use of hand-held detectors. The detection sensitivities of instruments used for these surveys have been previously addressed:in the LTP. Furthermore, discrete point sources do not contribute-to the uniformly distributed activity ofthe survey unit. it is not expected that such sources at this magnitude would impact a surveytunit's ability to satisfy the applicable acceptance criteria.

Noting tliat Class 2 or Class 3 area survey designs do not employ elevated measurement comparisons, associated investigation levels are based on positive indications of licensed radioactivity above the DCGLw or above background. Because such areas are minimally.impacted or disturbed, potential discrete particles woul'd most likely be situated near the soilsurface where detection efficiencies are highest.

1.2.9 Procedures And Guidance Documents General.use of the portable ISOCS system is administrated by departineital

implementing procedures that address the calibration and operation activities as well as analysis of the data. These procedures are listed as follows:

- 1;0 -

0I

ReportNo.: YNPS-FSS-TBNOI-00 YA-REPT-00-018-05 Rev. 0 0 DP-8869, "In-Situ (ISOCS) Gamma Spectrum Assay System Calibration Procedure."

• DP-8871, "Operation Of The Canberra Portable ISOCS Assay System."

• DP-8872, "ISOCS. Post Acquisition Processing And Data Review."

Where the portable ISOCS system is used for Final Status Surveys, the applicable FSS Plan will address detector and collimator configurations,

.applicable (surrogated) investigation levels, MDC requirements, and appropriate Data Quality Objectives, as applicable.

A secondary application of the portable ISOCS system is to assay surfaces or bulk materials for characterization or unconditional release evaluations. Use of the portable ISOCS system for miscellaneous evaluations will be administrated uider a specific guidance document (e.g.. Sample Plan, etc.).

Operating parameters :such as physical configuration, efficiency calibrations, count times, and MDCs will be applied so as to meet the criteria in the associated controlling documents. Such documents will also address any unique technical issues associated with the application.and may provide guidance beyond that of procedure AP-0052, "RadiationProtection Release of Materials, Equipment and Vehicles."

1.2.10 Environmental Backgrounds If background subtraction is used, an appropriate background spectrum will be collected and saved. Count times for environmental backgrounds should exceed the count time associated with the assay. In areas where the.

background radioactivity~is particuiarly problematic (e.g. ISFSI), the background will be characterized to the point of identifying gradient(s) such that background subtractions are eitherappropriate or conservative.

Documentation regarding the collection and application of environmental backgroundswill be provided as a component of the final survey plan.

1.2.11 Quality Control Quality Control (QC)activitiesfor the ISOCS system ensure that the energy calibration is valid and detector resolution is within specifications. A QC file will be set up for each detector system to track centroid position, FWHM, and activity. Quality Control counts will be performed on a.shiftly basis prior to the system's use to verify that.the.system's energy calibration is valid;. The Na-22 has a. 1274.5 keV photon which~will.be the primary mechanism used for performance monitoring. If the energy calibration is found to be out of an acceptable tolerance, (e.g. greater than +/-4 channels), then the-arnplifier gain may be adjusted and a follow-up QC count performed. If the detector's resolution is found to be above the factory specification, then an evaluation ReportNo.: YNPS-FSS-TBNOI-0O 4II 4I

Report No.: YNPS-FSS-TBNO1-00 S YA-REPT-00-018-05 Rev. 0.

will be performed to determine if the detector should be removed from service and/or if the data is impacted. Evaluations associated with QC counts shall be documented. Such documentation may be limited to a remark directly on the applicable QC report or in a logbook if the resolution does not render the system out of service. Otherwise the evaluation should be separately documented (e.g. Condition Report, etc.) so as to address the impact of any assay results dbtained since the last acceptable QC surveillance.

Where it is determined that background subtraction is necessary, a baseline QC background will be determined specific to that area or region. When background subtraction is required, a QC background surveillance will be performed before a set of measurements are made~to verify the applicability of the.background to be*subtracted. Due to the prevailing variability of the

• background levels across the site, the nature and extent of such surveillances will be on a case-by-case basis and should be addressed in the documentation associated with the applicable survey plan(s).

In addition to the routine QC counts, each assay report is routinely reviewed

'with respect to K-40 to provide indications where amplifier drift impacts nuclideidentification routines. This review precludes the necessity for sPecific (i.e. required) after-shift'QC surveillances. It also minimizes investigations of previously collected data should the system fail a before-use QC surveill'ance on'the next day of use.

1.2.12 Data Collection Data collection to support FSS activities will be administered by a specific Survey Plan.. Survey Plans may include an index of measurement locations with associated spectrum filenames to ensure that all the required measurements are made and results appropriately managed. Personnel specifically trained to, operate the system will perform data collection

.activities.

Data collection activities will address environmental conditionsthat may Inpact soil moisture content. Logs shall be maintained so as to provide a mechanism to annotate such conditions to ensure ihat efficiency calibration files address the in-situ condition(s). In extreme cases (e.g. standing water,

. etc.) specific conditions willbe addressed to ensure that analysis results reflect.

the conditions. As previously discussed with:respect to water, when unique environmental conditions exist that may impact analysis results, conservative compensatory factors will be applied to the analysis of the data.

p

ReportNo.: YNPS-FSS-TBNOI-00 YA-REPT-00-018-05 Rev. 0 1.2.13 Efficiency Calibration The central feature of the portable ISOCS technology is to support in-situ gamma spectroscopy via the application of mathematically derived efficiency calibrations. Due to the nature of the enviromnent and surfaces being evaluated (assayed), input parameters for the ISOCS efficiency calibrations will be reviewed on a case-by-case basis to ensure the applicability of the resultant efficiency. Material densities applied to efficiency calibrations will be documented. In practice, a single. efficiency calibration file may be applied to the majority of the measurements.

The geometry most generally employed will be a circular plane assuming uniformly distributed activity. Efficiency calibrations will address a depth of 15.cm for soil and a depth up to 5 cm for concrete surfaces to account for activity embedded in cracks, etc. Other geometries (e.g. exponential circular plane, rectangular plane, etc.) will be applied if warrantedby the physical attributes of the area or surface being evaluated. Efficiency calibrations are developed by radiological engineers who have'received training with respect to the ISOCS software, Efficiency calibrations will be documented in accordance with procedure DP-8869, "In-Situ (ISOCS)Gamma Spectrum Assay System Calibration Procedure."

1.2.14 Data Management Data management will be implemented in various stages as follows:

• An index or log will be maintained to account for each location where evaluations for elevated activity areperformed. Raw spectrum files will be written directly or copied to a central file server.

Data Analysis - After the spectrum is collected and analyzed, a qualified Radiological Engineer will review the results. The data review process includes application of appropriate background,.

nuclide libraries, and efficiency calibrations. Data reviews also verify assay results with respect to the applicable investigation levels and the MDCs achieved. Data reviews may include monitoring system performance utilizing K-40. When the data analysis is completed, the.

analyzed data file will be archived to a unique directory located on a central file server.

Data Reporting - The results of data files whose reviews have been completed and are: deemed to be acceptable may be uploaded to a central database for subsequent reporting and statistical afialysis.

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Report No.: YNPS-FSS-TBN01-00 YA-REPT-00-018-05 Rev. 0

• Data Archiving - Routinely (daily) the centralized file server(s) where the raw and analyzed data files are maintained Will be backed up to tape.

1.3. Conclusions/Recommendations The in-situ gamma spectroscopy system is a cost-effective technology well-suited to replace traditional scanning survey techniques to eyaluate areas for elevated radioactivity. The static manner in which this system is operated eliminates many variables and limitations inherent to hand-held detectors moving over a surface. This system provides a demonstrably lower detection sensitivity than those offered by hand-held field instruments. This attribute qualifies this. system as an Alternative, technology in lieu of hand-held Nai field instruments in areas where background radiation levels would prohibit the use of such detectors to evaluate for elevated gross activity. The MDC to which'this system will be operated satisfies (or exceeds) criteria applied to traditional scan surveys using hand-held field instruments.

Effective investigation levels for both open land areas (i.e. soils) and for building surfaces can be derived and applied to in-situ gamma spectroscopy results. Where, surrogate DCGLs are employed, investigation levels will developed on a case-by-case basis using the approach outlined in this document.

The manner in which investigation levels are derived employs several conservative decisions and assumptions. Additionally, adequate spacing applied to scannmig survey locations yields an overlap in surface coverage providing 100-percent coverage of Class 1 areas and redundant opportunities in a significant portion of the survey area to detect localized.elevated activity.

1.4 References

1. YNPS License Termination Plan5 Revision 1

2. Multi-Agency Radiation Survey And Site InvestigationManual (MARSSIM)

Revision.1, 2000

3. Canberra User's Manual Model S573 ISOCS Calibration Software, 2002

4. Decommissioning Health Physics r A Handbook for MARSSIM Users, E.W.

Abelquist; 2001

5. Canberra's Genie 2000 V3.0 Operations Manual, 2004

6. In-Situ (ISOCS) Gaimma Spectrum Assay System.Calibration Procedure DP-8869, Revision 0

7. Operation of the Canberra Portable ISOCS. Assay System DP-8871 Revision 0

8. Technical Ref., by Thomas J. Glover.

Report No.: YNPS-FSS-TBNO1-00 YA- RE 1P-00-018-05 Reev. 0 Attacii*,nt I PoMtablUe ISC)CS Detector Systei Photoc

-,A

-.15 -

Report No.: YNPS-FSS-TBNOI-O0 YA- R EP'l'-O1-O 105 Rev.. 0 Attachmteinit 2 Field-Of-Vjl, Chaiacterization Generaly, the IW*M.c decicoorwil] 4e oimlfitlcd with it ecollimator sit Ot2 ncdters peindiculnr to the being evaluutcd. Note ihat ehrateri~ng t]* detot-s lielt-o V-view bL-'ae bould be perifonned wvithout a source by( comparing ISOCS-generated eoliri~utiei for var'ioW

&onmitris If a diffctenti.olinAtor configuralion is to b.Cmployed a sinilar fi14-J-vicw chraclefization WlIl be pciforwrcd, To Ifild;of-view for this configuration, a scric of measurements were, inade .it various i Iali[f-*-h o ,-o1 rclttie it) the ccenTe of the riofercn"evplaaie. The source vse for these met arvmlltsA~ 4

1. pci Co-60 ojut-soure, vith a physical Size of approximacly cmn, Each spectmi-m wis ana yzed t.,a pointtt ourn,446lth %wilhand without background sutwioct, It was observed that the de~t~ct& reponi~ded! .qi, !llto the poini isoumic.

Figure I presdnti.te results with-background subtractiom applied. NoteI tiiat there Nsa good c-lmlatinii with the expecred nominAl activity and that outsidethe 2-7mete rAdius of thE %"8orking-field-of-vie (i6e,. at900 inche )sore deletorrespense occurs. TIbs validates Itiat 1e :correct, attenki oi aIlot areapplied to the, algorithms used to eoiiiptte%the ecllic.iencv calibrationu POINT SO0URCE TES-1 SZ,,

0.3 0it 4$ a 0 72 B4 Vigr.2 shows* :th eflfe ci, pantd rivýed nmi4eals .presentin the refewnee bakground.,which ind~icates- ani inere-esing cmer-i-*ponse the Further the point~stourc.. is .Iified,.off center; 1:)¢/tector r-esponse outsidc the aslsumed fi ¢e 2-meter) field-of-view woQtýid yieldc)4 ser.att-- results, Normally, soturce imin adjaccn ito survey units should bc reduced to ,*liminat,. background the interference;

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Report No.: YNPS-FSS-TBNOI1-00 I

6

Report No.: YNPS-FSS-TBNO 1-00 S YA-RETTNX)0118-04J5 Rev

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Report No.: YNPS-FSS-TBNOI-00 YA-REPT-00-01 8-05 Rev: 0 Attachment 3 Typical Grid Pattern For In-Situ Gaminma Spectroscopy K

Typical Scan Grid Pattern (For 2m scan height using 900 collimator.)

3~'=Scan Point Location Q =zSan Area Footprint Report No.: YNPS-FSS-TBNO1-00 Appendix D ALARA Evaluation TBN-01 Units 2 through 8 and TBN-01-01 and TBN-01-09 to TBN-01-17

Report No.: YNPS-FSS-TBNOI-00 Bases for ALARA Analysis of Survey Area TBN-01, Units 02 through 08 General: TBN-01, Units 02 through 08 consist of the Circulating Water Discharge line. It is being treated as a structure, and therefore will use the DCGL associated with a building that could be occupied by non-radiation workers. In fact, the line will filled with flowable fill, which will harden and prevent such occupancy. The following facts and assumptions underlie the bases used for this ALARA Evaluation.

1. Before FSS takes place, the sediment will be removed and the inside surfaces will be washed.

2. The characterization surveys show very little residual activity (<DCGL) on the inside surfaces after scraping off the sediment, without washing.

3. If any part of the pipe can be expected to have elevated levels, it would be the part that had standing water in it for most of the last 12 years. This constitutes approximately half of the 645 square meters or 322 square meters. Within this area, the activity is expected to be uniformly distributed.

4. Further remediation would require mechanical removal of the outer surface, e.g., grinding, because washing will have already been done.

5. It is assumed that grinding would go no faster than FSs scanning, which has been estimated at 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> for the entire surface. Half the area would take 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

6. Assume that the operating equipment requires two men in the pipe plus a hole-watch or three men total.

7. Assume that the cost to the project is $50 per man-hour.

8. Conservatively assume that no specialized equipment needs to be rented or purchased.

9. Assume that this process would remove 90% of the remaining activity.

10.Since no people will actually be able to occupy the structure, assume that the population density for open land applies, instead of that for buildings.

11 .The volume of solid waste removed would be small, estimated at 0.1 cubic meter.

Bases:

1.: Cost of remediation (Item A.1. on worksheet) 3 men x 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> x $50/man-hour = $6,000

2. Cost of waste disposal (A.2.b.)

$19/cubic foot, from Generic ALARA Review, YA-REPT-00-003-05

$19/cubic foot x (35.3 cubic feet/cubic meter) = $671/cubic meter

3. Shipping distance (A.4.a)

-4100 round-trip from Rowe, MA to Memphis, TN, which is the nearest place that such waste is likely to be shipped. (Data from Yahoo! Maps)

4. Worker Dose (A.5.a.)

No measurable worker dose will be picked up because this is not in a radiation area.

I

Report No.: YNPS-FSS-TBNO 1-00 I Calc of ALARA Action Level (AL) C.1.

C.2.

C.3.

C.4.

0.9 0.07 70 0.0004 F = removable fraction for remediation being evaluated r monetary discount rate N = Number of years over which the collective dose is calculated PD = population density for the critical group C.5. 322 A = area being evaluated Cost(T): $6,085 Total cost of remediation Lambda 1.32E-01 decay constant (/y) 1-eA-(r+lambda)*N = 1.OOE+00 AL= 211.55 AL = (Cost(T)/($2000*C.4*0.025*C.1*C.5))*((C.2+Lambda)/(1l-e^A((C.2+Lambda)*C.3)

Formula from LTP, Appendix 4A 2

Report No.: YNPS-FSS-TBNOI-00 Survey Area: TBN-01 Survey Unit: 01 and 09 II through 17

1. Cost of performing remediation work (CostR) $3,840

2. Cost of waste disposal (CostD)= (2.a) * (2.b) $810

a. estimated waste volume 1 m3

b. cost of waste disposal 810 $/rn3

3. Cost of workplace accident (Coskcc) = $3,000,000 person1

• 4.2 x 108h-1 * (3.a) $4

a. time to perform remediation action 32 person-hours

4. Cost of traffic fatality (COStrF) =

($3,000,000

• 3.8 x 10- km1 * (2.a) * (4.a)}/(4.b) $12

a. total distance traveled per shipment 1481 km 3 3

b. waste volume per shipment 13.6 in , if unknown, use 13.6m as a default value

5. Cost of worker dose (Costwocse) = $2,000 per person-rem * (5:a) * (5.b) $0

a. workerTEDE 0.00001 rem/h

b. remediation exposure time 32 person-hour Cost! $4,666 Ave. Conc Relative Radionuclide (dom/100~cm2'l DCGL (dvm/lOOcm2) Fraction DCGL Fraction H-3 0.00E+00 0.OOE+00 0.0000 C-14 0.OOE+00 0.OOE+00 0.0000 Fe-55 0.00E+00 0.00E+00 0.0000 Co-60 Ni-63 Sr-90 6251 0.OOE+00 0.OOE+00 6251 1.00E+00 0.00E+00 0.OOE+00 1.0000 0.0000 0.0000 9

Nb-94 0.00E+00 0.00E+00 0.0000 Tc-99 0.OOE+00 0.OOE+00 0.0000 Ag-1 08m 0.OOE+00 0.OOE+00 0.0000 Sb-125 0.OOE+00 0.OOE+00 0.0000 Cs-1 34 0.OOE+00 0.OOE+00 0.0000 Cs-1 37 0.OOE+00 0.OOE+00 0.0000 Eu-152 0.OOE+00 0.OOE+00 0.0000 Eu-1 54 0.OOE+00 0.OOE+00 0.0000 Eu-155 0.OOE+00 0.OOE+00 0.0000 Pu-238 0.OOE+00 0.OOE+00 0.0000 Pu-239 0.OOE+00 0.OOE+00 0.0000 Pu-241 0.OOE+00 0.OOE+00 0.0000 Am-241 0.OOE+00 0.OOE+00 0.0000 Cm-243 0.OOE+00 0.OOE+00 0.0000 Total Concentration 6.25E+03

[*otal DCGL Fraction 1.00

• Co-60 concentration assumed to be at the wrst case (I.e. at their DCGL values). Concentrations at or above these levels automatically warrant remediation.

0 3

ReportNo.: YNPS-FSS-TBNOI-00 II Calculation of ALARA Action Level (AL) 1

1. Removable fraction for remediation action being evaluated 1

2. Monetar discount rate 0.07 y

3. Number of years over which the collective dose is calculated 70 y 2

4. Population density for the critical group 0.09 people/m

5. Surve2Y unit area 1 m Radionuclide AL 5234 5234 2617 5234 2617 2617 2617 H-3 I <MDA 410 4.1 20.5 4.1 20.5 20.5 20.5 0.086 0.030 0.288 0.161 0.036 0.054 0.030 C-14 <MDA 204 121 101 474 93 063 035 Fe-55 <MDA 1 1 1 1 1 1 1 Co-60 8.45E+03 2617 2617 2617 5234 5234 2617 2617 Ni-63 <MDA 20.5 20.5 20.5 4.1 4.1 20.5 20.5 0.030 0.035 0.285 0.366 0.052 0.082 0.111 Sr-90 <MDA 003 457 72, 081 97 105 529 Nb-94 <MDA 1 1 1 1 1 ' 1 1 Tc-99 <MDA 2617 2617 2617 2617 2617 2617 Ag-108m I <MDA 20.5 20.5 20.5 20.5 20.5 20.5 0.169 0.037 0.030 0.078 0.031 0.054 Sb-125 <MDA 718 898 029 125 603 063 Cs-1 34 <MDA 1 1 1 1 1 1 Cs-137 <MDA Eu-152 <MDA Eu-154 <MDA Eu-155 <MDA Pu-238 <MDA Pu-239/240 <MDA Pu-241 <MDA Am-241 <MDA Cm-243/244 <MDA m of Als8.45E+03 AADCGL Fraction <

ALARA AL?

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