DRC-2018-005808 - 0901a068808478fc

ENERGYSOLUTIONS
June 12, 2018 CD18-0108
Mr. Scott T. Anderson
Director
Utah Division of Waste Management and Radiation Control
195 North 1950 West
Salt Lake City, Utah 84114-4880
Div of Waste Management and Radiation Control
JUN 1 2 2018
77-t-200-X55
Subject: Radioactive Material License UT 2300249; Expanded WMG
Characterization Summary of the San Onofre Nuclear Generating
Station's Unit 1 Reactor Pressure Vessel
Dear Mr. Anderson:
EnergySolutions herein offers an expanded WMG summary of the characterization of the
San Onofre Nuclear Generating Station's Unit 1 Reactor Pressure Vessel (SONGS RPV),
replacing that previously attached to the request for written concurrence from the
Division of Waste Management and Radiation Control with application of the U.S.
Nuclear Regulatory Commission's Branch Technical Position on Concentration
Averaging and Encapsulation to the classification of the SONGS RPV (via CD08-0097).
In response to a verbal inquiry received from Division staff, WMG expanded their
discussion in the attached characterization summary document regarding the additional
radiological surveys of the SONGS RPV Core Barrel, Core Baffle and Core Formers and
how these surveys were used in the characterization calculations to provide a more
accurate Nickel-63 activity for the SONGS RPV.
EnergySolutions herein reaffirms its request for the Division's written concurrence that
its proposed application of the NRC Branch Technical Position on Concentration
Averaging and Encapsulation and that the SONGS RPV can be disposed at Clive as Class
A LLRW subject to the generator's final characterization and classification. Should there
be any questions regarding this revised Characterization Summary, please contact me at
801-649-2000.
Sincerely,
Vern C. Rogers
tit e Rr40 Jun 12 2018 9:10 AM
Vern C. Rogers
Manager, Compliance and Permitting
cc: Don Verbica, DWMRC
enclosure
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111 [phone] • Fax: [phone] • www.energysolutices.com
WMG Overview of the Characterization and Classification of the SONGS Unit 1
Reactor Vessel Package
The SONGS 1 Reactor Vessel and internals were characterized and classified using
neutron activation analysis. Neutron activation analysis is the process of calculating
radioactivity in materials exposed to neutrons. Input parameters for the analysis
included the reactor physical characteristics and dimensions, initial material composition
for each element and the irradiation history. The irradiation history for the SONGS 1
reactor vessel and internals was taken straight from the reactor operating history which
is shown below in Table 1.
Table 1
SONGS 1 Operating History
Cycle Start
Date
Stop
Date
Length Total
Days Days
EFPDs Capacity
Factors
1 01/01/68 10/02/70 1005 1054 631.2 62.80
2 11/20/70 12/25/71 400 461 354.0 88.49
3 02/24/72 06/01/73 463 516 414.2 89.45
4 07/24/73 03/14/75 598 638 449.0 75.08
5 04/23/75 09/30/76 526 719 479.2 91.10
6 04/11/77 09/15/78 522 573 430.7 82.51
7 11/05/78 04/09/80 521 955 452.8 86.91
8 06/17/81 11/29/85 1626 1865 393.2 24 .18
9 07/26/86 11/28/88 856 1034 486.3 56.81
10 05/25/89 06/30/90 401 622 296.6 73.95
11 02/06/91 11/30/92 663 663 536.0 80.85
The analysis methodology used is commonly referred to as the ANISN/ORIGEN
methodology since the ANISN discrete ordinates neutron transport code is used to
calculate the flux levels within the reactor regions for input into the 0RIGEN2 program
which performs the activation calculations. The ANISN/ORIGEN methodology has been
used extensively in the industry for activation analysis of decommissioned reactors.
WMG has used this methodology to characterize and classify 21 commercial reactors
and 19 research reactors over the past 25 years. This methodology has been reviewed
by the NRC and approved under prior licensing actions for decommissioned reactors.
June 11, 2018 Page 1 of 4
The results of this analytical method can be improved using empirical data to
benchmark or normalize the results to measured data. The three main sources of
empirical data used were the reactor surveillance capsule results, intact reactor vessel
radiation surveys and radiation surveys of component segments after internals
segmentation had been completed. These radiation surveys were not available at the
onset of the project, so the results are refined as the project progresses and more
information becomes available.
The initial results were normalized to the surveillance capsule data which reports the
maximum neutron fluence at the reactor vessel clad interface. Once all the spent fuel
high level waste was removed from the reactor for long term storage on site, radiation
surveys were performed inside and outside the reactor vessel in August of 2001. These
intact survey results showed the characterization results were reasonable and
bounding, but it was difficult to discern contributions from various components on dose
rates taken inside the reactor vessel where the detector probe was surrounded by the
source. The characterization results through this part of the process are documented in
WMG-20004-9088, which went through 6 revisions between February of 2000 and
October of 2002. The reported Co-60 activity for the Greater-Than-Class-C (GTCC)
components as measured internal to the RPV was 1.00E+05 curies as of the reference
date, which equates to 1.10E+05 as of the survey date accounting for decay.
In December of 2001, after reactor internals segmentation operations had been
completed, radiation surveys of the core baffle, core formers and core barrel were
available. Component sections were packaged into GTCC cannisters and detailed
radiation surveys were performed in an area of low background. The GTCC cannisters
are stored on site along with the spent fuel high level waste. The radiation survey
results are attached and summarized in the following table.
After nearly 9 years of decay between shutdown and the 2001 radiation surveys, Co-60
was the only remaining gamma emitting radionuclide in any appreciable abundance.
Therefore, all the measured gamma radiation was attributed to Co-60. Dose to curie
conversion techniques were used to calculate the Co-60 activity as of December, 2001.
The results showed that the measured results were an average of 2.1 times lower than
the expected results. Therefore, a normalization factor of 2.1 was used to adjust the
characterization results for all components. These results, which were normalized to
the component specific dose rates, were first reported in 2008, using the same scaling
factors initially developed for the non-gamma emitting radionuclides such as Ni-63.
These are the final characterization results which only change due to radioactive decay
going forward. These final results were decay corrected to the earliest anticipated
shipping date of 12/1/2018, and are documented in WMG Report 17-230-RE-218, "San
Onofre Unit 1 Reactor Vessel Package Updated Classification Status".
June 11, 2018 Page 2 of 4
Table 2
SONGS 1 RPV Storage Canister Data
Canister
ID No. Contents
Net
Weight
lbs.
Maximum
Dose Rate
R/hr 06"
Average
Dose Rate
R/hr 06"
Co-60 at
Measurement
L2 Core Barrel 2789 1600 697 1.75E+03
L3 Core Barrel 2719 1000 774 1.91E+03
L4 Core Barrel 2773 1600 879 2.20E+03
L5 Core Barrel 2012 500 358 7.19E+02
L6 Core Barrel 2708 1000 692 1.70E+03
L7 Core Barrel 2177 2200 799 1.70E+03
S2 Core Baffle 1948 6000 3850 7.30E+03
S3 Core Baffle 1902 7000 4158 7.77E+03
S4 Core Baffle 1566 4500 3458 5.74E+03
S5 Core Baffle 2296 6000 4483 9.48E+03
S6 Core Baffle 1850 6000 3850 7.07E+03
S7 Core Formers 1430 2400 1300 2.05E+03
L1 Core Formers 1497 3400 1542 2.64E+03
Total 5.20E+04
Note: Dose Rates taken at 6"
underwater
Original Co-60 Activity from the Core Barrel, Core Baffle and
Formers
Co-60 Normalization Factor = 1.10E+05 /
5.20E+04 = 2.1
1.10E+05
Characterization of activated metals includes calculating radioactivity for easy to detect
nuclides, such as Co-60 and hard to detect nuclides such as Ni-63, Fe-55 etc. The
hard to detect nuclides are calculated by using scaling factors relative to Co-60 which
are calculated from the 0RIGEN2 output. Once the Co-60 is determined from
measured radiation survey results, the hard to detect nuclides can be calculated using
the scaling factors. The activity of the hard to detect nuclides tracks with Co-60 activity.
Therefore, when Co-60 goes down as a result of a normalization calculation, all the hard
to detect nuclides activities are also reduced.
June 11, 2018 Page 3 of 4
The final results meet the limits for Class A waste provided the weight and volume of
the encapsulation media is included in the concentration calculation as allowed in the
Branch Technical Position on Concentration Averaging and Encapsulation. Ni-63 is the
classification controlling nuclide at 88% of the Class A limit. The Ni-63 activity was
refined over the course of the analysis based on the availability of more accurate
information and radioactive decay. A summary of the Ni-63 activity is provided in
Table 3 below.
Table 3
SONGS 1 RPV Nickel-63 Activity
Report
Date
Ni-63
Curies
Notes
Oct
2002 • 1 14E+04
Activity reported in WMG 20004-9088 R6 Table 5-1
based on internal intact radiation surveys and
surveillance capsule results performed on
8/30/2001.
Feb
2008 5. 14E+03
Activity normalized using more accurate survey
results on segmented components removed and
surveyed externally from the RPV and then
decayed to 2/1/2008 in WMG report 07-064-RE-
091.
July
2017 4.79E+03
Activity decay corrected to anticipated shipping date
of 12/1/2018 (6209 days).
The reactor vessel package was filled with low density cellular concrete grout for
structural stability. The interior grout was added to prevent movement of components
during transportation. The layer of grout between the vessel wall and the package shell
was added for structural stability and to absorb impact from conditions normally incident
to transport. In addition, the SONGS RPV is packaged within a three-inch thick steel-
walled shipping and disposal package to comply with U.S. Department of Transportation
regulations and will be manifested as Class A waste.
June 11, 2018 Page 4 of 4
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Reference Number
S0123-VII-20.9
Pita 11
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Approval Date:tit/446i Time:
Form Number
SCE HP (1) 259-17
REV.2 08/01/00
SURVEY DESCRIPTION; Trans Nuclear West greater than
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TECHNICIAN Page 7 of 15
(for this survey)
Form Number
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Page g of 15
(for this survey) '
Reference Number
S0123-VII-20.9
Waste Can Under Water Weight 11(014 tbs. Load Cell Nurnberkilien 5ekatIt Cal. Due Appnova! Da e: hpiq Time: 12.7.4yo
Form Number
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Page 5 at
(for this survey)
Reference Number
SO123-VII-20.9
SURVEY DESCRIPTION: Trans Nudear West greater than
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REMARKS: AlIgnmentarrows are used to mark the
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2
3
4
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7
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20
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O Post-Decon fJ Pra-Job
O Shipment/Reoelpt El Source/Leak Test
al Other Gra
SURVEY NO.
EQUIP. ID.
90 Degree 6"
I Stand Off
toco
1000
000
Highest Contact 5,0900
Dose Rate
MO NO.
REPRO.
1
0 Degree 6"
Stand Off
2e0C)

75%
2 3q00
18"
11' 25%
Highest 6" Stand Off .306
Dose Rate
2.00 t o (
DATELij c" TIME
NO. (t
12ct, I Page of
270 Degree 6"
Stand Off
(900
1 MO
Waste Can Under Water Weight ) itag(61 lbs. Load Cell Number
APP
ut.G.
CZ Approval Date: Time:
36"
50%
3 I ?CO
Print
Sign
Page 7
(for this survey) •
Reference Number
50123-VII-20.9
Form Number
SCE HP (1) 259-17
REV.2 OB/01/00
180 Degree 6"
Stand Off
7 / 500
8 2Z00
g I7ôû
DPW100Clie Of 1710111/100CM* Ow-CW
DPM/100cm" OPM Or 100Crtla Ifif/hfilOOCMx or OW-CW <MDCR
REV.2 08/01/00
%IC_ Form Number
Slgn 0.0.4._ SCE HP (1) 259-17
— Approval Date: rzlifolTime:. tya
54"
8
.5cx)
Cal. Due 3/17/02-
'Y No. NO.
TIME /Zoe-) — SONGS
UNIT 1 SURVEY REASON Post-Decon Pre-Job SURVEY NO.
AREA 0 Routine ShIpment/Recelpt MONO.
ELEV Job Coverage 0 Source/Leak Test REP NO.
ROOM Pwr Entry % ai Other Gra- EQUIP. ID.
7' 1" Waste Can Serial number L 2-
370
Waste Can Under Water Weight ZgOLI lbs. Load Cell Number
DATE /2 / I of
Masslinn
10 25
11
12
13
14
15
SURVEY DESCRIPTION: Trans Nuclear West greater than
Class C waste can survey.
REMARKS: Alignment a rows are used to mark the
0 Degree survey side.
Dose Rates In R/hr
Dose Rate Survey Only OP 'DEC k `Asiet) *-ZIN
Cornzphvie4r 'PoigEi>.. ARA, cA Abippre Gxec z GgrAireP 7-444 elms C Instruments used
PRzx
/3fg TECHNICIAN
Di7 4.41Fer t. it;
Ar—egL4,
APPR
RADIOLOGICAL SURVEY :e 011-oo7--
Acno2.iioa I
S kcs "
Serlal No.
ode
Page
a
DPM 100cma or
<MOOR
SURVEY CLASS
Boundary
Trend Pt.
General Area
Component
0 Individual
Page /0 of /5 .
(for this survey)
Reference Number
S0123-VII-20.9
of
36"
0 Degree 6"
Stand Off
1(4900
75%
2 Ì
50%
90 Degree 6"
I Stand Off
5oo
Highest Contact 9-706
Dose Rate
270 Degree 6"
Stand Off
goo
LIO0
18"
25%
Highest 6" Stand Off (GOO
Dose Rate
180 Degree 6"
Stand Off
7 2. ct
Print
Sign
Print
NO.
A
Ma Hot Part. not Opm
NA
SURVEY mierCurj SONGS RADIOLOGICAL
OPM 100om' or <MOOR
DPN9100cm* or mrihril (Wm' OW-OW
Max net cpm NO.
UNIT SURVEY REASON Post-Deoon 0 Pre-Job SURVEY NO. ot /c,2 0,- 00
AREA C> 0 Routine ShIpment/Heoelpt Mo NO. 2o Zo I Coo
ELEV 0 Job Coverage 0 Sottreetleak Teal REP NO. 2b0 10 I
ROOM Pwr Entry % other "rCC tAbiSte CA4 EQUIP. ID. S I — Res
DATEI2ji Jo' i TlIvIE
NO. P"' 7 a
DPW100cml DFM or toocm2 mor/i0Oomi or OW-GW darn
5
7
25
Boundary
0 Trend Pt
0 General Area
CI Individual
rt Component
SURVEY CLASS
SURVEY DESCRIPTION: Trans Nuclear West greater than
Class C waste can survey.
Dose Rates In RThr.
Dose Rate Survey Only
OP "Deck RYsr&-'6 's RA
Model Pe2 xH
Serial No 326j3sy
Cal. Due Oz. Waste Can Under Water Weight 2.7 140 lbs. Load Cell Number
L 7' 1" Waste Can Serial number
00
70-0
Highest Contact 376C)
0 Degree 6"
Stand Off
100

54"
75%
2 qoo
50%
18"
25%
Highest 6" Stand Off
Dose Rate
180 Degree 6"
Stand Off
8 /000
9 60t)
36"
too
3 StO
90 Degree 6"
I Stand Off
MOO
Dose Rate
270 Degree 6"
Stand Off
10
L1 7D
10
11
1 2
10
11
12
13
14
16
CDAtr4r4416Air ARA ,eA N WIT G'rec aRGATER rblAAI CLYOS I C
Instruments used
TECHNICIAN
ttÀ A.6YeT .5.G .c e11/4
Sign "4.1)4 A '04 /4e0fL;4-
APPR
print
reco 1 Page of
NO. it" 7 a Masslinn
A
REMARKS: Alignment arrows are used to mark the
0. Degree survey side.
Hot Port.
MN)
Page /i of /5
(for this survey) '
Reference Number S0123-VII-20.9
Form Number
SCE HP (1) 259-17 08/01i00
NO. 13" T a a Masslin
NO. Hot Port. Max
not opm
A
8
11
Coo 12
Page of
SURVEY CLASS JD Boundary
0 Trend Pt.

General Area gi Component
0 Individual
Trans Nuclear West greater than
REMARKS: Alignment arrows are used to mark the
0 Degree survey side.
Dose Rates In R/hr
Dose Rate Survey Only •
OP DeCK ?051-€1> Ept
cpAlroroJnierir )1,TED 412, t, CA , AlkIPPre
ark - (;eefireR 7-4,4 _a1.0154 e. ••
instruments used •
Print
Page it- of /5
(for this survey) WiDA•tdreris. c. 1
TECHNICIAN
Model x
Serial No. 3;;5134
§ign 4.0-4144.414:#
APP BY"
Referenbe NUmber
80123-V1i-20.9
Print
Sign
API:royal
Luta.. oSt.C,
Date:V*( Time12.;
Form Number
SCE HP (1) 25947 REV.2 08/01/00
DATE
NO. 13-1
Waste Can Under Water Weight 2 '8 šI lbs. Load Cell NumberfOrAinkilii Cal. Due
270 Degree 6"
Sta nd. Off
(:9C) 1.0
54"
18"
25%
Highest 6" Stand Off 1100O
• Dose Rate .
Highest Contact (40 060
Dose Rate
0 Degree 6"
Stand Off
1 CICO
75%
2 ‘2o0
50%
3 800
36"
7' 1" Waste Can Serial number oi
90 Degree 6"
Stand Off
3so
270
180 Degree 6"
Stand Off
7 &X)
8 gOO
9 )300
SONGS RADIOLOGICAL SURVEY 2"-C-417
SURVEY REASON Post-Decon Ej Pre-Job SURVEY NO,
0 Routine Shipment/Recelpt MO NO. 4020 21.5 t 060
0 Job Coverage 0 Source/Leak Testi
Pwr Entry % [] Other &TCC liJi3 04 REP NO. 200 51 - Re..s C- EQUIP. ID.
OPM
100om, or <MOOR
OPM/100cm*
or mr/hr/100orn,
OW-CW
16 1
2 17
3 18
4
5
8
19
20
21
7
9
22
23
24
10 25
11
12
13
14
15
SURVEY DESCRIPTION:
Ciais C waste can survey.
TIME 12eX).
DPW100crn1 OPM
Or 10Dcm2 mr/hr/100cm, or OW-CW <MDCR
OPM 100crne or <MDCR
DPM/10000 or for/1000cm* OW-CIN
DPW100cm* or mairI1000or 01N-CW
oigferil Cal Due Waste Can Under Water Weight 22-14 lbs. Load Cell Numbs
ATE...W.110 1 TIME /
NO. re' a NO. Fr?
AREA
ELEV
ROOM
0 I
LW
21
22
23
24
SURVEY CLASS
8oundary
0 Trend Pt.
General Area \gg Component
IndlvIdual
SURVEY DESCRIPTION: Trans Nuclear west greater than
Class C waste can surVey.
REMARKS: Alignment arrows are used to mark the
0 Degree survey slde.
Dose_Rates J.n I3thr.
Dose Rate Survey Only
oP e.ck 704;76: Cmirliari7 frtjtEto st 4a CA MirPte Gra = 60+10 TiM4 c Instruments used
Model
Serial No.
TECHNICIAN
Print r) 4. ‘4er1.f.t4ifi'As
Sign • A .144 Med,
API*
F3rin Form Number
SCE HP (1) 259-17 REv.2 OW01/00 • AppriNal Data: 144 Time: 12406
16
17
18
A
7
8
9
10
11
12
13 .
26
NA
14
15
ug C>s-,
UNIT ¡ SURVEY REASON tJ Poet-Deco Pro-Job gp10/-001?
adr SONGS RADIOLOGICAL SURVEY Amerce"
SURVEY NO.
tJ Job Coverage
Pm Entry_%
tJ ShIpment/Recelpt
0 Souroe/Leak Test Et other c;ra.. vosie Ch4
Routine • MO NO.
REPNO.
EQUIP.10.
AOZezol ct zoolot c.;1 -RcS -c-
Page of
a • Masslinn.
tiot Pro.
12M. 100crna or <MDCR
Msx NO. net cpm
3
4
5
6
fj
32spo
Page of 5
((or thls sutvey) •
Referende Number 90123-Vl)-20.9
0 Degree 6"
Stand Off
3oo
75%
Highest 6" Stand Off
Dose Rate
54"
38"
18"
7' 1" Waste Can Serial number
90 Degree 6"
I Stand Off
500
1456
Highest Contact )760
Dose Rate
270 Degree 6"
Stand Off
I 'go
Z5(3
.230
-10
1 1
12
180 Degree 8"
Stand Off
7
8 OD
SONGS
Waste Can Under Water Weight 22 12. lbs. Load Cell Number&
RADIOLOGICAL. SURVEY .."-Zwisr DATEE Liolt TIME /200 1 Page of
UNIT SURVEY REASON 0 Post-Decon 0 Pre-Job SURVEY NO.
AREA 0 Routine ShIpmentfReceipt MO NO.
ELEV 0 Job Coverage Sourceil..eak Test REP NO. ROOM Pwr Entry % XI other alai. 14/4ire eA4 EQUIP. ID.
7' 1" Waste Can Serial number
90 Degree 6"
Stand Off
800
-700
700
Highest Contact 3(060
Dose Rate
270 Degree 6"
Stand Off
aDIO
51 - Eze. -C- let.) i.rb
Page /LI of IS "
(for this survey) P;e
Pign ijk.kk.I /4,4-14411-44RefErrenbe ',lumber
TECHNICIAN
Approval Date: Time: -vocw
NO a NO. fr 'Y a Masslinn
15
SURVEY
CLASS CI Boundary
0 Trend Pt.
0 General Area
Component
ndMdual
DPWISOomt or nu/11000W OW-ON
Max net opm
Hot Pad.
SURVEY DESCRIPTION: Trans Nudear West greater than
Class C waste can survey.
REMARKS: Alignment arrows are used to mark the
0 Degree survey side.
Model H
APPRO 50123-VII-20.9
Print
sign
Forrn Number
SCE HP (1) 259-17
REV.2 08/01/00
Dose Rates In R/hr.
Dose Rate Survey Only oP Dect PosreD t RA
141AD4MEn11" asng% 1 04 I. A itIPpre
arct Ckeytrg' 7,144 cuiss Inshuments used
Serial No. 326 1 UP
Print
180 Degree 6"
Stand Off
7 960
8 1 tY.i0
0 Degree 6"
Stand Off
1 , "760
75%
2 700
50%
3 SOO
25%
Highest 6" Stand Off 1000
Dose Rate
54"
36"
18"
r.201-00 azozol eco
0
11
1 2
REP NO. eicf Max
net cm NO.
aste Can Under Water Weight Z360 lbs. Load Cell Numbeggoillkiin Cat. Due 3/t81.1- W
DATEID I TIME Zoo
General Area 00. Component
IndMdual
0 Boundary
Trend Pt.
SURVEY CLASS
Highest 6" Stand Off 2 ?-0 C.)
0 Degree 6"
Stand Off
NO. 13- 'I a
DPW100croo or ntritwit0Ocrif °WON
NO. Fr
DliAllOWm? or rarawrt0Ocros OIN.GW
OPM 100crne or <1ADOR
18
19
20
21
22
23
24
25
18
2
3
7
a
8
10
11
12
18
14
16
17
Model
Serial No. 31513N
TECHNIcIAN
:DAIAD 11.46/
Sig
5
n •.) kt.k
PPRMI‹
-
Page )5 ef 15
(for this survey)
Reforl31160 Number
S0123M1-20.9
Print
Forrn Number
SCE HP (1) 259-17
REV.2 08/01/00 afime: oir)
Print
Sign
Approval Date: (
SONGS
UNIT t SURVEY REASON . 0 Routine
0 JOb GOWNS
0 Pwr Erltry %
7' 1" Waste Can Serial number
RADIOLOGICAL
Post-Decon Pre-Job
0 Shipment/Receipt
0 Sourcaaalt Test
RI other Gra:. cfid
L
90 Degree 6"
/ Stand Off
2006
2200
2 2.00
Highest Contact 7oo0
Dose Rate •
270 Degree 6"
Stand Off
SURVEY .1wej
SURVEY NO. I /,90/-0 07 oZozo oco MONO.
EQUIP. ID. 51 - RCS - C. I
suRvEy DEsalIpTION: Trans Nuclear West greater than
' Class C waste can survey.
REMARKS: AlIgnment arrows are used.to mark the 0 Degree survey side.
Dose Rates in R/hr. •
Dose Rate Survey Only
CD? 1:)EtK ?b,5TE32,', 'RA
CpAl-rAzrfriE .1-bcrEti'• ARANitiDP.re Grc.c CI-Asc;
Instranents useci
Dose Rate ,
Page of
a Masslinn
A
OPM
1 ct 0001P
.:MOGR
Hot Port. efiN)
180 begree 6"
Stand Off
7 LIO