ML20202J078
| ML20202J078 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/31/1998 |
| From: | Nelson L DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20202J042 | List: |
| References | |
| LAC-TR-138, LAC-TR-138-01, LAC-TR-138-1, NUDOCS 9802230077 | |
| Download: ML20202J078 (14) | |
Text
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LAC-TR-138 LACl3WR INITI A1, SITE filARACTERIZATION SURVFN FOR SAFSTOR i
By:
Larry Nelson IIcalth and Safety Supenisor October 1995 Resised: Jaqunty 1998 i-Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI S4601
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9802230077 990210 c.
'.. . LAC-TR-118 PAGE2 2.0 QMilMIINGEVENTS WillCil COULD AFFFCT t PLANT CLliANUP (1) Failedhel During refueling operations following the first few fuel cycles, several fuel elements were observed to have failed fuel rods. These fuel failures were severe enoagh to have allowed fission products to escape into the Fuel Element Storage Well and reactor coolant. These fission product particles then entered, or had the potential to enter and lodge in or plate out in, the following syste.ns:
- 1) Forced Circulation
- 2) Purification
- 3) Decay lleat
- 5) Fuel Element Storage Well
- 6) Overhead Storage Tank
- 7) Emergency Core Spray
- 8) Condensate system between main condenser and condensate demineralizer resin beds
- 0) Reactor Vessel
- 10) Seal Injection
- 11) Waste Water
- 12) Reactor Coolant Post-Accident Sampling System
- 13) Control Rod Drive System (2) Engl Element Storage Well Leakags The stainless steel liner in the Fuel Element Storage Well (FESW) has had a history of leakage. From the date ofinitial service until 1980, the leakage increased from approximately 2 gallons per hour (gph) to just over 14 gph In 1980, epoxy was injected behind the liner and leakage was reduced to approximately 2 gph. Since then, the leakage trae has slightly increased.
This leakage traveled through flaws in the structural concrete of the containment building and through the biological shield. This leakage may require the removal of additional concrete frc'.. LACllWR to accomplish the final site release.
(3) Release of Contu linated Water To The Controlled Area. July 2.1982 at 0610 The failure to close the resin inlet valve in the resin addition line to the number one full flow demineralizer following the addition of resins subsequently caused the release of water to the Turbine Building Floor through the gasket on a bulls-eye sight glass in th t line. Approximately 75 gallons of contaminated water could not be accounted for in the waste water storage tanks. Approximately 20 gallons of this water is estimated to have entered the ground in the radiological controlled area outside the west turbine hall door and the turbine hall tmck bay door. Contaminated ground was remosed over a 3 sq. f1 area by the west turbine hall door and 2 sq. yard area by the truck bay door. It was placed in waste storage banels and later sent to burial at Barnwell, S C. l i
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9 o ' LAC-TR-138 PAGE7 SPsaLEupl_ Radioactivity Inygntoly
. January 1988 l ItalfLife Activity llalf Life Activity Radionuclide Radionuclide (Years)
(Years) (Curies) _ (Curies)
Cc-144 7.801 E-l 2.636 E+6 St-90 2.770 E+1 1.147 E+6 Cs-137 3.014 E+1 1.666 E4 6 Pu 241 1.440 E+1 1.138 E46 Ru-10d 1.008 E+0 1.524 E46 Fe-55 2.700 E40 5.254 E+5 Zr(Nb).93 1.754E 1(9.58E 2) 3.555 E+5 Zr-95 1.750 E-l 3.52 E+2 Cs-134 2.070 E+0 3.291 E+5 Ni-59 8.000 E+4 2.87 E+2 Kr-85 1.072 E+1 1.160 E+5 Tc-99 2.120 E+5 2.76 E+2 Ag-110m 6.990 E-1 1.018 E+3 Sb-125 2.760 E+0 2.73 E+2 Sr-89 1.335 E-1 1.000 E+5 Eu-155 4.960 E+0 1.68 Ev2 Te-127m 2.990 E-1 8.238 E+4 U-234 2.440 E+5 6.37 E+1 Co-60 5.270 E40 6.395 E+4 Am-243 7.380 E+3 6.31 E+1 Ru-103 1.075 E-1 6.334 E+4 Cd-ll3m 1.359 E+1 1.78 E+1 Pm-147 2.620 E+0 4.129 E+4 Nb-94 2.000 E+4 1.59 E+1 Ni-63 1.000 E+2 3.540 E+4 Cs-135 3.000 E46 1.40 E+1 Cc.1 <" 8.890 E-2 2.638 E+4 U-238 4.470 E+9 1.22 E+1 Cm-242 4.454 E-l 1858 E+4 Eu-156 4.160 E-2 8.63 l Am 241 4.329 E+2 1.474 E+4 Pu-242 3.760 E+5 8.58 l Pu 233 8.774 E+1 1.252 E+4 U-236 2.340 E+7 6.32 Pu-239 2.410 E+4 8.837 E+3 Sn-121m 7.600 E+1 4.44 Pu-240 6.550 E+3 7.165 E+3 Np-237 2.140 E+6 2.19 Eu-l54 8.750 E+0 4.020 E+3 U-235 7.040 E+8 1.89 Cm 244 1.812 E+1 3.603 E+3 Sm 151 9.316 E+1 1.51 Cr-51 7.590 E-2 3.002 E+3 Sn-126 1.000 E+5 7.01 E 1 Te-129m 9.340 E-2 1.170 E4 3 Se-79 6.500 E+4 5.52 E-1 11 3 1.226 E+1 5.510 E+2 1-129 1.570 E+7 3.90 E-1 Fe-59 1.220 E-1 5.120 E+2 Zr-93 1.500 E+6 1.11 E-1 Eu-152 1.360 E+1 5.110 E+2 1-131 2.200 E-2 2.00 E-3 Am-242m 1.505 E+2 4.900 E+2 Total Activity = 1.00 E7 curies NOTB Attachment 1 is an inventory of the Spent Fuel Radioactivity decay corrected. l
LAC-TR-138 PAGE8 4.2 Cate_[ntemals/RX Components Radionoclide inventorv Reactor components in and near the reactor core during power operation become radioactive due to nuclear interaction with the large neutron Hux present in this region. Most of the residual radioactivity is produced by n,y reactions with the atomic nuclei of the target material although n,P reactions, for example the l production of C-14 from N-14, are also sigrJficant The residual radioactivity in the materials of the various LACBWR reactor components has been estimated using activation analysis theory and, where available, actual data from laboratory analyses ofirradiated metal samples Best esti mates of neutron fluxes in and irradiation histories of specific components were used in these calculations. Original material chemical compositions were obtained from actual mater:al certification records when readily svaliable but standard compositions for specified materials were used in some cases. Radioactive decay of the activation product nuclides has been taken into account to obtain the best estimate values for the residual radioactivity as of January 1,1988.
As of January 1,1988, the largest contribution (210,000 Ci) to the radioactivity inventory in LACBWR activated metal components is the isotope Fe-55 (llL = 2.7y). Tlic r=xt largest contributor (101,000 Ci) is Co-60 (lit = 5.27y).
The activity of these two relatively short-lived isotopes will decrease very significantly during the proposed SAFSTOR period. The major long lived contributor to the radioactivity inventory (10,700 Ci) is Ni-63 (Ill =100y). The activity of other activation product nuclides have been lumped together in two categories, those with halflives less than 5 years and those with halflives greater than 5 years. The group with IIL <5y consists mostly of Zr-95 (64d)in Zircaloy components and Cr-51 (27.7d) and Fe-59 (44.6d)in stainless steel components along with small quantities of Sn-113 (115d), Sn-119 (293d), Sn-123 (129d),
lif-175 (70d),1If-181 (42.4d), W-181 (121d) and W-185 (75.1d). The group with IIL > Sy consists mostly of Ni-59 (8x10'y) with small quantities of C-14 (5730y),
Zr-93 (1.5x10'y), Sn-121 (50y), Cd l13 (14.6y), Nb-94 (2x10'y) and Tc-99 (2.13x10'y).
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LAC-TR-138 ,-
' PAGE 9 fore Internal /RX Component Radionuclide Inventerv - January 1.1988 .
Estimated Curie Content Other Nuclides Components Fe-55 Ni-63 Tn> Sy Total Co-60 Tn < Sy In Reactor 22,100 63,221 1,352 2,810 15 S9,507 Fuel Shrouds (72 Zr,8 SS) 4,886 4,826 817 24 15 10.568 Control Rods (29) 1,270 594 63 2,396 4' 4,327 Core Vertica Posts (52)
Core Lateral Support 21,477 770 105 8 31,468 Structure 9,108 78,851 2,826 386 30 115,532 Steam Separators (16) 33,439 1,443 3,402 123 17 1 4,968 Thermal Shield 1,029 10 2 -0 1,388 Pressure Vessel 347 15,230 546 75 6 22,315 Core Support Structure 6,458 408 15 2 ~0 598 Horizonta! Grid Bars (7) 173 Incore Monitor Guide Tubes 307 188 611 7 _1 1.118 189,226 7,133 5,824 84 281,807 Total 79,540 in FESW 14,988 2,384 -0 26 31,065 Fuel Shrouds (24 SS) 13,667 1,007 95 27 3 2,050 Fuel Shrouds (73 Zr) 918 2,386 910 ~0 17 6,769 Control Rods (10) 3,456 l 156 5 3 5.626
! Start-up Sources (2) 3.177 2.285 20,666 3,545 32 49 45,510 Tmal 21,218 NOTE: Attachment 2 is an inventory of the Core Internals /RX Component Radioactivity decay corrected. l L.___
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- 1,AC-TR-138 PAGE 10 4.3 }$arlt19nsc391faccl(adiRm!Glii910EntDE A plant smear survey was performed of all accessible interior building surfaces in an attempt to detennine the amount ofloose surface contamination in the plant.
The specific isotopic identification of the contamination was also determined.
Each smear was gamma scanned to determine not only a correlation factor in pCi per DPM/100 cm' but also the percentile of each radioisotope present in the mixture. From previous, part 61, snalysis of plant smears, it has ban determined that Fe 55 is the major beta cmitter in the plant and is in approximately the same percentage as Co-60. Fe-55 will be the only beta emitting isotope listed as a contaminant. Alpha activity on the surfaces has been checked by the use of an internal Proportional Counter and has been found to be negligible and so will not be considered. The survey did indicate that the major isotopes present in the plant's loose surface contamination are the following isotopes:
ImLong JI2Lif&
Co-60 5.27 years Us 137 30.1 ycars Mn-54 312.2 days Fe-55 2.7 years it must be realized when reviewing the results of this survey that a 100% smearing of plant surfaces was nat performed and therefore the following data is subject to ,
significant error. 9 The majority of the loose surface contamination throughout the plant is found in the plant contaminated areas. The plant areas that were classified as contaminated areas at plant shutdown in 1987 are listed below.
a) Waste Treatment Building (1) decon n a (2) basem.cnt (3) resin liner room (4) high level storage pit b) Turbine Building (1) stop valve area (2) full flow room (3) condensate bay (4) area under main condenser (5) feed pump bed plates (6) tunnel-includes 4500 WT cubicle and crawlway to stack c) Containmer.t Building (1) 701 south by FESW (2) mezz around core spray pumps (3) west N1 platform (4) purification platform (5) FESW IX cuoicle (6) purification pump area (7) basement -inchades UCRD platform, purification IX cubicle, retention tank cubicle. tubbasement, and FCP cubicles. l
LAC-TR-13S '
PAGEli -
PLANT LOOSE SURFACE CONTAMIN ATION - JANUARY 1988 .
Isotopes Present,in pCi Total Area pCi Co-60 Cs-137 Mn-54 Ce-144 Co-57 Cs-134 Fe-55. Content Location t
Turbine Building ffB) 0.83 0.07 - - - - 0.83 L73 a) Main Floor 0.14 0.04 - 0.49 1.16 b) Mezzanine -including stop valve area 0.49 - -
0.06 0.02 0.42 0.92 0.42 c) Grade Floor -includes feedwater heater area 0.81 0.18 0.06 - - - 0.8I 1.86 d) Tunnel I Containment Buildina (CB) 0.2 0.39 - - 3.16 6.91
- 1) Abovegrade 3.16 -
7.40 2.36 0.04 0.04 0.08 31.44 72.80 b) Below grade 31.44 0.66 - 7.57 16.28 Waste Treatment Building 7.57 0.48 - -
8.53 3.53 0.04 0.04 0.08 44.72 101.66 Tctals 44.72
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NOTE: Attachment 3 is an inventory of LACBWR's Loose Surface Contamination Inventory decay corrected.
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LAC-TR-138 -
PAGE IS , -
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PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - JANUARY 1988 -(cont'd)
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Nuclide Activity,in pCi Eystem Total Ci Content Plant System Alpha Co-60 Mn-54 Cs-137 Ce-144 Zn-65 Other Fe-55 Fuel Element Storage 1.4 E4 1.0 E4 - 1.7 E6 Well System 8.5 ES 3.9 E2 8.5 E5 -
Fuel Element Storage 6.0 E2 4.6 E3 4.5 E2 83 E3 Well - all but floor 13 E3 4.9 13 E3 -
Fuel Element Storage 5.0 ES 4.1 E4 1.1 E5 Cs-134 = 13 E2 53 E7 Well floor 2.6 E7 7.6 E3 2.6 E7 -
Co-58 = 13 E2 4.2 E4 4.0 E2 2.2 E3 Fe 59 = 1.'7 E3 3.I E5 Resin Lines 13 E5 1.0 E2 13 E5 -
Co-57 = 4.8 El Co-58 = 2.1 E3 Nb-95 = 3.5 E2 Ru-103 = I.6 E2 3.4 E4 1.9 E5 Fe-59 = 1.4 E5 2.6 E7 Main Condenser 1.1 E7 8.5 E3 1.1 E7 3.6 E6 -
Co-57 = 4.1 E3 Co-58 = I.7 E5 hb95 = 3.0 E4' Ru-103 = 1.4 E4 I
NOTE: See attachment 4 is an inventory of the plant system - Internal Radionuclide Imrntory decay corrected.
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LAC-TR-138 i PAGE 24 I ATTACilMENT 1
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SPENT FUFI, RADIOACTIVITY INVJINTORY i
Decay Corrected to January 1998 IIalfLife Activity ItalfLife Radionuclide (Years) (Curles) Radionuclide (Years) (Curies)
Cc-144 7.801 E-1 365 Sr 90 2.770 E + 1 8.93 E5
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Cs-137 3.014 E+1 1.32 E6 Pu-241 1.440 E+1 7.03 tis Ru-106 1.008 E40 1.58 E3 Fe-55 2.700 E+0 4.03 E4 j Cs-134 2.070 E4 0 1.16 E4 Ni 59 8.000 E+4 287 Kr-85 1.072 E+1 6.08 E4 Tc-99 2.120 E+5 276 Ag-110m 6.990 E-1 5 Sb-125 2.760 E+0 22 Co-60 5.270 E+0 1.72 E4 Eu-155 4.960 E40 42 Pm 147 2.620 E40 2.93 E3 U-234 2.440 E+5 64 Ni 63 1.000 E+2 3.30 E4 Am 243 7.380 E+3 63 l Am 241 4.329 E+2 1.45 E4 Cd-l13 . 1.359 E+1 11 Pu-238 8.774 E+1 1.17 E4 Nb-94 2.000 E+4 16
]
Pu-239 2.410 E+4 8.84 E3 Cs-135 3.000 E+6 14 Pu-240 6.550 E+3 7.16 E3 U-238 4.470 E+9 12 l
Eu 154 8.750 E+0 1.82 E3 Pu-242 3.760 E+5 8.58
- Cm 244 1.812 E+1 2.46 E3 U-236 2.340 E+7 6.3:
11-3 1.226 E+1 313 Sn-121m 7.600 E+1 4 j
Eu-152 1.360 E+1 307 Np-237 2.140 E+6 2.19 l Am-242m 1.505 E+2 468 U 235 7.040 E+8 1.89 Sm-151 9 ';16 E+1 1.4 Sn-126 1.000 E+5 7.01 E - 1 Se-79 6.500 E+4 5.52 E - 1 1129 1.570 E+7 3.90 E - 1 Zr-93 1.500 E+6 1.11 E - 1 Total Activity = 3.13 E6 Curies
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2 -
LAC-TR-138 E PAGE 25 ;*
ATTACHMENT 2 CORE INTERNAI /RX COMPONENT RADIONUCLIDE INVENTORY - JANUARY 1998 Estimated Curie Cortent _.
Other Nuclides Components Fe-55 Ni-63 Total Co-60 Tn > Sy In Reactor 4,855 1,261 8 12,060 Fuel Shrouds (72 Zr,8 SS) 5,936 1 371 762 8 2,453 Control Rods (29) 1,312 46 59 2 448 Core Vertical Posts (52) 341 1,649 718 4 4,816 Core Lateral Suppoi' Structure 2,445 6,055 2,637 15 17,685 Steam Separators (16) S,978 261 115 0.5 764 Thermal Shield 387 79 9 - 181 Pressure Vessel 93 1,170 509 3 3,416 Core Support Structure 1,734 31 14 - 91 IIorizontal Grid Bars (7) 46 14 570 _;i 669 Incore Monitor Guide Tubes 82 14,531 6,655 43.5 42,585 Total 21,355 In FESW 1,151 2,224 13 7,057 Fuel Shrouds (24 SS) 3,669 246 77 80 2 514 Fuel Shrouds (73 Zr) 183 849 9 1,969 Contro? Rods (10,1 928 853 175 146 _2 Ll76 Start-up Sources (2) 3,308 26 10,618 Total 5,697 1.587 l
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LAC-TR-138 ,-
PAGE 26 ,
ATTACIBIENT 3, PLANT LOOSE SURFACE CONTAMINATION - JANUARY 1998 Total Area Isotopes Present, in pCi pCi Location Fe-55 Content Co-60 Cs-137 Turbine Bui! ding (TB) 0.22 0.06 0.06 0.34 a) Main Floor b) Mezzanine-including stop valve area 0.13 0.11 0.04 0.2C c) Grade Flocr-includes feedwater heater area 0.11 0.05 0.03 0.19 0.22 0.14 0.06 0.42 d) Tunnel Containment Buildina (CB) a) Above grade 0.85 0.16 0.24 1.25 b) Belowgrade 8.44 5.88 2.41 6.73 Waste Treatment Building 2.03 0.38 0.58 2.99 Totals 12.01 6.78 3.43 22.22
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LAC-TR-138 ,
PAGE 27 .
ATTACHMENT 4 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - JANUARY 1998 Nuclide Activity,in pCi System Total Others Ci Content l Plant System pe_55 Alpha Co-00 Cs-137 Mn-54 I
430 135 638 CB Ventilation 123 -
OtTgas -
upstream of filters SINTEM Raf0ED Ofruas -
do$nstream of filters SINTBf RDIOED 4,564 3,973 0.24 9,882 TB drains 1,305 4.0 El 2,918 3.2 10,202 1,907 0.79 15.031 CB drains 967 95 1,345 TB Waste Water 276 6.8 -
56,380 1,828 5.15 74,418 CB Waste Water 16,126 7.9 El 69,804 6.06 90,066 Main Steam 19,966 2.9 E2 -
250 159 - 482 Turbine 71 1.8 23,894 2.67 30,743 Primary Purification 6,834 1.2 El -
Emergeng Core Spray Sl'STSI RElf0ED 3,490 620 0.29 5,142 Overiiead Storage Tank 998 3.4 El 430 44 601 Seal Inject 123 3.8 -
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5 LAC-TR-133 -
PAGE28 .
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- ATTACENENT 4 PLANT SYSTEMS INTERNA.L RADIOSTCLIDE INVENTORY - JANUARY 1998 Nuclide Activity,in Ci System Total Other Ci Content Plant System Fe-55 Mpha Co-60 Mn-54 4.9 E2 26,348 9 39 Zn 65 = 0.11 35027 Decay Heat 7.679 Baron Iniect SYSTF1i RFA101ED 4.6 El 2,658 0.88 3,465 Reactor Coolant PASS 760 9.4 El 5,370 1.79 7,002 Alternate Core Spray 1,536 61,750 20.90 Zn 65 = 0.24 80,533 Shutdown Condenser 17,662 1.1 E3 40,272 13.93 Zn 65 = 0.16 52,525 Control Rod Drive Efiluent i1,519 7.2 E2 402,715 133 Co 57 = 0.20 525,037 Forced Circulation 115,187 7.0 E3 -
Zn 65 = t.56 671,192 230 Co 57 = 0.33 875,403 Reactor Vessel and Internals 191,978 1.2 E4 Zn 65 = 2.68 56,380 9.69 Zn 65 = 0.10 72,796 Condensate after beds & Feedwater 16,126 2.8 E2 10,471 3.94 13,50I Condensate to beds 2,995 3.1 El I
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r LAC-TR-13S ,
5 PAGE 29 . ~y ATTACHMENT 4 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - JANUARY 1998 Nuclide Activity,in pCi l System Total Other pCi Content Plant System Fe-55 Alpha Co-60 Mn-54 Cs-137 Fuel Element Storage 65,272 3.9 E2 228.205 4.24 - 293,S71 Well System Fuel Element Storage Well 4.9 349 0.18 3,655 4,109
- all but floor 100 Fuel Element Storage Well Cs-134 = 4.57 1,996,568 7.6 E3 6,980,399 151 32,578 Zn-65 = 3.43 9,017,304 floor 9,983 1.0 E2 34,902 12.72 - 44,99S Resin lines Zn-65 = 5.93 844,7C2 8.5 E3 2,953,246 1,091 -
Co-57 = 0.35 3,807,545 Main Condenscr _
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