ML20128L055
| ML20128L055 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/19/1985 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8507240288 | |
| Download: ML20128L055 (16) | |
Text
o .
July 19,1985 Docket No. 50-409 LICENSEE: Dairyland Power Cooperative FACILITY: La Crosse Boiling Water Reactor (LACBWR)
SUBJECT:
MEETING TO DISCUSS PROPERTY DAMAGE INSURANCE On June 27, 1985 the NPC staff met with representatives of Dairyland Power Cooperative to discuss the licensee's requested exemption to reduce the insurance coverage from the currently required coverage of $500 million. A list of attendees is provided as Enclosure 1.
Dairyland presented the results of a study performed to estimate the cost of clean-up from a TMI-type accident (100% clad failure; 50% fuel melt).
Copies of viewgraphs presented are included in Enclosure 2. The licensee stated that LACBWR would not be returned to service in the event of a severe accident, hence costs were estimated for clean-up to the point at which normal decommissioning of the plant could begin. The study results indicate the clean-up costs at LACBWR would be approximately $179 million.
The NRC staff had no disagreement with the licensee's presentation and felt that the stuoy was consistent with the clean-up costs estimated in NUREG-CR-2601, which forms the basis for newly proposed levels of insurance coverage. However, an Accident Evaluation Branch representative stated an opinion that licensees requesting exenptions from insurance requirements should be required to analyze accidents r: ore severe than the licensing design basis and more severe than those in NUREG-CR-2601. Participants agreed that this issue should be referred to NRC management for prompt resolution. ,
Otispnal W W Richard Dudley, Pro,iect Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
As stated cc w/ enclosure:
See next page DISTRIBUTION Docket File NRC PDR Local PDR ORB #5 Reading JZwolinski 0 850719 -
h 7) g 050004o9 EJordan J PGrimes PDR ACRS(10)
NRC Participants DL:0RB# D'.:0RB#5 DL:0RBf5 CJamerson RDudley:tm JZwolinski 07/4/85 07/w/85 07/0/85 sEoI ax-3r 4l
eEen UNITED STATES
[
o,i NUCLEAR REGULATORY COMMISSION c p WASHINGTON, D. C. 20555
% ,,,,.* July 19,1985 Docket No. 50-409 LICENSEE: Dairyland Power Cooperative FACILITY: La Crosse Boiling Water Reactor (LACBWR)
StIBJECT: PEETING TO DISCUSS PROPERTY DAMAGE INSURANCE On June 27, 1985 the NRC staff met with representatives of Dairyland Power Cooperative tn discuss the licensee's requested exemption to reduce the insurance coverage from the currently required coverage of $500 million. A list of attendees is provided as Enclosure 1.
_ Dairyland presented the results of a study performed to estimate the cost of clean-up from a TMI-type accident (100% clad failure; 50% fuel melt).
Copies of viewgraphs presented are included in Enclosure 2. The licensee stated that LACBWR would not be returned to service in the event of a severe accident, hence costs were estimated for clean-up to the point at which normal decommissioning of the plant could begin. The study results indicate the clean-up costs at LACBWR would be approximately $179 million.
The NRC staff had no disagreement with the licensee's presentaticn and felt that the study was consistent with the clean-up costs estimated in NUREG-CR-2601, which forms the basis for newly proposed levels of insurance coverage. However, an Accident Evaluation Branch representative stated an opinion that licensees requesting exemptions from insurance requirements should be required to analyze accidents more severe than the licensing design basis and more severe than those in NUREG-CR-2601. Participants agreed that this issue should be referred to NRC management for prompt resolution.
k Pichard Dudley, Proiect Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
As stated cc w/ enclosure:
See next Dage
cc:
Fritz Schubert, Esquire Clarence Riederer, Chief Engineer Staff Attorney Wisconsin Public Service Dairyland Power Cooperative Commission 2615 East Avenue South Post Office Box 7854 La Crosse, Wisconsin 54601 Madison, Wisconsin 53707
- 0. S. Heistand, Jr., Esquire Mr. Frank Linder Morgan, Lewis & Bockius General Manager 1800 M Street, N.W. Dairyland Power Cooperative Washington, D.C. 20036 2615 East Avenue South La Crosse, Wisconsin 54601 Mr. John Parkyn, Plant Manager La Crosse Poiling Water Reactor Dairyland Power Cooperative P. O. Box 275 -
Genoa, Wisconsin 54632 U.S. Nuclear Regulatory Commission
- Resident Inspectors Office Rural Route #1, Box 276 '
Genoa, Wisconsin 54632 Town Chairman Town of Genoa Route 1 Genoa, Wisconsin 54632 Chairman, Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Visconsin 53702 Regional Administrator, Region III U.S. Nuclear Pequlatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
e ENCLOSt'PF 1 JUNE 27, 1985 ATTENDANCE REPRESENTATIVE ORGANIZATION R. Dudley NRC - ORB #5 W. Paulson NRC - ORB #5 R. Wood NRC - OSP
_- E. B. Tremmel Dairyland-Washington L. Soffer NRC/DSI/AEB L. G. Hulman NPC/DSI/AEB H. F. Devine Dairyland R. E. Shimshak Dairyland Power J. R. (Jack) May Nuclear Energy Sves.
W. J. (Bill) Manion Nuclear.Energv Svcs.
i
.e .
. . j ENCLOSURE 2 POSTACCIDENT REC 0VERY COSTS FOR THE LA CROSSE BOILING WATER REACTOR DAIRYLAND POWER COOPERATIVE JUNE 27, 1985 1
JUNE 27, 1985 PRESENTATION AGENDA 1; PbRPOSE OF MEETING
- 2. DESCRIPTION OF LACBWR -
~-
- 3. DESCRIPTION OF THE ACCIDENT
- 4. DESCRIPTION OF RECOVERY
- 5. REVIEW OF RECOVERY COST ESTIMATE 6
DESCRIPTION OF LACBWR 9
. GENERAL PLANT INFORMATION
. . POWER RATING 50 MWE (NET)
.. DESIGN PRESSURE. 1,400 PSIG
.. O ERATING P PRESSURE 1,300 PSIA
.. POWER PRODUCTION 165 MWT
.. N0MBER OF FbEL ASSEMBLIES 72
..URANIbMCONTENT 18,963 LBS 41.4 KW/ LITER
.. AVERAGE POWER DENSITY
.. ACTIVE CORE HEIGHT 83 IN
. CONTAINMENT
.. INTERNAL HEIGHT 144 FT
.. INSIDE DIAMETER 60 FT
.. STEEL SHELL IHICKNESS 1.61 IN
.. STEEL DOME THICKNESS 0.60 IN
.. CONCRETE WEIGHT 14,150,000 LBS
.. CONCRETE ANNULUS THICKNESS 9-24 IN
, REACTOR VESSEL
.. MATERIAL A302B C.S. W/304L CLADDING
.. INSIDE DIAMETER 8.25 FT
.. SHELL THICKNESS 4 IN
.. INTERNAL HEIGHT 37 FT
.. WEIGHT 26.5 TONS i
42,000 GAL. WATER STORAGE TANK TOP OF CRANE EL. 729'-6" I
j/1 1
/f '
/ /
/ /
/ /
/ /
/ /
MAIN FLOOR / SHIEi.D PLUG /
EL. 701'-0" / / /
5 l
/ '/
/ #'9)'t'
=
= I
// ;m / ,/
/
/
/
E B
a /
// REACTOR /
/
INTERMEDIATE
/
/ !
/. i
/
7 FLOOR EL. 667'-0"
/ ..
/ =
=' .
j> f, . . . /
/ E Nh$ /
/ _
j /
/ 5 /
/ 5 /
GRADE FLOOR / 5 EL. 642'-9"
/5...
/
g, @
...p 6000 GAL. / , /
RETENTION / , /
TANK gg , /
& , /
// f//
// y$a o CONTAINMENT BulLDING ELEVATION 10 FIG. 10.4
I M
t o su s
=
',71 h _ .
! I liWW t
,a mummunesh8P * 'I t - --
anansa.
- 6. m ,h u =-
i m
J
'> ~
l
' k..
N
,...x.y .,. .<,,. ,_-
_ w. . .
x
- 9, 6
\, r. ,.f. b
. ,1_, 7 ~ n.2
.'kl' C W , 'h -_ _m, y .
4
\ s ,
li: I,wl , /, #g Q.-e.'\ .\ ' f ]1
\ t "" " "~ 1 g); hl .3,.- / i tr
_ a . .- 'p '
t I f\/ w l A \..n : . 't.1! . i .
7 l rtin ,g $
- s$. "-fi)4\.llA,p~~~.
- /
_a MJ- N - : i
-- 1 .. < - - ~ y w ----*9 1
N Fr ) ,' xS---.>m ---l,-" "
'N ,7 m- .'
,N : s'
_we - .
'.. lj <
9> \/. - .
i.
s s
'M"#
!g
'th.$.i h_.j
. ~ . . -
m'y i r
- -e
( __
l ,
'on
( ~1
\
l l ptAu At Et.Ev. Tof o* 1 i
i 1
l 1
R
. NA 1 OE 0 I
T G 1 AH l T TC, I
G CI XW / I F
ES ll E C
i C 0 N-Eu E ER A I
RO E
V RI T R '
FO EC S g TA L E ~
NR E X i 2 O G ' lI O-
. R E
/
1i' / V H C-
/
s 1 R
0 C a
0 T
, ' 1 ET 4 I '
/ SS 2 W i NU S s
s
- l" s
/
EA DH NX B I
lJ ^
i / OE T R -
l C.
L s
/ C& OE A n'
i s i
/ V G S
/ 0 H '
, 0 C '
/ 4 G
N DI 1
1
/
d l
/
7 f /
1
- , , 0,0 T WE
'K N 0
0t B I
l U
2 T l
I W
S m'
l
' f B
E L
I U 6 e,
S d N
I s
8 '
R U '
T -
1' ' [
r p
')
' /
4N 0" 8'
7 6
',,/j ////CNT
- 6 L
E G T ,
. N I
A NM G D LAO D L
PL R PO L
I B U R E
/ N ATO RCR I
B R
E EA T U
M NEN T N E RO F L
I A G&C O
/
Q O L T E R LW N O E
UE O O C L FG F TA N NR EO ; I PT A SS M
! )' i l! 1fi lj1!!! Jj.
i -
I FORCED CIRCul.ATION TURSINE SulLDING PUW FULL FLOW
- FORCED ..nmq H.P. HEATER NO. 3 DIMINERAllZERS fv1 r '
CIRCULATION i 1, ,1, ,
,d6b, ,K, / / / / 9',
! Puw 3 q , ,
3 , f u :
! L
'mfO, AA ! OOOOR 5
' < q 7 ///// ,
C , , . . , , .
j OaaO l '
& /
{ '
'y' - CONDENSER ', g CONDENSATE 1.,, ; ', Fours
- g ,k -
7 CONTAINAENT BUILDING .
h l " ' ' ' ' ' A h C V /
- O
(
/ 1 1 ,1 1 _ a,
} !
j EVAPoltATOR O -
EVAPORATOR SPENT ,
FEED TANK llHlUU LABORATORY RESIN TANK j
-WATER
~
A ^~~~~~~ '
-z' O-- "
e b e e ' -
OCK l
f ; y COLLECTING g yootgoog
/ - e . TANK E & STORAGE- l
F:5:'9 % DECONTAM- _
a f
s ?d INATION AltEA ! \
k
!! E a = ,
x, s
.__.-[ ' COUNTING j
j
@ 'ar#)" l .
SHOWER &
WASH AREA k4 '# ROOM WASTE TREATMENT BUILDING b
GRADE FLOOR OF TURBitt BLDG, EL. M0' + .
FIG .10.3
0.60-in. steel and no concrete
. 1.16 in. steel and 9 in. ordinary building , ,,,,,, 1 24 In. concrete ceilirg i J ummmmw tu, bin.
building 24 in, concrete control well room I(
ei. 668 rt. /
- \
6-in.c/ oncrete I floors
\ l 9 in concrete !
w all % {
- E grade el. 639 CONTROL ROOM SHIEi. DING FI G.10.7 4
, . - . - - - - _ ., ,,_-,,_.___-_,,..__..,________.._m. . . _ _ _ , -____.-_,__-_..,__-,-...___,_.._,-_..-__,,,.m.r_.m.-..m.,__-.-
~ '
}\\Q.t65 DESCRIPTION OF 'THE ACCIDENT
. CORE HISTORY AT ACCIDENT
.. AVERAGE CORE EXPOSURE - 17,000 MWD /MT
.. OPERATING POWER LEVEL - 100 PERCENT
~
. EVENT
.. LARGE BELOW-CORE UNISOLABLE BREAK
.. HIGH PRESSURE CORE SPRAY AND A0XILIARY CORE SPRAY ACT0 ATE
.. CONTAINMENT FLOODED TO CORE MID-PLANE 3.9
.. CORE CONDITION p)0"f,L& N ,,bcE h,ps .. REFERENCE CASE - 100 PERCENT CLAD FAILURE, NO F0EL MELTING g . . . WORST CASE. - 100 PERCENT CLAD FAILURE, 50 PERCENT M edd F0ELMELTING
.. EXPOSURE RATE ON OPERATING FLOOR LEVEL TWO YEARS AFTER ACCIDENT gg
... REFERENCE CASE - 64 MREM /HR b) #'
... WORST CASE - 280 MREM /HR
/
. IMPACT OF BELOW-CORE BREAK
.. MAXIMIZES RECOVER'I COST
.. WORST CASE CONTI.INMENT ENTRY, REACTOR DEFUELING, AND DECONTAMINATION
.. CREATES LARGEST WATER CLEANUP BORDEN - ADDED PROCESSING Eo0!PMENT COSTS, ENERGY COSTS, AND HIGH SOLID WASTE SHIPPINGANDBORIALCOSTS
4 SIGNIFICANT RELEASED RADI0 ACTIVE INVENTORY -
AFTER TWO YEARS
.100% CLADDING FAILURE; 100% CLADDING FAILUREJ
~
RADIONUCLIDE NO-FUEL MELT - CI 50%' FUEL MELT - CI KR-85 1.2 x 10 3 1.92 x 10 4 SR-90 3.7 x 10-1 1.86 x 104 l Cs-134 4.5 x 10 4 3.94 x 10 5 Cs-137 2.3 x 104 1.97 x 10 5 j TOTAL 6.9 X 104 64.4 x 104 i
3
)
DESCRIPTION OF~ REC 0VERY d
. PREPARATION J/r
.. RECOVERY ENGINEERING
. .. TEMPORARY OFFICES / CRAFT FACILITIES
.. MOCK-UP INSTALLATION
.. LAYDOWN FACILITY CONSTRUCTION
.. WASTE STORAGE FACILITY CONSTRUCTION
.. CONTAINMENT WATER PROCESSING FACILITY INSTALLATION
.. AUGMENTED LAUNDRY FACILITY INSTALLATION
.. CONTAINMENT VENT INSTALLATION
.. CONTAINMENT ACCESS STRUCTURE CONSTRUCTION
.. CONTAINMENT AIR LOCK CONSTRUCTION
.. PROCESSING OF CONTAINMENT WATER
- .. VENTING OF CONTAINMENT
.. FLOOD CONTAINMENT TO OPERATING FLOOR + }# *
, CONTAINMENT ENTRY AND DECONTAMINATION t
.. INITIAL ENTRY
.. INSTALL CLOSED-CIRCUIT TVS AND RAD MONITORING EQUIPMENT
.. DECONTAMINATE ABOVE 701 FOOT LEVEL
.. REFURBISH CRANE SM 8cc f 5'"4
.. INSTALL CONTAMINATION CONTROL ENVELOPE , }# "j," ,
.. REMOVE REACTOR VESSEL HEAD
.. SEGMENT AND STORE CORE SPRAY BUNDLE
.. EXAMINE CORE
.. INSTALL DAMAGED FUEL STORAGE RACK
.. PERFORM MOCK-UP TRAINING
- .. REMOVE DAMAGED FUEL AND STORE
.. SEGMENT AND STORE VESSEL INTERNALS
{
.. INSTALL RECIRCULATION N0ZZLE PLUGS
.. COMMENCE CONTAINMENT WATER DRAINING / EXPOSED AREA l
DECONTAMINATION
.. DECONTAMINATE RECIRC PUMP CUBICLES VIA HATCHES
.. COMPLETE CONTAINMENT WALL / SURFACE DECONTAMINATION
,,m.-gmw--.--.,--m,-., ,w-,.m,---.e,--,_m n-p ,--.y e.,
- - e,-a,rwmn'~nw- ,,e,,,--
4 DESCRIPTION OF RECOVERY (CONTINUED)
. FUEL AND CORE RUBBLE DISPOSAL
.. REFURBISH MAIN AIR LOCK
.. COMMENCE CASK LOADING AND SHIPPING OF DAMAGED FUEL
, COMMENCE CONVENTIONAL DISMANTLEMENT ee
. ~
REVIEW OF RECOVERY CnST ESTIMATE .
. ESTIMATING METHOD
.. Building Block Approach
.. Sequential Definition / Scheduling of Activities
.. Activity Dependent Costs
.. Period Dependent Costs
.. Significant References
)
... NUREG/CR-2601
... Three Mile Island Unit 2 Program Reports
{ ... Department of Energy Decommissioning Handbook
... Atomic Industrial Forum Decommissioning Study 1
. SUle(ARY OF POSTACCIDENT RECOVERY COSTS
- Reference 50% Fuel Category case, 1984 $ Melt, 1984 $ comment Plant Structures, Systems, 115,155,000 142,438,000 Cost increase factors:
and Structures Recovery plan / implementation $ 4.3 MM Fuel equipment 12.5 HM Waste disposal 6.0 MM Mock-ups 2.5 MM Supplies 1.9 MM .
Disposal of Damaged Fuel 17,716,000 17,716,000 Reference case based on Scenario 3 of NUREG-2601.
Impact on Facility 19,171,000 19,171,000 Decommissioning Total Recovery Cost 152,042,000 179,325,000 A = $27,283,000-
- 25 percent contingency included. .