ML20154A819
| ML20154A819 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/06/1988 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-49 NUDOCS 8805160179 | |
| Download: ML20154A819 (24) | |
Text
- Docket 72-4 Project M-49 f.!AY 0 61988 4
MEMORANDUM FOR: Leland C. Rouse, Chief Fuel Cycle Safety Branch ,
Division of Industrial and Medical Nuclear Safety, NHSS
(
FROM: John P. Roberts, Section Leader Irradiated Fuel Section !
Fuel Cycle Safety Dranch ,
SUBJECT:
MEETINGWITHDUKEPOWERCOMPANY(DPC)
] DATE/ TIME: May 4, 1988; 9:00 a.m. (
l) LOCATION: Room 6.B-11, White Flint Building, Rockville, MD ATTENDEES: See enclosure 1 PURPOSE: To discuss DPC's license application under 10 CFR Part 72 for !
dry spent fuel storage at its Oconee Nuclear Station site. '
DISCUSSION: i After introductions Duke proceeded with its presentation (see enclosure 2) !
- which followed its agenda (see enclosure 2). Tcchnical discussion folicwed.
DPC then spoke of its need to meet short term and long term schedules (see enclosure 2) to be able to reachieve a prudent operating reserve in its reactor i 4
pools. NRC staff expects to provide initial coments to NUTECH on its a NUH0MS.24P modular design by the end of May 1988 (DPC references the NUTECH designinitsapplicationforOconee). Initial coments on DPC's env!ronmental report will follow by the end of June. A site visit to Oconee in late June or ,
early July by NRC staff in conjunction with the environmental review was also discussed. The environmental review is the pacing segment of the licensing i review, since DPC desires to commence site work in October 1988 and construction d
in April 1989. l
- Reactor technical specification changes associated with removal of fuel to dry j storage will be separately handled through an amendment application filed with ;
the Office of Nuclear Reactor Regulation. i i
pri.ginal- signed By- i 8805160179 880506 ADOCK 05000269 1
yPDR PDR John P. Roberts, Section Leader l
- Irradiated Fuel Section i i Fuel Cycle Safety Branch 4
Enclosures:
i j 1)AttendanceList ,
i 0) DPC Presentation 7 j
~
er Docket No; 72-4L: Project'f M 9 M TLPORD IMNS Central File brb bnbe Kbu
- OFC : I !
1 ......... .................................................................
j NAME: J berts:lg ;
DATE: 5/f/88 OFFICIAL RECORD COPY .
j
5 4
l i l d
NRC/DPC MEETING ATTENDANCE LIST MAY 4, 1988 !
. t 4 :
) John P. Roberts NRC/NMSS 1
f Renee M. Perfetti NRC/NRR/ DEST i l Helen N. Pastis NRC/NRR/DPR ,
- Paul Guill Duke Power j James Thornton Duke Power l M. A. Haghi Duke Power Jim Schneider NRC/NMSS l K C. Leu NRC/hMSS Ralph Stevers SAIC, McLean, VA j a
'ohn R. Stokley SAIC, McLean, VA '
i Ata Istar SAIC, McLean, VA l 1
, Fritz Sturz NRC/NMSS !
! Jack D. Rollins NUTECH (Atlanta) l l Bob Lehnert NUTECH (San Jose)
- l Bill McConaghy NUTECH(SanJose) i
] Deborah Ryan SAIC(SanDiego) f Richard Belanger SAIC(SanDiego) }
l Terry L. Bradley Duke Power i
! Dave Rehn Duke Power !
! i j l i
F l
d J
i l
l I
r
~
OCONEE NUCLEAR STATION ISFSI LICENSINC "KICKOFF" MEETING NRC HFAD00ARTERS - ROCKVILLE. 50 MAY 4 1988 Introduction Duke Oconee ISPSI Facility Overview Duke Su==ary of Principal Design Criteria Duke Su==ary of Principal Technical Specifications Duke Early NRC Technical Concerns / Questions NRC Schedule Requirenents Duke
- Short Ters Items (1988)
- Long Tern Items (1989)
Logistics / Schedule of NRC Review Process NRC
- Part 72 Review Plan
- Part 50 Review Plan
- Part 50 and Part 72 Prenoticing Schedule / Strategy ,
Discussion All l
I l
j i
1
OCONEE SPENT FUEL STORAGE CURRENT OPERATING RESERVE STATUS 1
^
INVENTORY STATUS AVAILABLE STATUS OCONEE 1/2 POOL 939 359 +14 +72 l
i OCONEE 3 POOL 490 328 -17 +41 1
POR = 345 STORAGE SPACES RPOR = 287 STORAGE SPACES i
I i I
OCONEE UNIT 1/2 SPENT FUEL POOL PROJECTED OPERATING RESERVE STATUS DATE POR STATUS SPACE AVAILABLE RPOR STATUS i
01/89 - 38 307 + 20 <
1 07/89 - 90 255 - 32 06/90 -142 203 - 84 12/90 -194 151 -136 11/91 -233 99 -175 i 1400 . . -
1338. .
POOL CAPACITY __
1 3 0 1213 . - - -
i F ~
1150 . LOSS OF FCR .
g .,____ __... __ . - _ _ _ ...._.,___ ____
i S 1988 . - - - . .
S Y 1925 - T - - . . . -
S -
LOSS OF POR l 963 <. - - - - - . - . . .
I 900 . . , , -
l 1; I 1988 1988 1988 1989 1989 1989 1999 1999 1990 1991 1991 1991 MAR JUL N0Y MAR JUL N0Y MAR JUL NOU MAR JUL N0Y !
DATE (YEAR / MONTH) l i
a l
i
- j OCONEE UNIT 3 SPENT FUEL POOL l
PROJECTED OPERATING RESERVE STATUS 1
DATE POR STATUS SPACE AVAILABLE RPOR STATUS l
08/88 - 77 268 - 19 12/89 -129 216 - 71 05/91 -181 164 i23 POOL CAPACIIV 820 __..___________________..__________-
174 - - - -
- 128 - - - - -
0 681 - - - - - - -
F LOSS OF FCR 635 A __
S 589 - -
S ~
V 543 . - - - . -
S 496 LOSS OF POR - - -
450 , , i . , , , . . . i 1988 1988 1988 1989 1989 1989 1990 1990 1990 1991 1991 1991 MAR JUL N00 tLAR JUL NOU MAR JUL NOU MAR JUL N00 DATE (YEAR / MONTH)
DUKE POWER COMPANY OCONEE NUHOMS ISFSI i
ISFSI FACIL.ITY OVERVIEW o LOCATION OF FACILITY AT OCONEE o FACILITY DIMENSIONS AND CAPACITY o BASIC FACILITY FEATURES o FACILITY INTERFACE WITH ONS STATION
LDiD . ' -l
'W f I( r y l
?
/AAf INf y' "f m &&n TT L n i- - -
/I @
]
d U# i il 111111 ili 1111ll161111I )
UNIT 2 q
l h l E 7_ nnnlinn
"%pl'"""'"""/r
,l, Q- -
l 3 - f ll11lll1111llll11 i t illilllillll ',' ~
gD
- C J
=x (Illif f f f fillf fit!fillfllfillllf f ff f f' fil'.l/ /O \
l t
EP ll 'A l
} , m {jilliiiiililllitiiiiiiiinu inin uitj ,
lj v
,,I -0 (* UNIT a. e'3
/ niittiinittlitullf riflinitifillfittil /qg 9. .
I f 8 ,
111611161111111111161611111111lllill[f=il
--e o l l-- I!!'sma5&A':Ki '!!!!!!!lllhb ,
h%
' 0 SMS TRAlLER g "7, % hA 3 f
- D D'r" L J OWASTE m
(
F.AD#STE FACILITY
- m R$ILER [
~
Y/ ?hy!N r
- I l
p _ N CONST !
'~^
- =
L \ OFFtrE' '
~) ASSE' (IBLpG '___ '
- /
1 y g
._.iA'N)1d e .
i I l t i I If I I I i
/
I i s,1
'r ly 1. li
' flI l__ -
, r , ,
[ ( J l l I I I I l b //
f p l -
INTAXF 97Rtfri
-/
( n n _
"/- -
n n -r - -
~
h h _- H -
}
\-- Q 55 S 1 INTAKE CANAL
\ n =: r r, Z E: 0z -
~ _ .
2 7 Z c qa - -
55 m m H xg H) w, 71 Wl w
l' r'Y H
w l
s .
T7 I ITs i j l 1 i
\
N ISFSI LAYOUT OCONEE NUCLEAR STATION
'O Figure 2.1-3
DUKE POWER COMPANY OCONEE NUHOMS ISFSI ISFSI STATION INTERFACE o PROPOSED SECURITY SYSTEM o EMERGENCY PLAN ARRANGEMENTS o
ELECTRICAL REQUIREMENTS / SUPPLY o PROCEDURES AND TRAINING o FACILITY DECOMMISSIONING PLAN o ENVIROMENTAL IMPACT o PROPOSED TRANSPORT ROUTE APPLICATIONS MADE TO 10CFR50 BRANCH COVERING CASK HANDLING WITHIN THE OCONEE FACILITY
l
)
I DUKE POWER COMPANY OCONEE NUHOMS ISFSI i
PRINCIPAL DESIGN CRITERIA I 1
ISFSI SITE:
o SEISMIC LOADS o TORNADO WIND LOADINGS o TORNADO GENERATED MISSILE o FLOOD EFFECTS o SNOW AND ICE LOADINGS o FIRE AND EXPLOSION EFFECTS
1 DUKE POWER COMPANY OCONEE NUHOMS ISFSI PRINCIPAL DESIGN CRITERIA SITE TRANSFER ROUTE:
STRUCTURAL ACCEPTANCE o TARGET HARDNESS WITHIN REPORT DROP ACCIDENT CONSTRAINTS I l
l
_,_g.,,., -_ . - -. ., , .__, .,,_, ..__s ,_.-
M
- fV l 1 s
'y h o
VA ng,Syg l
e,, _"
,,% Son gegoll,'e~So,, %uu~ urn 4"% 4 l ex - ..
c a, 4 f stoc* eteAmlu 4 L -
O r 's
- gO Q OSEO INGg mumm i
D.
O
, a 's'*,'
's,,,,f i
le Slog \inintuii m 1 O ( " j'g' 8 o 87 1
/,,__ g ;
A O. G ?W(Eg avg f,' &
L W
'~_ _ . .h _.r-'
, i
$ EV Acg ,
,h I
', l e
"i & 4y A
y //
R. 8. u qb.
ff-
,i 7 N Oe4 Ife
~
{ l '
fr f l G > rs*jen gns }[g h' 5 ($
a - :
E W 'a KDrptth 8\ '
o
/
! l 0 l'i L E
'96 i $35 -d nx k
..n...n.un on.nl jg e
a a
mir$ 5 m
ON ,'
I h.
@ z Z bi a % ,
i
_ ,l/ . : . . . -
g " :-
g [
ninninnntf f
- . -- + 7 ,l i- l g%. . n . . n "
j g .0$!!Nuis ia' 7 '
I'
, $_ l 3 3 0rnnnitnntnenntittttttfittittff[tth.
M :--
'I ll n. s. :.:$ 0 E, (suo...nuauuann.ninniniipp ,,Z
, g Wgt 3 g :--
a inonnnontuntnenntninnone '/yg -
-o a --
in. . ..n.u niiiii. 6.n.4 6. uin u.fy il x ,
C )
'I E !!!< 'ntt!'tfitt re 3-
- l ni -- - uni.no,,l41tlpuj '- -
i .
- / SCAFFOLO "
+
l E* I SMs TRAILER % f g 80 STOR 'i U l fpfM)
L J SI6 i ! ((
La
- Mo#1TE t
a FAG M IT '
~7991LER [ ]l .
f 0 A. IN -,,)
OFFICE'1 ASSE>eLY 8 LOG '
l l g i illl i i i I I1 7g 4 t y' 'n i ' t? ' If . 'P ! 'J 'U
% 4e7 4
(' li l} ll Il 6 ' i I#n.
r-57 - "a- mm' l#
9 5 5 5 -
Y uH y
9 h o 3 N
==
g 3 1 o
-' N,
,p q _ INTAKE CANAL i Ei 52 J -
- A $ 55E5 d 2 N L.
O
-g E- r,r M
b3 @ ~ '
4-: -
w I 8U n wi i' l
lk Si l WW iii a <- g ri r,i "h
~
i-aQo
- :D xi 1
+. bM k M.
..e EA N 7 O
2 l
l l
DUKE POWER COMPANY OCONEE NUHOMS ISFSI 1
PRINCIPAL DESIGN CRITERIA FUEL ASSEMBLY SELECTION :
o B&W 15X15 MARK B OR SIMILAR PWR DESIGN o
ANY POSSIBLE CONTROL COMPONENT PRESENT o
NO KNOWN GROSS CLAD DAMAGE
DUKE POWER COMPANY OCONEE NUHOMS ISFSI PRINCIPAL DESIGN CRITERIA CRITICALITY:
o MAINTAIN K-EFF LESS THAN .95 o BURNUP CREDIT o MODERATOR DENSITY OPTIMIZED BETWEEN 0 & 1 GRAM /CC o AXIAL BURNUP PROFILE :
- WORSECASECORRESPONDS ROUGHLY TO 63% IN TOP 18 IN. ;
- MEITIODDEPENDENT
- NEGLIGIBLE EFFECTS POSSIBLE WITH Q11ER MODELS o MISLOADED ASSEMBLY ACCIDENT CREDITTAKEN FOR SOLUBLE BORON VARIOUS SCENARIOS POSSIBLE o STORAGE CELL SPACING - VARIABLE STORAGE CELL MATERIAL l
o INITIAL ENRICHMENT / DISCHARGE BURNUP LIMITS - FIGURE 1
~
FIGURE 1 FUEL ASSEMBLY ACCEPTANCE CRITERIA CRITICALITY 40-35-.
30-n S
2 25-
! D acceptable 3
l 320- unacceptable
! o.
f $15-l 5 10-
{
5-l l
0 i i , , , , , , , , , , ,
1.60 2.00 2.40 2.80 3.20 3.60 4.00 IE (w/o U235) l i
i
DUKE POWER COMPANY OCONEE NUHOMS ISFSI PRINCIPAL DESIGN CRITERIA THERMAL:
o FUEL ASSEMBLY DECAY HEAT LOAD -
.66 KW/ ASSEMBLY o MAXIMUM FUEL CLAD TEMPERATURE 570 DEG. C. TRANSFER MODE 340 DEG. C. STORAGE MODE o
ASSEMBLY HEAT LOAD METHODOLOGY ORIGEN-S (SCALE 3) 27 GROUP NDF4 CROSS SECTION REGULATORY GUIDE 3.54 o FUEL ASSEMBLY MINIMUM COOLING TIME - 7.5 YEARS o
FUEL ASSEMBLY ENRICHMENT /BURNUP LIMITS - FIGURE 2
FIGURE 2 .
FUEL ASSEMBLY ACCEPTANCE CRITERIA .
J DECAY HtAT 40-
- 35- decay heat curves ____ -
30-n 3
225- --- 10 yr wrve .
D acceptable _
3: 20-o v
l-- 7.5 yr curve o.
a E 15-a cn 10-l 5-l 0 i i i i i i i g -- g . -
i i ,
l i
1.60 2.00 2.40 2.80 3.20 3.60 4.00 l
l- IE (w/o U235) l I
i
DUKE POWER COMPANY OCONEE NUHOMS ISFSI l PRINCIPA DESIGN CRITERIA .
l l
RADIOLOGICAL : l 0 SOURCE TERM METHODOLOGY-ORIGEN S l 0 TRANSFER CASK SURFACE DOSE RATE LESS THAN 200 MR/HR o HSM SURFACE DOSE RATE 20 MR/HR o SITE BOUNDARY DOSE - LESS THAN 0.01 MR/YR o DOSE TO WORKERS DURING CONSTRUCTION - 2.5 MR/HR AVG.
DUKE POWER COMPANY OCONEE NUHOMS ISFSI TECHNICAL SPECIFICATION l l
SUMMARY
i I
l DSC VACUUh1 DRYING PRESSURE 5-10 TORR l HELIUht BACKFILL PRESSURE 2.5 PSI - +2.5 PSI DSC WELD TEST / INSPECTION LIQUID PENETRANT l PER ASME STANDARD )
l FUEL ASSEh1BLY RETRIVAL/ -
FOLLOWING DROP OF l INSPECTION 60 INCHES OR MORE l
l DSC SURFACE CONTAMINATION 2200 DPM BETA / GAMMA PER 100 Chh 220 DPM ALPHA PER 100 Chh HSM INLET / OUTLET SURVIELLANCE INSPECTION INLETS EVERY 24 HOURS INSPECT INLETS / OUTLETS AFTER HIGH WIND TRANSFER ROUTE SELECTION CONSTANT ELEVATION TO 5 FT. BOTH SIDES FUEL SELhCTION CRITERIA PWR FUEL PER FIGURE 3 RESTRICTIONS
FIGURE 3
. FUEL ASSEMBLY ACCEPTANCE CRITERIA 40- __
1 - --
i 35- decoy heat ~_ ________ ___
- curves __
! 30-r n 3
2 25-x --- 10 yr curve o acceptable 3 -- 7.5 yr curve 020-
- o. unacceptable
- a burnup curve j E 15-a m
10-5-
1 l
0- i i i i i i i i i i i i i l 3.60 4.00 i 1.60 2.00 2.40 2.80 3.20
- IE (w/o U235) 4 1
)
DUKE POWER COMPANY OCONEE NUHOMS ISFSI NEAR - TERM SCHEDULE o FILE VENDOR TOPICAL 2-26-88 o FILE SITE APPLICATION 3-31-88 1
BEGIN FACILITY EARTHWORK 10-1-88 o
o RELEASE EQUIPTMENT 10-1-88 FABRICATION CONTRACTS o NRC APPROVAL NEEDED 4-1-89 o BEGIN DESIGN CONCRETE 4-1-89 POURS t
.-- -m .,-3,_..,-_- .._, , ,. -- _ -,, ,. ..,_.. .,_.~. . ,_ , ,.._,_.--_.-.,-.,,.,m
i DUKE POWER COMPANY l OCONEE NUHOMS ISFSI \
LONG TERM SCHEDULE o PRE-OPERATIONAL 10-1-89 TESTING BEGINS o FACILITY COMPLETE, 1-1-90 FIRST DSC's DELIVERED o LOAD FIRST 11 DSC's 1990 o LOAD 5 DSC's 1991 j o LOAD 5 DSC's 1992 '
o LOAD 4 DSC's 1993 o LOAD 4 DSC's 1994 o LOAD 5 DSC's 1995
OCONEE UNIT 1/2 SPENT FUEL POOL PROJECTED OPERATING RESERVE STATUS WITH DRY STORAGE DATE SPACE AVAILABLE POR STATUS DSCs LOADED 01/89 307 -38 _
07/89 255 -90 _
01/90-06/90 423 +78 7 06/90 371 +26 _
12/90 319 -26 _
06/91-10/91 390 +46 3 11/91 339 -6 _
01/91-04/92 387 +42 2 1400 -
1338 -
POOL CAPACITY - -
--~~- --~~-~~------- ~~~~~~-~~~~
16 1275 - !
0 1213 - -
T 1150 g ., _ _ _ _ _ _ _ . . .,__... _ _ LOSS OF FCR S 1988 - - - - -
S -
Y 1025 - -
S LOSS OF POR -
963 .. _ _______ _ _ _ _ _ _ _ _ _ _ _ . ... ._-_____! 3 1., t L_.
J 900 . . , , , , - ; , , , ,
1988 1988 1988 1989 1989 1989 1990 1990 1990 1991 1991 1991 MAR JUL NOU MAR JUL N0Y MAR JUL N0Y MAR JUL NOV DATE (VF.AR/ MONTH)
l 1
OCONEE UNIT 3 SPENT FUEL POOL i
PROJECTED OPERATING RESERVE STATUS l
WITH DRY STORAGE l
DATE SPACE AVAILABLE POR STATUS DSCs LOADED 1
l OW88 268 -77 _
12/89 216 -129 _
1 08/90-11/90 312 -33 4 01/91-04/91 360 +15 2 05/91 308 -37 _
820 ._ _ POOL CAPf.CITV- _ _ _ _ _:_ _ _ ___ _._ ,,_,._ _ _ _ _ _ _ _ _ _
774 .
l
- 728 . - . . . . .
1 0 681 . . . .
F LOSS OF FCR 635 .---- - - - - - - - - - - - - - - - - -
A -
S 589 .
S Y 543 . . .
3 496 . .
LOSS OF POR - . .
1988 1988 1988 1989 1989 1989 1990 1990 1990 1991 1991 1991 MAR JUL NOV MAR JUL N00 MAR JUL N00 MAR JUL Nog DATE (YEAR / MONTH) l 1
- - . - - - - ., - - . . _ , . _ . . . - . . - . - - - - - - - - . . _ , . - - ... ..-. -