ML17325B439

Summary of 910605 Meeting W/Util Re Proposed Reracking of Spent Fuel Pool.List of Meeting Attendees & Viewgraphs Encl

ML17325B439
Person / Time
Site:	Cook
Issue date:	07/24/1991
From:	Pegg W Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-80615, NUDOCS 9107310233
Download: ML17325B439 (77)

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Docket Nos.

50-315 and 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 July 24, 1991 LICENSEE:

Indiana Michigan Power Company FACILITIES:

Donald C. Cook, Units 1 and 2

SUMMARY

OF MEETING WITH D.

C.

COOK REGARDING THE PROPOSED RERACKING OF THE SPENT FUEL POOL (TAC NOS.

80615 and 80616)

The staff.met with the licensee for the Donald C.

Cook facility (Indiana Michigan Power Company) and representatives from Holtec on June 5, 1991.

The purpose of the meeting was to discuss the licensee's proposed reracking of the spent fuel pool.

The licensee requested this meeting to determine if the staff had any concerns over the reracking which should be addressed in the licensee's formal submittal and request for license amendment.

Enclosure 1 is the list of attendees.

Enclosure 2 is a copy of the licensee's slide presentation.

BACKGROUND The licensee cited several factors for their decision to rerack the D.

C.

Cook spent fuel pool.

These include:

1.

Loss of the capability by 1994 to fully off-load the core into the spent fuel pool; 2.

Projections that this rerack will provide adequate storage capacity until the year 2009.

With consolidation, this rerack is projec'ted to last until a permanent repository is built in 2010, the latest estimate by the Department of Energy (DOE); and 3.

Consideration of dry cask or vault storage and consolidation as alternatives.

As a result of the above, the licensee will submit their license amendment request for this rerack in the near future.

DISCUSSION The licensee's presentations reviewed four major areas:

(a) the reracked spent fuel pool layout and thermal hydraulics, (b) criticality safety analysis of the spent fuel storage

racks, 9i073i0233 910724 PDR ADOCK 050003~5 p

PDR

(c) rack and pool structural/seismic considerations, and (d)

ALARA aspects.

The main concern expressed by the staff involved the nonlinearity and lack of experimental verification supporting the computer code developed by Holtec to analyze the effect of seismic phenomena on the spent fuel pool racks.

The staff had not been sent any information on the experimental tests conducted by Holtec to verify the accuracy of the computer code.

The licensee will supply this information to the staff.

The submittal will include analysis of a 3-D earthquake and a time-history response spectra discussion.

The licensee has also committed to check the calculated spent fuel pool temperatures against the ion exchanger maximum operating temperature to ensure that the spent fuel temperature limits of Standard Review Plan (SRP) 9.1.3 are not exceeded.

Further discussions with the licensee will be scheduled after the licensee's amendment submittal has been examined by the staff.

Enclosures:

As stated Original signed by:

Timothy E. Collins for

>!. D. Pegg, Technical Intern Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation DISTRIBUTION:

NRC 5 Local PDRs F. Miraglia J. Partlow B. Boger J. Zwolinski PD III-1 r/f L. Marsh T. Colburn OGC E. Jordan NRC Participants ACRS (10)

R. Lobel, Region III NAME

PShuttleworth DATE:07/

/91 g

WPegg 7

TCo1bura

~Warsh

07/(r1/91~

07/79 /910

07/27/91 OFF CIAL RECORD COPY Document Name:.

RERACKE

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NAME T.

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Colburn Pegg Richings Kim Klementowicz Bagchi Kim Wagner Lewis Turner Wi 1 1 i ams Malin Ferguson Brewer Soler Singh LIST OF ATTENDEES ORGANIZATION NRC/NRR/PD31 NRC/NRR/PD31 NRC/NRR/SRXB NRE/NRR/ESGB NRC/NRR/PRPB NRC/NRR/ESGB NRC/NRR/ESGB NRC/NRR/SPLB AEPSC HOLTEC AEPSC AEPSC INDIANA MICH POWER AEPSC/NSSL HOLTEC HOLTEC ENCLOSURE 1

TELEPHONE NUMBER (301) 492-1341 (301) 492-1391 (301) 492-0888 (301) 492-0729 301) 492-1082 301) 492-0733 (301) 492-0729 (301) 492-0808 614) 223-2052 (813) 787-4625 (614) 223-2040 (614) 223-2050 (616) 465-5901 X1513 614) 223-2020 (609) 424-0999 609 424-0999

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JUNE 5, ~9S<

NRC/AEPSC/HOLTEC INTERNATIONALMEETlNQ

SUBJECT:

DONALD C. COOK NUCLEAR PLANT SPENT FUEL POOL RERACKING TOPIC Introduction Reracked Pool Layout/

Thermal Hycfraulics Criticality Rack and Pool Structural/

Seismic Considerations ALARA Aspects Conclusion

= SPEAKER DH. Malin/

E.G. Lewis K.P. Singh SZ. Turner A.L Soler DR. Williams SJ.

Brewer COMPANY AEPSC Holtec Holtec Holtec AEPSG AEPSG

Spent Nuclear Fuel Storage JUNE 6, 199$

ERIC 8. LEWIS

SPENT FUEL STORAGE MODULE lpxlp lpxlp lpxlp lpxlp I

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CASK AREA D.

C.

COOK UNITS No.

1 and 2

SPENT FUEL POOL ARRANGEMENT

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COOK NUCLEAR PLANT SPENT FUEL STORAGE PROJECTION THROUGH 2017 6000 4500 4000 S500 SOOO 2600 2000

$ 600

$ 000 600 0

MAX CAPACITY WITH FCD 9

0 5

YEAR A88UME8 DOE DOE8 HOT PERFORM

YEAR REPOSITORY START DATE 1985 1987 1989 1998 2003 2010

~ DRY CASK gR VAULT

~ ONSOLiOAT)OW

~ RERACK

RERACKING OBJECTIVES

~ MAXIMIZESTORAGE LOCATIONS

~ MINIMIZEOVERALL STORAGE COST

~ DESIGN FOR CONSOLIDATION

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COOK NUCLEAR PLANT SPENT FUEL STORAGE PROJECTION THROUGH 2017 5000 4500 4000 8600 SOOO 2500 2000

$ 600 1000 600 0

RBRACKED MAX CAPACITY MAX CAPACITY WITH FCD 9

9 5

YEAR ASSUMES DOE DOEb HOT PEBFOAM

SPENT FUEL POOL RERACK PROJECT SCHEDULE

~ AWARD CONTRACT

~ GATHER DATA

~ START ANALYSIS

~ SUBMIT LICENSING REPORT

~ RECEIVE LICENSE

~ START FABRICATION RECEIVE RACKS ~

COMPLETE INSTALLATION~

-1990 1991 1992 1993 1994

LICENSING RECORD VOGTLE UNIT 2 MILLSTONE UIGT 1 INDIA%POINT UNIT 2 J.A. FITZPATRICK KUOSHENG 1 8c 2 TM UNIT 1 ULCHIN Ut'GT 2 ST. LUCIE UNH' BYRON 1 8'c 2 BRPJDWOOD 1 4 2 PILGMMUI'GT 1 GR.A]%3 GULF I V.C. SUMMER OYSTER CREEK IVDCHO SECO QUAD CITIES I 2 2 ENRICO FEB2% I 1989 1989 1989-90'.

1990 1989-90 1990 1989 1988 1988 1988 1986 1985 1984 1984 1983 1982 1981 POOL STRU WAS AjXO REQU D

CONCUIVXNTWITH RACK QUAIZFICATION.

GOVERj.'GNG DOCUMENTS 1.

OT POSITION PAPER.....

2.

RUING-0800 3.

REGUIWTORY GUIDES 4.

NF-ASME CODE 5.

FUEL SUPPLIER'S SPECIFICATION

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TYPICAL CELL WALLS H

BASEPLATE BASEPLATE BEARING PAD Figure 6.2.1 Pictorial View of Rack Structure 6-51

Table 2

1 2

COMMON MODULE DATA Storage cell ins'de dimension:

Storage cell height (above the baseplate):

Baseplate thickness:

Suppcx leg height:

Support leg type:

Number of suppor'egs:

Remote lifting and handling provision:

Poison mater'l:

Poison lengt:::

Poison width:

Cell Pitch:

8'5"

~ 0.04" 168

+ 1/16" 0.75" 5.25" (nominal)

Remotely adjustable legs 4

(minimum)

'es Boral 144 7

5 8.97" (nominal) 2-11 '

Sl>ea tl) in'"i@ore

3. 3. 2 COMPOST'l'E I)OX hSSEHBf.Y

~ e

~

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Box Cells Ce1 1

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Pit h Developed

) c o11 Boral panel Snea thin>

Baseplate One Znch Lateral Plow Hole (Typical)

Ficure 3.3.5 ELEVATZON VIEN OP RACK gODULE 3-14

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ANALYSES PERFOI&fED IN SUPPORT OF Tl<S LICENSING APPLICATION RAULIC QUALIFICATION 2.

SEISMIC QUAIJFICATIONOF RACKS 3.

SEISMIC QUALIFICATIONOF 1HE POOL STRU CAL ACCIDENTANALYSES 5.

CRITICALIIYSAFETY EVALUATION 6.

KC)IOLOGICALASSESSMEMI

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DISCWWGE SCENARIOS 1.

NORl&G. DISCEEARGE, 80 ASSEMBLIES SINGLE EEL POOL COOLING TRPB 2.

NORMALDISCWWGE, TWO COOLlNG TR.A3NS 3.

FULL CORE OFFLOAD, TWO COOLING TWINS

Table 5.4.3 DATA FOR SCENARIOS 1 THROUGH 3

Discharge ZD No of Assemblies Time After Shutdown when Transfer Begins (hrs) offload Expo.

T~i Time (hrs)

(hrs)

Discharge 1

Discharge 1

80 80 168 168 19.07 39420

19. 07 39420 Discharge 1

80 Discharge 2

193 (Full core) 168 168

19. 07 39420 46.00 39420 5>>18

Table 5.5.1 POOL BULK T~~ZRATURE AND HEAT CATION RATE DATA Coincident Heat Generat cn Rate TRsx Max. Pool Bulk Temo.,

Time

, Coincident to T~

(after reactor

~sut loMO 35.24E6 35.57E6 60.46E6 154. 19 124 S5 145.73 212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> 199 hours 223 hours0.00258 days <br />0.0619 hours <br />3.687169e-4 weeks <br />8.48515e-5 months <br /> 5-19

Table 5.5.2 TIVE TO BOIL EOR VARIOUS DZSCHARG SCZNAMOS Case No.

Time-to-Boil (hours)

G~OGPW 7.06 10-46 4.66 5-20

150 145 140 135 CL 130 OO

a. 125-CO 120 115 110 105 100 200 300 400 500 600 700 800 900 1000 1l00 1200 1lMF AR'ER REACTOR SIIUTOOV/N, IPR FXGURE 5. 5. 4 BULK POOL TENPERhTURE FOR ChSE 3

Table 5.F 1 r

Local and Cladding Temperature Output Data for the Maximum Pool Hater Condition (Case 1)

Conc'"

on No Blockage 50% Blockage Maximum Local Wats Temn 228.4 238.9 Maximum Cladd'g

~orna.

'P 251.9 259. 6 5-23

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DONALD C.

COOK NUCLEAR STATION CRITICALITY SAFETY ANALYSIS SPENT FUEL STORAGE RACKS MIXED ZONE THREE REGION DESIGN REGION 1 FRESH FUEL OF 4.95%

ENRICHMENT (OR FUEL OF ANY BURNUP)

REGION 2 BARRIER ZONE FUEL OF 4.95%

ENRICHMENT SURNED TO 50 MWD/KgU (OR REACTIVITY EQUIVALENT)

REGION 3 FUEL OF 4.95%

INITIAL ENRICHMENT BURNED TO 38 MWD/K U (OR REACTIVITY EQUIVALBIT)

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FUEL ASSEMBLY TYPES CONSIDERED (CASMO CALCULATIONS)

FUEL TYPE ENRICHMENT BURNUP K-INFINITE W 15 X 15 W 15 X 15 2.5 2.5 10 1.0145 0.9210 W 17 X 17 STND W 17 X 17 STND 2.5 2.5 10 1.0106 0.9188 W17 X 170FA W 17 X 17N OFA W

15 X 15 W

15 X 15 2.5 2.5 4.95 4.95 10 0

40 1.0087 0.9144 1.1941 0.9204 W 17 X 17 STND 4.95 1.1880 W 17 X 17 OFA W 17 X 17 OFA 4.95 4.95 40 1.1933 0.9149 ANF 17 X 17 4.95 1.1883

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RR 1 NQf%MISNfhMKPATIESi S 504 REGION 1

CELLS 0 1447 REGION 2 9 1662 REGION 3 CELLS CELLS

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RL 2 NlEI%lSTORAGE PATTKSi IHI EMPT LOCATIONS (CHECKERBOARO) r 629 REGION 1

156 EMP1Y LOCATIONS CELLS 0 1447 REGION 2 CEU S 9 1341 REGION 3 CELLS

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10000 UNAC 8URNU KPTAB DOMA E

IN 2.0 2.5 3.0 XS h.o INITIAL ENRICHMENT, %U-255 hS 5.0

7.50

+ 0.06" BORAL IN 0.109" GAP 0.101

+ 0.005" THK 0.0345 gmB-10/cm FUEL OO 0.3659 IN.

0.

DENSITY 10.29 9/cc 00 NUMBER 204 (15 x 15)

CLAD IO 0.3734 IN.

ROD OO 0.422 IN.

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?ITCII 0.563 IN.

OOSOOCi, TNIMSLES OD O.546 IN.

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OOOOOOOOOOO OOOOOOOOOK 0.035" SS SHEATH 0,219" B.75 = 0.04" 3OX I.D.

OOU PITCH 8.969" NOhllNAL NOT TO SCALEI

.075" SS BOX FUEL STORAGE CELL CROSS SECTION

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I RES'.CN 3 REG."Nj REGION 3 RE;.'"N3 REGION/

REQiOlIQ ROBICS L REG::N 4 REGION L FRESH FUEL i

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2" WATER GAP WITH REFLECTING BOUHOARY CONDITIONS OR 50 CM WATER REFLECTOR WITH ZERO FLUX BOUNDARY CONDITION

1.20 1.10 0.90 0.85 0.80 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.9 INITIAL ENRICHMENT, WTR U-235

1.10

~~ 0.90 0.85 0.80 0

5 10 15 20 25 30 35 40 45 50 FUEL BURNUP, MWD/KgU

5.00 4.75 4.50 4.25 4.00

~~3.75

~ 3.50 K

~ 3.25

~ 3.00

~ 2.75

~ 2.50 M 2.25

~ 2.00 CXw 1 75 1.50 1.25 1.00 0.75 0

5 10 15 20 25 30 35 40 45 50 55 60 BURNUP, MWD/KgU

j 4;

Q ~ a, 0 (

~

g'I F

9 P

0.950

+~ 0.945 0.940

< 0.935

~ 0.930 z'

0.925 I

~ 0.920 O

0.915 ooo= 0.910

- 0.905

~ 0.900 25 30 35 40 45 50 FUE:L BURNUP, MWD/KgU 55 60

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0.935 0.930 0-0

~ 0.925

~~ 0.920 O

0.915 0.910 0.5 1.0 1.5 2.0 2,5 WATER GAP BETWEEN MODULES, inches

1.2 1.0 toO 0.8 RKD Cl 0.6 l

0.4 o,c,gag 0.2 0.0 FUEL HElGHT {ft)

Table 4.1

SUMMARY

OF CRITICALITYSAFETY ANALYSES Design Basis burnups at 4.954 f 0.054 initial enrichment Temperature for analysis Reference k

(KENO-5a)

Calculational bias, 6k Uncertainties Bias statistics (954/95<)

KENO-5a statistics (954/954)

. Manufacturing Tolerances Rater-gap Fuel enrichment Fuel density Burnup (38 MWD/KgU)

Burnup (50 MWD/KgU)

Eccentricity in position Statistical combination of uncertainties Axial Burnup Effect Total Maximum Reactivity (k )

0 in Region 1 50 in Region 2

38 in Region 3

20'C (68'F) 0.9160 0.0090 0.0021 2 0.0012 R 0.0064 k 0.0045 k 0.0034 k 0.0035 0.0019 0.0047 0.0019 i 0.0110 0.0037 0.9287 t 0.0110 0.940 See Appendix A Cl)

SQuare root of sum of sQuares.

4-22

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+ 35000 O

> 30000

~ 2soaa 2:

D

~~20caa 4

'l5000 ACC BURN PTABL P

DOM IN

~yO qCr UNAC EPTAB BURNU DOM E

IN 2.0 2.5 3.0 3.5 t.O W.S INITIAL ENRICHMENT, sU-235 5.0 ACCEPTABLE BURNUP DOMAIN IN REGION 2 SHOWING EXISTING SPENT FUEL ASSEMBUES

SEXSMIC QUALIFICATION OF CKS 0 UL S 00

~SEES 1 ~

2 ~

3 ~

4 ~

5.

GENERATE STATISTICALLY INDEPENDENT TIME-HISTORIES PROVE NUREG COMPLIANCE DEMONSTRATE STATISTICAL INDEPENDENCE PREPARE A DYNAMIC MODEL FOR THE RACK STRUCTURE PERFORM DYNAMIC ANALYSIS - DYNARACK a.

SINGLE RACK 3-D MODEL b.

WHOLE POOL MULTI-RACK MODEL 6.

7.

8 QUALIFY POOL STRUCTURE LINER FATIGUE EVALUATION MECHANICAL ACCIDENT EVALUATION

Back Geometr c

Centerline P)e H/q g4 pit C

4 O

Cy Long Direction Support y

Ps/

S]

.X TQQ.cal

~

Friction

Element, Figure 6-5.1 SCHEMATIC MODEL FOR DYNARACK 6-64

Y 0 RACK-FUEL IMPACT WELD STRESSES (CELL/BASEPLATE)

ED STAL BASEP 210'605 psi W B EQcQE 31258 29820 psi Fy (M1

+ M2) 1 MY

.577 1.0 BETWEEN SUPPORT TUBES MAXXMUM CORNER HORIZONTAL DISPLACEMENT MAXIMUM DBE STRESS FACTORS D R.

+ BEND.

593'06790 52718 504 OF INITIAL GAP CELL CROSS-SECTION PEDESTAL CROSS-SECTION

.239

.460 2.0 2 '

DROP TO TOP OF ASSEMBLY

( 15501

)

(3 6" HEXGHT)

DROP TO BASEPLATE LINER FATIGUE 5.341" (DAMAGE) 2 906" MAX.

MAX. STRESS DIFF. 25730 psi, 15" NO LINER CONTACT ALLOW FOR NO PLASTICITY 50100 psi

I c~

'I 5

'l A

k

'l l

RACK 5'ACi<

1

~

RACK 18 CASK AREA RACK 5 RACK 11 RACK 17 4

2 iRACK 2~I RACK 4 1

2 1

RACK 10 4

4 1

RACK 16 1

RACK 22 4

4 RACKi RA':K 9 1

RACK 15 2

1 RACK 21 4

2 1

RACK 2 2

RACK u~

2 1

2 1

RACK 14 RACK 20 1

RACK 1

RACK 7 2

RACK l~

2 RACK 19 3

FIGURE 6. 14

~ 1 RACK Ate FOOY PEDESD*L NUMBERING FC1R D. C. COOK t1ULTl-RACKHODEL 6-71

Table 6 ~ 14.5 MAXIMUMRACK DISPLACEMENT AND FOOT LOAD a04 Remarks Single Rack Analysis Maximum Rack Corner Displacement c

0.0778 Maximum Foot Pedestal o ce 183,300 WPMR, p ~

0

~ 2 0 ~ 1455 (Rack f21 in y)

gpMR, Random p 0.3322 (Rack 416 in x)

~MR, p 0.8 0.4416 (Rack 418 in y) 157,400 (Rack

$ 19, Foot 4) 170,900 (Rack 419, Foot 4) 180,900 (Rack 45, Foot 2) p ~ friction coefficient 6>>51

2.03 2.00 COOK POOL MULTI-RACK SEISMIC ANALYSIS, RUN MP2 (Rondom Cof.)

RACK 16 TO RACK 17 NORTH CORNER DYNAMIC GAP AT RACK TOP 1.98 xO 1.95 9 1.93 D

1.90 P 1.88 I

1.85 1.83 1.80 0

1 2

3 4

5 6

7 8

9 10 11 12 13 I 4 15 16 TIME. SEC.

~

~

0 C

S 0 S

1 ~

2.

3 ~

4 NO INTER-BACK IMPACT IN THE CELLULAR REGION NO RACK-TO-MALL IMPACT MULTI-RACK ANALYSIS GIVES MUCH LARGER DISPLACZZENTS THAN OLDER 3-D SINGLE RACK RESULTS LARGE MARGINS AGAINST STRESS LIMITS

~

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OOL S

U OA INGS 1 ~

2 ~

3 ~

4 ~

DEAD WEIGHT OF POOL STRUCTURE DEAD WEIGHT OF RACK MODULES DYNAMIC LOAD OF SUPPORT PEDESTALS (DBE or OBE)

INERTIA LOADING DUE TO SELF-EXCITATION 5 ~

6 ~

HYDRODYNAMIC LOADING THERMAL LOADING

p l

l a,'

r'

0 OO SS S

HYDROSTATIC RACKS + FUEL (STATIC)

RACK + FUEL DYNAMIC ADDER (EQUIVALENT UNIFORM PRESSURE)

WATER DYNAMIC ADDER (USING APPROPRIATE VERTICAL g)

DYNAMIC ADDER ON WALLS DUE TO SLOSHING 17.33 psi 16.65 psi,

.59 psi 3'8 psi 2.573 psi (N-S) 4.114 psi (E-W)

PER P

KZP 108.6 <

364.19 KlP/ft ft CULA D

CH G

KIP 62.757 ft KZP 380.3 ft

1 ALL FACTORED LOADS PRODUCE MOMENTS AND SHEARS WHICH ARE LESS THAN THE LOCAL WORKING STRENGTH.

2.

CUMJLATIVE DAMAGE FACTOR FOR THE LINER DUE TO 1

DBE AND 2 0 OBE EVENTS IS LESS THAN 1.0.

Spent Fuel Pool Rerack ALARA Actions

~ Review data from other plants for lessons learned

~ Formal ALARA review

~ Pre-job briefings

Spent Fuel Pool Rerack Estimated Person-Rem Exposure Preparation Installation Prepare replaced racks for shipment 13 - 26 3.5 -

6.2 1.0 2 0 Total 5.5 10.8

Contamination and Hot Particle Control

~ Hydrolaze racks prior to removal from spent fuel pool

~ Rinse racks upon removal from spent fuel pool

~ Implement guidance for work in hot particle areas

~r