ML13322A309

Summary of 881207 Meeting W/Util,Westinghouse & Bechtel Re Reracking Spent Fuel Pools.List of Attendees & Viewgraphs Encl

ML13322A309
Person / Time
Site:	San Onofre
Issue date:	02/08/1989
From:	Hickman D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8902230114
Download: ML13322A309 (78)

Text

February 8, 1989 Docket Nos.:

50-361 and 50-362 FACILITY:

San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 LICENSEE:

Southern California Edison Company (SCE)

SUMMARY

OF MEETING HELD ON DECEMBER 7, 1988 RE:

SPENT FUEL POOL RERACKING On December 7, 1988, Southern California Edison Company (SCE) and represent atives of their subcontractors Westinghouse Electric Corporation (WEC) and Bechtel Power Corporation (BPC5, met with NRR staff to discuss their plans to rerack the spent fuel pools of San Onofre Units 2 and 3. The list of attendees is provided in Enclosure 1.

The meeting consisted of a presentation by SCE and their subcontractors with questions, comments and discussion by the staff. Enclosure 2 provides the briefing slides prepared by SCE.

A list of issues to be addressed in the amendment request is provided as.

original signed by Donald E. Hickman, Project Manager Project Directorate V Division of Reactor Projects -

III, IV, V and Special Projects

Enclosures:

As stated DISTRIBUTION D oFet ile NRC & Local PDRs PD #5 Reading JLee DHickman OGC (f/info only)

EJordan BGrimes ACRS (10)

MRJohnson (Region V)

NRC Participants 5

,DRSP/D:PD5 1 (mand:rw iv"GKnighton*

2/ 7/89 2/r/89_

8902230114 890208*

PDR ADOCK 05000361 P

PDIC

p W0 U'NITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 8, 1989 Docket Nos.:

50-361 and 50-362 FACILITY:

San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 LICENSEE:

Southern California Edison Company (SCE)

SUMMARY

OF MEETING HELD-ON DECEMBER 7, 1988 RE:

SPENT FUEL POOL RERACKING On December 7, 1988, Southern California Edison Company (SCE) and represent atives of their subcontractors Westinghouse Electric Corporation (WEC) and Bechtel Power Corporation (BPC5, met with NRR staff to discuss their plans to rerack the spent fuel pools of San Onofre Units 2 and 3. The list of attendees is provided in Enclosure 1.

The meeting consisted of a presentation by SCE and their subcontractors with questions, comments and discussion by the staff. Enclosure 2 provides the briefing slides prepared by SCE.

A list of issues to be addressed in the amendment request is provided as.

Donald E. Hickman, Project Manager Project Directorate V Division of Reactor Projects -

III, IV, V and Special Projects EnclosurE:S:

As stated

44hgj Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Units 2 and 3 cc:

Mr. Gary D. Cotton Mr. Hans Kaspar, Executive Director Senior Vice President Marine Review Committee, Inc.

Engineering and Operations 531 Encinitas Boulevard, Suite 105 San Diego Gas & Electric Company Encinitas, California 92024 101 Ash Street Post Office Box 1831 San Diego, California 92112 Mr. Mark Medford Southern California Edison Company Charles R. Kocher, Esq.

2244 Walnut Grove Avenue James A. Beoletto, Esq.

P. 0. Box 800 Southern California Edison Company Rosemead, California 91770 2244 Walnut Grove Avenue P. 0. Box 800 Mr. Robert G. Lacy Rosemead, California 91770 Manager, Nuclear Department San Diego Gas & Electric Company Orrick, Herrington & Sutcliffe P. 0. Box 1831 ATTN:

David R. Pigott, Esq.

San Diego, California 92112 600 Montgomery Street San Francisco, California 94111 Richard J. Wharton, Esq.

University of San Diego School of Alan R. Watts, Esq.

Law Rourke & Woodruff Environmental Law Clinic 701 S. Parker St. No. 7000 San Diego, California 92110 Orange, California 92668-4702 Charles E. McClung, Jr., Esq.

Attorney at Law Mr. S. McClusky 24012 Calle de la Plaza/Suite 330 Bechtel Power Corporation Laguna Hills, California 92653 P. 0. Box 60860, Terminal Annex Los Angeles, California 90060 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. C. B. Brinkman 1450 Maria Lane/Suite 210 Combustion Engineering, Inc.

Walnut Creek, California 94596 7910 Woodmont Avenue, Suite 1310 Bethesda, Maryland 20814 Resident Inspector, San Onofre NPS c/o U. S. Nuclear Regulatory Commission Mr. Dennis F. Kirsh Post Office Box 4329 U.S. Nuclear Regulatory Commission San Clemente, California 92672 Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Sherwin Harris Resource Project Manager Public Utilities Department City of Riverside City Hall 3900 Main Street Riverside, California 92522

ENCLOSURE 1 SPENT FUEL POOL RERACKING MEETING SAN ONOFRE UNITS 2 AND 3 DECEMBER 7, 1988 LIST OF ATTENDEES NAME AFFILIATION FUNCTION The Nandy SCE Licensing Jack Rainsberry SCE Licensing Derrick Mercurio SCE Licensing Raymond Baker SCE Project Engineering Richard Blaschke SCE Civil Engineering Richard Miller SCE Civil Enginerring Dennis Ostrom SCE Civil Engineering Tom Watson WEC Engineering Analysis Keith Matthews WEC Licensing Harry Flanders WEC NCD Analysis Don Green WEC NCD Analysis William Guerin WEC Nuclear Safety Richard Day BPC Structural Engineering Selcuk Atalik BPC Task Engineering Don Hickman NRR Project Manager Charles Trammell NRR Project Manager Jerry Wermiel NRR Plant Systems Norman Wagner NRR Plant Systems Neil Thompson rJRR Structural Engineering Hans Asher NRR Structural Engineering David Jeng NRR Structural Engineering Herman Graves NRC Research Giuliano DeGrassi NRC Brookhaven N1ational Lab

ENCLOSURE 2 SPENT FUEL POOL RERACKING HEAVY LOADS EVALUATION SAN ONOFRE UNITS 2 AND 3 DECEMBER 7, 1988

AGENDA I. INTRODUCTION (SCE)

DERRICK MERCURIO II. HEAVY LOADS (BECHTEL)

RICHARD DAY

1. INTRODUCTION A.

SCOEL

1.

INCREASE SPENT FUEL STORAGE CAPACITY A.

INCREASE FROM 800 TO APPROXIMATELY 1572 ASSEMBLIES PER UNIT B.

STORAGE CAPACITY TO YEAR 2002 WITH CORE OFF-LOAD

I. INTRODUCTION B.

PROJECT SCHEDULE AND MILESTONES 6/3/88 INITIAL MEETING WITH NRC 12/7/88 MEETING WITH NRC 2/1/89 SUBMITTAL OF PROPOSED LICENSE AMENDMENT 3/30/89 BEGIN RACK FABRICATION FOR UNIT 2 8/1/89 LICENSE AMENDMENT ISSUED BY NRC 10/2/89 RACK DELIVERY FOR UNIT 2 10/89 BEGIN RACK INSTALLATION IN UNIT 2 (COMPLETE RACK INSTALLATION DURING CYCLE 5 OPERATION)

C. HEAVY LOADS CONSIDERATIONS 0

CONSTRUCTION SEQUENCING TEMPORARY SPENT FUEL STORAGE IN CASK POOL 0

TEMPORARY CRANE -

JANUARY 15, 1989 AWARD 0

NUREG-0612 EVALUATIO-N

AGENDA

1. RACK REMOVAL/INSTALLATION SEQUENCING

2. SAFE LOAD PATHS

3. TEMPORARY CONSTRUCTION CRANE

4. CONTROL OF HEAVY LOADS (NUREG 0612)

5. POSTULATED CONSTRUCTION LOAD DROP

6. CASK POOL COVER DESIGN FUNCTIONS

-At It A

RACK REMOVAL/INSTALLATION SEQUENCING APPROACH

- SPENT FUEL STORED IN CASK POOL (DURING RERACKING)

SIGNIFICANT CRITERIA

- MAINTAIN SAFE LOAD PATH

- PROVIDE MINIMUM 3 EMPTY ROWS OF CELLS (NO SPENT FUEL)

ADJACENT TO WORK AREA

- PROVIDE FLEXIBILITY IN SPENT FUEL LOCATIONS

- MINIMIZE REQUIRED FUEL SHUFFLING

SPENT FUEL POOL (UNIT 2 )

1. 13 CASKC

1. 12

1. 15 PO ORIGINAL CONDITION

SPENT FUEL POOL (UNIT 2)

CASK POOL FINAL CONFIGURATION

RERACK SEQUENCING SPENT FUEL POOL (UNIT 2) 800 FUEL STORAGE LOCATIONS IN EXISTING RACKS 480 FUEL ASSEMBLIES STORED IN POOL (POST CYCLE 5 REFUELING)

ORIGINAL CONDITION 320 EMPTY FUEL STORAGE LOCATIONS

PROPOSED RERACK SEQUENCING PLACE 180 FUEL ASSEMBLIES IN CASK POOL RACK PLACE PROTECTIVE COVER OVER CASK HANDLING POOL LOCATE REMAINING 300 FUEL ASSEMBLIES AT NORTH END REMOVE NES RACKS #10-15 STEP 1 REMOVE PIPING AND SUPPORTS FROM VACATED AREA.

PROPOSED RERACK SEQUENCING INSTALL W RACKS #7 & 8 SHIFT 132 FUEL ASSEMBLIES INTO W RACK #8 REMOVE NES RACKS #7-9 STEP 2 REMOVE PIPING AND SUPPORTS FROM VACATED AREA

PROPOSED RERACK SEQUENCING a3

m.

• INSTALL W RACK #6

• PLACE ALL FUEL ASSEMBLIES IN W RACKS #6 & 8

• REMOVE NES RACKS #1-6 STEP 3

• REMOVE REMAINING PIPING AND SUPPORTS

PROPOSED RERACK SEQUENCING INSTALL W RACKS #1-4 REMOVE PROTECTIVE COVER FROM CASK HANDLING POOL SHIFT 180 FUEL ASSEMBLIES FROM CASK POOL TO SPENT FUEL POOL STEP 4 PLACE W RACK #7 IN SPENT FUEL POOL

SAFE LOAD PATHS FUEL HANDLING BUILDING (UNIT 2)

• A v

PARTIAL PLAN AT ELEV.

63

-6 FOOL DECK

TEMPORARY CONSTRUCTION GANTRY CRANE guy 5:91 ~ ~

~

~

~

E 94f711/'a,,'ll EL 7&'

SECTION - SPENT FUEL POOL (UNIT 2)

TEMPORARY GANTRY CRANE

-35 TON UPGRADED COMMERCIAL CLASS C

- MEET CMAA-70 AND CHAPTER 2-1 OF ANSI B30.2 REQUIREMENTS

- FACTOR OF SAFETY FOR LOAD BEARING MEMBERS

- 3 AGAINST MINIMUM TENSILE YIELD STRENGTH

- 5 AGAINST AVERAGE ULTIMATE STRENGTH

- MEET SRP LOAD COMBINATIONS (INCLUDES DBE)

- DUAL HOLDING BRAKES ON HOISTS (MAIN AND AUXILIARY) RATED AT 150% OF MOTOR TORQUE

- GANTRY AND TROLLEY BRAKES RATED AT 150%

MOTOR TORQUE

- HOOKS TESTED AT TWICE RATED CAPACITY

NUREG 0612 CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS SECTION TITLE 5

GUIDELINES FOR CONTROL OF HEAVY LOADS 5.1.1 GENERAL (GUIDELINES) 5.1.2 SPENT FUEL POOL AREA - PWR

NUREG 0612 SECTION 5.1.1 GENERAL (GUIDELINES)

EXTENT OF REQUIREMENTS COMPLIANCE

2. PROCEDURES COMPLY

3. CRANE OPERATORS COMPLY

4. SPECIAL LIFTING DEVICES COMPLY

5. LIFTING DEVICES THAT ARE COMPLY NOT SPECIALLY DESIGNED (SLINGS)

7. CRANE DESIGN COMPLY

NUREG 0612 SECTION 5.1.2 (GUIDELINES FOR)

SPENT FUEL POOL AREA - PWR EXTENT OF REQUIREMENTS COMPLIANCE (3) (a) "HOT" SPENT FUEL AT ONE COMPLY LOCATION WITH MAXIMUM (NO "HOT" FUEL)

SEPARATION FROM LOAD PATH (b) PREVENT LOAD BLOCK MOVEMENT COMPLY WITHIN 25' (HORIZ) OF "HOT" FUEL (NO "HOT" FUEL)

NUREG 0612 SECTION 5.1.2 (GUIDELINES FOR)

SPENT FUEL POOL AREA - PWR EXTENT OF REQUIREMENTS COMPLIANCE (3) (c) MECHANICAL STOP/ELECTRICAL COMPLY INTERLOCK TO PREVENT TRAVEL (NOT APPLICABLE)

WHERE DROP COULD DAMAGE EQUIPMENT (SAFE SHUTDOWN)

- ANALYZE DROPS IN COMPLY UNRESTRICTED TRAVEL AREAS TO ENSURE NOT CAUSE OF CRITICALITY, LEAKAGE UNCOVERING FUEL, OR LOSS OF SAFE SHUTDOWN EQUIPMENT

NUREG 0612 SECTION 5.1.1 GENERAL (GUIDELINES)

EXTENT OF REQUIREMENTS COMPLIANCE

1. SAFE LOAD PATHS COMPLY.

EXCEPT MARKINGS OFFLOOR

6. CRANES COMPLY EXCEPT LOADTESTS

- INSPECTION, TESTING, AND (2-2.2.2) PERFORMED AT MAINTENANCE PER CHAPTER SHOP AND SITE PRIOR TO 2-2 OF ANSI B30.2-1976 INSTALLATION

TEMPORARY GANTRY CRANE TESTING PER ANSI B30.2-1976

- OPERATIONAL TESTS (SECTION 2-2.2.1)

AT FACTORY PRIOR TO SHIPMENT AT SITE PRIOR TO FINAL INSTALLATION IN PLACE (OVER POOLS) PRIOR TO INITIAL USE RATED LOAD TEST (SECTION 2-2.2.2)

AT FACTORY PRIOR TO SHIPMENT (1.25 X 35 TON)

AT SITE PRIOR TO FINAL INSTALLATION (1.25 X 35 TON)

MODIFIED LOAD TEST (HOIST & TROLLEY ONLY)

IN PLACE (OVER CASK POOL ONLY) PRIOR TO INITIAL USE (1.25 X MAX. ANTICIPATED LOAD)

NUREG 0612 SECTION 5.1.2 (GUIDELINES FOR)

SPENT FUEL POOL AREA - PWR EXTENT OF REQUIREMENTS COMPLIANCE (3) (b) LOAD BLOCK MOVEMENT WITHIN 25' (HORIZ) OF FUEL

- SUFFICIENT FUEL DECAY COMPLY

- APPROVAL OF SHIFT MEET INTENT BY SUPERVISOR PROCEDURE APPLICATION AND SCHEDULED WORK ACTIVITIES MECHANICAL STOP/ELECTRICAL COMPLY INTERLOCK IN PLACE PRIOR TO PLACING "HOT" FUEL IN POOL

NUREG 0612 SECTION 5.1.2 (GUIDELINES FOR)

SPENT FUEL POOL AREA - PWR EXTENT OF REQUIREMENTS COMPLIANCE (3) (b) LOAD BLOCK MOVEMENT WITHIN 25' (HORIZ) OF FUEL

- SUFFICIENT FUEL DECAY COMPLY

- APPROVAL OF SHIFT MEET INTENT BY SUPERVISOR PROCEDURE APPLICATION AND SCHEDULED WORK ACTIVITIES MECHANICAL STOP/ELECTRICAL COMPLY INTERLOCK IN PLACE PRIOR TO (NOT APPLICABLE)

PLACING "HOT" FUEL IN POOL

NUREG 0612 SECTION 5.1.2 (GUIDELINES FOR)

SPENT FUEL POOL AREA - PWR EXTENT OF REQUIREMENTS COMPLIANCE (3) (d) CARRY LOAD (CASK) MAXIMUM MAXIMUM 24 INCHES 6 INCHES, OR LESS, ABOVE FLOOR IN POOL (RACK WEIGHT < CASK)

EXCEPT WHEN ENTERING/

LEAVING ALL OTHER AREAS 12 INCH MAXIMUM (3) (e) ANALYZE POSTULATED LOAD COMPLY - APPLYING DROPS PER NUREG APPENDIX A DROP ANALYSES TO NORMAL TRAVEL PATHS

POSTULATED CONSTRUCTION LOAD DROP SPENT FUEL POOL RESULTS: 1) LINER (3/16" THICK) AND RELINER (1/8" THICK)

PENETRATED

2) CONCRETE BASEMAT PENETRATED ABOUT 5 3/4 INCHES (7% OF THICKNESS)

3) LEAKAGE CONFINED TO LEAK CHASE SYSTEM (MAXIMUM FLOW RATE < 60 GPM)

4) MAKEUP WATER SUPPLY (150 GPM)

5) TECHNICAL SPECIFICATION WATER LEVEL MAINTAINED

CASK POOL COVER DESIGN FUNCTIONS PRECLUDE COVER DROP IN CASK POOL DURING INSTALLATION/REMOVAL WITHSTAND POSTULATED CONSTRUCTION LOAD DROPS (COMPLY WITH NUREG 0612 APPENDIX A)

ANCHORCOVERTOPOOLDECK PROVIDE UNIFORM WORKING SURFACE (LAYDOWN AREA)

I 1-7 I

~

CA6*

Pooe CO II CA O.5 Il II liiilI 1711 I

_CS I I PLI(AS<POLCVR

C RA'I /1JEHOK POOL COV COVER SUPPO EAM PooL SEC Ti/oNA

SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 SPENT FUEL POOL RERACK PRESENTATION DECEMBER 7, 1988

AGENDA INTRODUCTION (SCE)

DERRICK MERCURIO SEISMIC ANALYSES OF SPENT FUEL RACKS (WESTINGHOUSE)

HARRY FLANDERS

I.

INTRODUCTION A.

S.fE

1.

INCREASE SPENT FUEL STORAGE CAPACITY A..

INCREASE FROM 800 TO APPROXIMATELY 1572 ASSEMBLIES PER UNIT B.

STORAGE CAPACITY TO YEAR 2002 WITH CORE OFF-LOAD

I. INTRODUCTION B.

RACK DESIGN PARAMETERS

1.

FREE STANDING RACKS

2.

FIXED BORAFLEX POISON

3.

2 REGION DESIGN A.

312 LOCATIONS (APPROXIMATE) -

NEW AND RECENTLY IRRADIATED FUEL B.

1260 LOCATIONS (APPROXIMATE) -

IRRADIATED FUEL

4.

LICENSE FOR 4.1% ENRICHED FUEL (5.1% DESIGN)

5.

STORE UNITS 1, 2 AND 3 FUEL

I.

INTRODUCTION C.

PROJECT SCHEDULE AND MILESTONES 6/3/88 INITIAL MEETING WITH NRC 12/7/88 MEETING WITH NRC 2/1/89 SUBMITTAL OF PROPOSED LICENSE AMENDMENT 3/30/89 BEGIN RACK FABRICATION FOR UNIT 2 8/1/89 LICENSE AMENDMENT ISSUED BY NRC 10/2/89 RACK DELIVERY FOR UNIT 2 10/89 BEGIN RACK INSTALLATION IN UNIT 2 (COMPLETE RACK INSTALLATION DURING CYCLE 5 OPERATION)

SAN ONOFRE UNITS 2 & 3 FUEL RACKS SEISMIC ANALYSIS o

Pool Layout o

Background Information o

Fuel Rack Structural Model o

Single Rack Seismic Models Full Fuel Loading Partial Fuel Loading (Quadrant)

Partial Fuel Loading (4 Rows)

Partial Fuel Loading (1 Row)

Empty Rack Displacement Results o

Multiple Rack Seismic Models Full/Full Full/Empty o

Displacement Results Rack Absolute Displacements Rack Relative Displacements Displacement Characteristics o

Conservatisms AEA-88-304

SAN ONOFRE UNIT 2 OR UNIT 3 SPENT FUEL POOL LAYOUT 528.00 REF.

3. 44

.13590

-Z-.eL TYP.

3.S (z}

125.50 12 X 13 14 X 15 14 X 1S 14 X 15 uP.

RRD R

R 27600 REF.

7.00 331 125.50 12 X 13 14 x 15 14 x 1S 14 x 1S RI RTI Rfn Rn 6.90

.0

BACKGROUND INFORMATION

BACKGROUND INFORMATION Friction

.8 Maximum/.2 Minimum

Reference:

Rabinowicz, E., Friction Coefficients of Water - Lubricated Stainless Steels for a Spent Fuel Rack Facility, Report Q 23.1.3 to Boston Edison Co.,

November 1976 Finite Element Code WECAN, Westinghouse Electric Computer Analysis.

Configuration control under strict QA standards.

Generic review by NRC and reviewed 2 times by Franklin Institute for fuel rack application.

Hydrodynamic Mass Potential flow theory

Reference:

Fritz, R. 1, The Effects of Liquids on the Dynamic Motions of Immersed Solids, Transactions of the ASME, February 1972 Time History Developed by Bechtel Three statistically independent components 80 seconds duration Standard Fuel Dynamic properties supplied by fuel vendor Characteristics AEA-88-304

FUEL RACK STRUCTURAL MODEL

SEISMIC MODEL DEVELOPMENT FOUE

++

++

FUEL RACK MODULE STRUCTURAL MODEL

.SEISMIC M,,ODEL

FUEL RACK STRUCTURAL MODEL REGION II Cell to Cell Connection Cell Base Plate Support Pad

EFFECTIVE STRUCTURAL PROPERTIES

-CELL TO CELL CONNECTION CELL ASSEMBLY SUPPORT PAD STIFFNESS p

D[KI

EQUIVALENT STRUCTURAL MODEL MODE SHAPES I

I I

I.

I 1ST MODE 2ND MODE 3RD MODE 4TH MODE 5TH MODE 6TH MODE 7TH MODE 12.7 HZ 40.4 HZ 74.5 HZ 116.3 HZ 165.8 HZ 226.86 HZ 304.2 HZ

SINGLE RACK SEISMIC MODELS FULL FUEL LOADING PARTIAL FUEL LOADING (QUADRANT)

PARTIAL FUEL LOADING (4 ROWS)

PARTIAL FUEL LOADING (1 ROW)

EMPTY RACK DISPLACEMENT RESULTS

THA D IMEN NNLUIEA SEI 1C MMEL M

xI V.

MG/

NOLINEAR SEISMIC MOSrl SINGLE 9 ACK 12-D VIEW OF 3-0 W, CELL TO CELL HYDRODYNAMIC MASS, CONNECTION FUEL RACK CELL ASSEMBLY FUEL ASSEMBLY MM FUEL GRID ROTATIONAL\\

Mt STIFFNESS\\

HYDRODYNAM IC MASS, FUEL FUEL -TO -CELL---***Mo GAP ELEMENT M.M FUEL BASE LIFT-OFF ELEMENT

FUEL AND CELL MODE SHAPES REGION 2 STANDARD FUEL FUEL IST FUEL 2ND FUEL 3RD FUEL 'TH CELL 1ST FUEL 5TH FUEL 6TH F

FUEL 8TH CELL 2ND FUEL 9TH FUEL 10TH FUEL 11TH CELL 3RD CELL 4TH CELL 5TH

PARTIAL FUEL LOADING MODEL (OUADRANT LOADING)

EMPTY CELLS CELLS WITH FUEL FUEL

PARTIAL FUEL LOADING MODEL (4 ROW LOADING)

CELLS WITH FUEL FUEL EMPTY CELLS

MULTIPLE RACK SEISMIC MODELS FULL/FULL FULL/EMPTY

MULTIPLE RACK POOL MODEL. FULL/FULL 12-D VIEW OF 3-D MODEL)

MM MM M.

M MsM MU M

RACK 2 FULL RACK I FULL

MULTIPLE RACK POOL MODEL, EMPTY/FULL (2-D VIEW OF 3-D MODELI LM-1 UIQ.

MO U...

U...

RACK 2 RACK I EMPTY FULL

MULTIPLE RACK POOL MODEL (PLR4 VIEW)

N RACK TO RACK RACK TO RACK

-DIPCTION X-DIR

/CTION LMH][

H]MH RACK TO RACK Y-DIRECTIOR Y

MULTIPLE RACK MODULE MODE SHAPES REGION 2 STANDARD FUEL FULL/FULL CONDITION FUEL 2ND MODE CELLS OUT-OF-PHASE CELLS IN-PHASE 4.6 Hz 8.3 Hz 14.5 HZ EMPTY/FULL CONDITION FUEL 2ND MODE CELLS OUT-OF-PHASE CELLS IN-PHASE 4.6 Hz 8.4 Hz 15.2 Hz

DISPLACEMENT RESULTS RACK ABSOLUTE DISPLACEMENTS RACK RELATIVE DISPLACEMENTS DISPLACEMENT CHARACTERISTICS

SAN ONOFRE RACK DISPLACEMENT

SUMMARY

Max Disp (in)

Ret Disp (in)

Frequency (Hz)

MODEL TYPE*

Mu NS EW NS EW LOCATION NS EU Reg. 1, Std, Full

.2 1.50 1.80

.33

.41 Top/Top 14.1 17.0 Reg. 1, Std, Full

.8 1.49 1.37

.84

.44 Top/Top 14.1 17.0 Reg. 1, Std, E/F

.2 1.30 1.51 1.39

.96 Top/Top 14.7 18.6 Reg. 1, Std, E/F

.8 1.42 1.60

.99

.90 Top/Top 14.7 18.6 Reg. 1, Std, Quad

.2

.39

.43 Top/Top 15.1 17.1 Reg. 1, Std, Quad

.8

.67

.33 Top/Top 15.1 17.1 Reg. 1, Std, Rows

.2

.33

.60 Top/Top 15.1 17.2

-Reg. 1, Std, Rows

.8

.35

.64 Top/Top 15.1 17.2 Reg. 2, Std, Full

.2 1.00 1.39

.26

.59 Top/Top 13.8 14.1 Reg. 2, Std, Full

.8 1.44 1.36

.68

.76 Top/Top 13.8 14.1 Reg. 2, Std, E/F

.2 1.09 1.05

.99

.83 Top/Bot 14.2 15.2 Reg. 2, Std, E/F

.8 1.39 1.33 1.17

.96 Top/Top 14.2 15.2 Reg. 2, 2xStd, Full

.2 2.28 2.38

.44

.38 Bot/Top 11.7 12.0 Reg. 2, 2xStd, Full

.8 1.33 1.34

.87

.83 Top/Top 11.7 12.0 Reg. 2, 2xStd, E/F

.2 1.29 1.37 1.27 1.22 Bot/Bot 13.1 14.5 Reg. 2, 2xStd, E/F

.8 1.40 1.14

.98

.79 Top/Top 13.1 14.5 Loading Conditions Four terms are used to define the different loading conditions.

They are defined as follows. Full is used to describe the fully loaded situation.

ElF describes a case where one rack is full and another is empty.

Quad represents a single rack case where one quadrant only is loaded.

Rows describes a case where only four rack rows are loaded.

Finally, 2xStd represents a fuel assembly with double mass, increased beam stiffness, and increased hydrodynamic mass.

These are single rack cases. Relative Displacements do not apply.

MAXIMUM ABSOLUTE DISPLACEMENTS UNITS (IN.)

Friction Region 1 Region 2 Coefficient Standard Fuel Standard Fuel 2xStandard Fuel Full-Full Full-Full Full-Full N-S E-W N-S E-W N-S E-W

.2 1.50 1.80 1.09*

1.39 2.28 2.38

.8 1.49 1.604 1.44 1.36 1.33 1.34

• Empty-Full Condition AEA-88-304

MAXIMUM ABSOLUTE DISPLACEMENT PLOT REGION 1 STANDARD FUEL FULL/FULL FRICTION COEF.8_

2.5 Z2.0 N-S w

1.5 u

0 1.0 0.5 000 01.0

0 0

20 30 40 50 60 70 80 ST8RG IA. EG TIME (SEC.)

MAXIMUM ABSOLUTE DISPLACEMENT PLOTS REGION 1 REGION 1 STANDARD FUEL STFiNARD FUEL FLL/FULL R1/FULL FRICTION COEF.8 25 FRICTION COEF.2 S2.5 E2.6 N-S 1.5 1.5

-S 0.0--

0.0 C

to U

0 40 1 0 70W7 0

10 2

3D 4D w

to 70 mmas TIm CBC.)

TIME CSE.

I REGION 2 REGION 2 STFoARD FUEL STAtDA FUEL FTA.L/FULL FU.L/FULL FRICTION COEF.8 Z.

FRICTION C(EF

.2

.5 2.5~

1.5-Ng E-V E-V N-S 0.5 0.5 0.00.0 0

10 U

30 40 Is U

70 U

0 10 U

2 40 to 00 70 S

anae TIME Cen.)

TIME CW.)

MAXIMUM RELATIVE DISPLACEMENTS UNITS (IN.)

Friction Region 1 Region 2 Coefficient Standard Fuel Standard Fuel 2xStandard Fuel Empty-Full Empty-Full Empty-Full N-S E-W N-S E-W N-S E-W

.2 1.39

.96

.99

.83 1.27 1.22

.99

.90 1.17

.96

.98

.83*

• Full-Full Condition AEA-88-304

MAXIMUM RELATIVE DISPLACEMENT PLOT REGION 1 STANDARD FUEL EMPTY/FULL FRICTION COEF.2 2.0 Z

z o~-

1.5 Z

.1N-S w

u 1.0 a_

E-W/

w H0.5

/

C w 0.0 0

10 20 30 40 50 60 70 80 9091A.EmG TIME (SEC.)

MAXIMUM RELATIVE/ABSOLUTE DISPLACEMENT PLOTS REGION 1 FEGICN 1 s

F-. R.

STRFFMlD 5.2..

EEPTY/R.LL 2PTY/FLL FRICTION CCEP.2 FRICTION COEF.2 S1.5 6

E-W

-SN-S 1.0 1.0 E-w 0.5 -0.6 0.0 A0.0 0

10 o

0 a

W 70 so 0

to a

30 a

W so 70 11 smies TINm Cc.)

umms Tm C:.)

FEION 2 REGIGN 2 STORD FTEL STFNOFRDJ FUE.

BTTY/RS..

EWLL LU FRICTION COEF.8

2.

FRICTION COEF.8 1.0 1.5 0.0 0.0 a-a 0.50.

0 10 30 a

W o 70 s

0 10 g

0 D 4 W a w

.70 so YIN tm.

TIE CEm.)

I~

p

-n U

0~~

-n z

F n

M) 1 0

• 0 FX

-n 1

I a4U Ill r&

rt)

SLIDING/TORSION DISPLACEMENT CHARACTERISTICS IVICK I RACK J!

ST 4MD FUEL.

STAWDS0 FUEL FL.L/FULL.

FRICTION COEF.

0.6 FULL/FUL.L.

FRICTION C..

- Q.6 3.0

-8,g 30M

1. (4Z 2-

.0.0 OvuMIN 1.0

-Z 1.5 1-0.5

-2.0 a

10

-1.5 0

t0 Z

10 40 no so 70 w0 0

10 1D 0

40 0

s0 70 sD TmEM cSEC TIME CmEC)

RICK I

RAICK Z STANDFD PUEL STANDF FUEL FLLL/FLL. FRICTION COEF.

0.2 FULL/FL.L.

FRICTION COEF.

0.3 Z g0 P-wavus.0

m. -

L1an z

1.8-2

. t 1.0 1.0 0.6

0.

-0.0

-0.0 a-u4 0

10 D

40 D

70 10 0

10 10 0

40 1 70 wD TIME C8E)

.i TIME CBEC3

CONSERVATISMS

CONSERVATISMS

1.

ALL FUEL ASSEMBLIES RESPOND IN PHASE.

2.

FRICTION COEFFICIENTS OF 0.8 MAXIMUM AND 0.2 MINIMUM.

3.

FUEL ASSEMBLY GRID IMPACT DAMPING OF 4.4%.

4.

HYDRODYNAMIC MASS BASED UPON CONSTANT GAPS. As GAP DECREASES THE HYDRODYNAMIC MASS RESTORING FORCE INCREASES, BUT SINCE THE ANALYSIS IS BASED UPON CONSTANT GAPS, THE DISPLACEMENTS WHICH CLOSE THE GAPS ARE CONSERVATIVE.

5.

THE SEISMIC MODEL, WHICH USES 4 EFFECTIVE SUPPORT PADS TO REPRESENT THE 26 TO 33 ACTUAL SUPPORT PADS, ROCKED ONTO ONE SUPPORT PAD AND PRODUCED ROTATIONAL MOTION.

SINCE THE ACTUAL RACK MODULE HAS MULTIPLE INTERIOR SUPPORT POINTS AND WILL NOT LIFT OFF ONTO ONE SUPPORT POINT, THE SUPPORT PADS IN CONTACT WILL RESIST THE ROTATIONAL MOTION.

6.

NO FRICTION USED IN SUPPORT PAD BALL JOINT TO RESIST ROTATION WHEN RACK ROCKS ONTO ONE PAD.

7.

GAPS BETWEEN FUEL AND CELL WERE MAXIMIZED AND PRODUCE THE MAXIMUM IMPACT FORCES.

8.

MARGIN OF SAFETY AGAINST RACK IMPACT BASED UPON THE MINIMUM GAP DURING SEISMIC EVENT.

SUMMARY

/CONCLUSIONS SOPHISTICATED AND REALISTIC DYNAMIC MODEL USED IN ANALYSIS EVALUATED MANY CASES AND DETERMINED BOUNDING CASES DESIGN BASIS IS FROM MULTIPLE RACK MODEL RACK TO RACK AND RACK TO WALL IMPACT DOES NOT OCCUR REMAINING SEPARATION RESULTS IN COMFORTABLE MARGIN OF SAFETY

IV.

SUMMARY

(SCE)

DERRICK MERCURIO

NRC SEISMIC DESIGN INFORMATION REQUESTS FROM THE JUNE 3, 1988 NRC MEETING SAN ONOFRE UNITS 2 AND 3

1.

PROVIDE A STRENGTH EVALUATION FOR THE GROUND MOTION DBE TIME HISTORY.

2.

DESCRIBE THE CHANGES IN RACK FREQUENCY WITH WELD SIZE AND CLIPS, AND INCLUDE DESCRIPTIONS OF THE SIZES AND NUMBERS OF WELDS AND CLIPS.

3.

PROVIDE ASSURANCE THAT.RACK-TO-RACK SPACING IS MAINTAINED.

4.

COMPLETELY ADDRESS RACK-TO-RACK AND RACK-TO-WALL INTERACTIONS.

5.

EXPLAIN ANY EFFECT OF THE RACK LEVELING PAD ON ROCKING OR LIFTING FROM SEISMIC INPUTS.

6.

JUSTIFY SRSS COMBINATIONS OF ADJACENT RACK DISPLACEMENTS.

7.

INCLUDE ROTATION ABOUT ONE RACK SUPPORT FOOT AS A POTENTIAL WORST CASE DISPLACEMENT.

8.

EXPLAIN HOW HIGH FREQUENCY IMPACT LOADS ARE CALCULATED WITH THE PROPOSED RACK MODEL.

A.

DESCRIBE IN DETAIL HOW THE RACK CELL WALLS ARE DESIGNED INCLUDING THE FUEL ELEMENT/CELL WALL IMPACT MODEL.

B.

IN-MODELING THE FUEL ASSEMBLY-RACK CELL GAP WIDTH, THE GAP SHOULD BE MAXIMIZED BY INCLUDING TOLERANCES.

C.

DEMONSTRATE THAT THE ANALYSES ENVELOPE DIFFERENT HYDRODYNAMIC MASS AND GAP SIZE CONDITIONS.

9.

ADDRESS ANALYSES UNCERTAINTIES TO VERIFY THE RACK MODEL DYNAMIC CHARACTERISTICS.

10.

IF VERTICAL ACCELERATION EXCEEDS 1G, INCLUDE THE IMPACT EFFECTS IN THE FUEL CELL ANALYSES.

11.

INCLUDE AN ADEQUATE RANGE OF FUEL ASSEMBLY STIFFNESS (INCLUDING IMPACT STIFFNESS) TO ENCOMPASS CURRENT AND FUTURE FUEL.

0564n

IV.

SUMMARY

0 2/1/89 -

SUBMITTAL OF PROPOSED LICENSE AMENDMENT PROVIDE COMPLETE RERACKING ANALYSES AND LICENSE AMENDMENT REQUEST 0

3/30/89 -

BEGIN RACK FABRICATION 0

8/1/89 -

NRC ISSUE LICENSE AMENDMENT

ENCLOSURE 3 SPENT FUEL POOL RERACKING SAN ONOFRE UNITS 2 AND 3 December 7, 1988 Issues to be Addressed in the License Amendment Request

1. Structural and Effective Structural Properties.

A. Analysis method and calculation to determine the structural properties of the cell-to-cell weld shear connection for the structural model.

B. Analysis method and calculation to determine the effective rotational stiffness properties of the cell-to-cell connections for the effective structural model.

C. Analysis method and calculation to determine the effective rotational stiffness properties of the fuel rack base for the effective structural model.

D. The basis for the use of rigid beams in the base of the nonlinear model.

"Rigid base plate"

2. Hydrodynamic Mass.

A. Details of the hydrodynamic mass calculation.

B. Justification of the hydrodynamic mass simulation in the N-S direction (4 rack configuration).

Maximum support pad lift-off and margin agairst overturn.

4. Uncertainties and conservatisms.

5. WECAN Code.

A.

Information on method and verification solutions on the nonlinear model superposition method. Justify its validity in case of multiple non-linearities.

B. List of licensees where WECAN was reviewed by NRC.

6.

Engineering explanation of the relationship between the values of rack relative displacements for the N-S and E-W directions. Why does N-S exceed E-W?

7.

Reference test data which may be used to substantiate rack parameters.

ENCLOSURF 3

8. Stresses in rack components.

9. Interface loads and effects on pool.

10.

Confirm earthquake time history inputs are compatible with FSAR.

11.

Rack-to-rack and rack-to-wall gap adequacy, including installation tolerances

12.

Walkdown requirements after a seismic event.

TDM:C33n