ML13336A038
| ML13336A038 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 10/01/1987 |
| From: | Bradfute J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8710080242 | |
| Download: ML13336A038 (21) | |
Text
OCT 1 1987 Docket No.:
50-206 LICENSEE: Southern California Edison Company FACILITY: San Onofre 1 SUBJECT
SUMMARY
OF MEETING HELD SEPTEMBER 25, 1987 REGARDING THE RELOCATION OF SPENT FUEL FROM SAN ONOFRE, UNIT 1 TO UNITS 2 AND 3 In the afternoon of 25 September 1987, representatives of Southern California Edison Company (SCE) met with members of the NRC staff to present and discuss their general concepts regarding the transport of spent fuel from the fuel storage pool at Unit 1 to the pools at Units 2 and 3.
The meeting was held in Room 110 of the Phillips Building in Bethesda. is the list of attendees.
Jack Rainsberry of SCE presented a description of the equipment and procedures used in the past for moving spent fuel from the spent fuel pool at Unit 1 to the railroad loading area. The procedure involved moving one assembly at a time in a small shipping cask set vertically on an air supported device (like a hovercraft) that moved on a concrete pad, propelled by a motor driven donkey engine and guided by a rail set into the concrete.
The device preforms well for the movement of small quantities of fuel but will be too slow for the movement of large numbers of fuel assemblies as is planned during the reload outage scheduled for June of 1988. The Unit 1 pool is nearly full and its capacity is insufficient for the fuel that will be removed from the reactor next June. SCE's desire is to use a larger shipping cask that will hold a minimum of seven assemblies and be transported by a gantry crane-from which it will be supported and to which it will be attached for increased stability during transit. Enclosure 2 is a copy of their presentation viewgraphs.
Units 2 and 3 are already licensed to store fuel from Unit 1 but the procedures for moving and handling fuel have not yet been approved by the NRC. Some safety related equipment and cables will be put in jeopardy during portions of the transport operation.
71000242 371001 PDR ADOCK 05000206
<P PDRL9
-2 On the surface, SCE's proposed facilities, equipment and procedures appeared to be appropriate and adequate, however, the licensee was encouraged to submit for staff approval a formal request to amend their license.
Subsequent to the actual meeting, the staff developed the position that, because a postulated drop of the cask can endanger safety related equipment, the licensee should commit to cask movement only in the cold shutdown/
refueling modes unless a strong argument can be made to justify cask movement during operation at power.
doiI signed by John 0. Bradfute, Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosures:
As stated cc:
See next page DISTRIBUTION Docket File NRC & Local PDRs PD#5 Reading GKnighton JBradfute OGC-Bethesda JLee Edordan JPartlow NRC Participants ACRS (10)
TOMartin-EDO MRJohnson-EDO R/P 4
D DV JBradfute:cd G
t on 9//87 0/8/ /87
Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Joseph 0. Ward, Chief General Counsel Radiological Health Branch James Beoletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105, San Francisco, California 94111 Encinitas, California 92024 Mr. Stephen B. Allman Dennis M. Smith, Chief San Diego Gas & Electric Company Radiological Programs Division P. 0. Box 1831 Governor's Office of Emergency Svcs.
San Diego, California 92112 State of California 2800 Meadowview Road Sacramento, CA 95832 Resident Inspector/San Onofre NPS c/o U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 -
9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane Walnut Creek, California 94596
ENCLOSURE 1 Jo k, g5&
adA4
.J~.
er/wi's/
IafcR soJ A
,-W t
S. tj e7z V4 r'.
/-/-
q
/2,49 - 7331 RREY G~~C_.E
/C-(\\
0-e Scr /os s (7/4/)
3&
2 loty LtorrS/Lcse (e t S) 30z,6 71 V~
ENCLOSURE 2 NRC MEETING SPENT FUEL TRANSSHIPMENT SAN ONOFRE UNIT 1 SEPTEMBER 25, 1987
AGENDA 0
REASON FOR TRANSSHIPMENT 0
PAST METHOD OF SPENT FUEL SHIPMENT 0
PROPOSED METHOD OF TRANSSHIPMENT 0
STRUCTURAL CONSIDERATIONS 0
DISCUSSION
REASON FOR TRANSSHIPMENT I.
FUTURE OPERATIONS A.
SPENT FUEL BUILDING STORES 216 ASSEMBLIES B.
68 SPACES ARE CURRENTLY AVAILABLE C.
52 SPACES REQUIRED FOR CYCLE X REFUELING D.
CAN ONLY OPERATE UNTIL CYCLE XI REFUELING OUTAGE E.
OPERATING LICENSE VALID THROUGH 2004 II.
IN SERVICE INSPECTION OF REACTOR VESSEL A.
WILL OCCUR DURING CYCLE XI REFUELING OUTAGE (1990)
B.
REQUIRES FULL CORE OFFLOAD (157 ASSEMBLIES)
C.
16 SPACES WILL BE AVAILABLE III. UNITS 2/3 LICENSED TO ACCEPT UNIT 1 FUEL
PAST METHOD OF SPENT FUEL SHIPMENT I.
BACKGROUND A.
NRC REQUEST FOR INFORMATION REGARDING CASK DROPS (MARCH 6, 1974)
B.
SCE DEVELOPED METHOD FOR CASK SHIPMENT USING AN AIR PALLET SYSTEM (MARCH 21, 1975)
C. MODIFICATIONS TO SOME TURBINE DECK STRUCTURAL MEMBERS AND A LOAD BEARING TEST IDENTIFIED D.
NRC APPROVED MODIFICATIONS, LOAD BEARING TEST AND METHOD OF CASK SHIPMENT (JANUARY 15, 1976)
PAST METHOD OF SPENT FUEL SHIPMENT II. METHOD A.
TURBINE GANTRY CRANE LIFTS EMPTY CASK ONTO AIR PALLET B.
TURBINE GANTRY CRANE LIFTS EMPTY CASK AND AIR PALLET ONTO TURBINE DECK C. AIR PALLET TRANSFERS EMPTY CASK ALONG WEST SIDE OF TURBINE DECK TO DECONTAMINATION PAD D.
TURBINE GANTRY CRANE PLACES CASK IN SPENT FUEL CASK HANDLING AREA E.
TURBINE GANTRY CRANE PLACES LOADED CASK ONTO AIR PALLET F.
AIR PALLET TRANSFERS LOADED CASK ALONG WEST SIDE OF TURBINE DECK TO THE SOUTH END G. TURBINE GANTRY CRANE REMOVES LOADED CASK AND AIR PALLET FROM THE TURBINE DECK
SAN NOFE NUCLEAR GENERATING STATION UNIT I TAKE-OFF TOWER CONTROL AND ADMINISTRATION
)
HEATER DECK MAIN EL. 35-6*TAS D. E.
TOWER IE B AUX.
AUX.[]E3 TURBINE GANT TRANSF TRANSFf CRANE (E31 6B POSITION 2 TURBINE GANTRY CRANE PO 2 POSITION I
CRANE RAIL TURBINE PEDESTAL O
EL.42-0"r NORTH TURBINE SOUTH TURBINE DECK EXTENSION GENERATOR DECK EXTENSION 8
EL. 42'-0" EL. 42-0 DECONTAMINATION PAD EL.42-O CONDNSAT SPARE SPUR NEATER DECK CNEST NWEL.
3LS 0
TANAUX FUEL TRNSF SPENT STORAGE 0
FUEL STORAGE 0
RACKS PLANT NORTH FUEL STORAGE BUILDING PLAN VIEW
PROPOSED METHOD OF TRANSSHIPMENT I.
TRANSPORT CASK II. CASK HANDLING CONTROLS III PROPOSED METHOD OF TRANSSHIPMENT
NEUTRON SHIELD LOWER CAVITY EXPANSION TANKS VALVE BOX NEUTRON SHIELD UALVE BOXES STAINLESS STEEL INNER SHELL NEUTRON SHIELD EXPANSION TANKS UPPER CAVITY VALVE BOX CORRUGATED STAINLESS STEEL OUTER SHIELDING JACKET URANIUM SHIELDING REMOVABLE FUEL8BASKET NEUTRON SHIELD (FLUID ANNULUS)
STAINLESS STEEL OUTER SHELL CASK IMPACT FINS CLOSURE HEAD IF-300 Irradiated Fuel Shipping Cask 7
-57
PROPOSED METHOD OF TRANSSHIPMENT CASK HANDLING CONTROLS I.
CRANE AND RIGGING CERTIFICATION A.
NON-DESTRUCTIVE TESTING B.
LIFT TESTS II.
HEAVY LOADS LIFT PATH A.
SPECIFIC LOAD PATH B.
PERSON WITH PROCEDURE IN HAND C.
PREREQUISITE VISUAL EXAMINATION AND OPERATIONS CHECK III.
SUPERVISION
-L zz 0
0 go
00 00 Li'i C~C) 10l is o__
0c
QW.C MAL I AMU NEW nlvL MARN
=3
$"Apr-,
MxR M-1.
apemima RAL r
40i amm rim
%4zost" OPM CAM LAYDOGN 403 na MONDOW AKA 401 N.
naL N.
N.
407 V
oil Pam ng
.... k."NN N.
ClEA IRAMSMR OLCM now CAKAL PAMM JL-l X.
CNN=
409 N.
OWT CANA OW *QWT cumcl MY CLM 404 putsomm a GAFMINT n
AMU momrmR COWAN=.
SM. FOOMAIM ORMODWY 409 now ooffAAMATM 1
411 IOMOL M
LAYDOW um FPMNQER ARLA
-Lllu X-212 putsoma muw d=
VECTIM" CLEM am" 4W U"
STMAM CONTAINMEN BUILDING FN-U2C4LD27 I DRAWN BY-RAY.
UIM-2 FUEL HANDIMIG BIM ING REVISION 0 DATE, 07/16/86 cZ CHANGE, FGZ STATUS-07/06/87 FIDOR PLAN ELEV (63' MJTA9E GEMENT DIVIS113N MY FU I cn" co~
STRUCTURAL CONSIDERATIONS I.
QUALIFICATION OF THE TURBINE BUILDING STRUCTURE A.
TURBINE BUILDING UPGRADED FOR 0.67G MODIFIED HOUSNER SEISMIC EVENT AND CONSIDERED CRANE NORTH AND SOUTH B.
NORTH EXTENSION STRUCTURE QUALIFIED FOR THE GANTRY CRANE LOCATED ON THE NORTH EXTENSION WITH A 10 TON LOAD DURING PLANT OUTAGES C. TURBINE BUILDING (SOUTH OF COLUMN LINE D) QUALIFIED FOR THE GANTRY CRANE WITH A 35 TON LOAD DURING PLANT OPERATION D.
OCCASIONAL TURBINE GANTRY CRANE USAGE FOR LOAD LIFTS UP TO 100 TONS IS ALLOWED UP TO AN OVERALL ANNUAL USAGE OF 1%
A-T1F1D JO 00 7IAJ5
STRUCTURAL CONSIDERATIONS II.
TURBINE GANTRY CRANE MODIFICATION A.
CASK SUPPORT ON THE WEST CRANE LEG BEAM B.
SPENT FUEL CASK RESTRAINTS DURING CRANE MOVEMENT ALONG THE TURBINE DECK III. CASK AREA OF THE SPENT FUEL POOL A.
STAINLESS STEEL PLATE ON THE FLOOR OF THE CASK AREA IN THE SPENT FUEL POOL
CIO LaiU Lai 29U
cam CP.,
=
Cc)
CASK RfSTRANT PLJATFO~ivA
\\T CSK PROPOSED CASK PLATFORM ON SHEAR LEG