ML13336A114
| ML13336A114 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/08/1988 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8809300161 | |
| Download: ML13336A114 (24) | |
Text
September 8, 1988 Docket No.:
50-206 FACILITY:
San Onofre Nuclear Generating Station, Unit 1 LICENSEE:
Southern California Edison Company
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 12, 1988 RE: TRANSSHIPMENT OF SPENT FUEL FROM UNIT 1 On August 12, 1988, the NRC staff met with representatives of Southern California Edison Company (SCE) to discuss the proposed transshipment of spent fuel from Unit 1 to Units 2 and 3. Attendees are identified in Enclosure 1. Enclosure 2 contains the viewgraphs presented at the meeting. The meeting was held pursuant to notice issued on August 1, 1988.
The meeting was centered on the additional information SCE provided in its letter of June 10, 1988. At the conclusion of the meeting, SCE committed to respond in writing to the questions the staff prepared (Enclosure 3).
In addition, the staff is awaiting additional information as follows:
- 1. Loads on walls and resulting stresses vs. allowables (FSAR) (to include consideration of a diagonal cask tip in the direction of the spent fuel storage racks).
- 2. Loads on the basemat and resulting stresses vs. allowables (FSAR).
- 3. Plans for repair of the leaking liner.
- 4. Resolution of 5-year load test on special lifting devices (load test vs.
NDE).
original signed by Charles M. Trammell Project Directorate V Division of Reactor projects -
III IV, V and Special Projects
Enclosures:
DISTRIBUTION
- 1. Attendees Docket File NRC Participants
- 2. Viewgraphs PDV Reading ACRS (10)
- 3. NRC Staff Questions CMTrammell MJohnson (Region V)
NRC & Local PDRs cc: w/enclosures MVirgilio See next page OGC-WF EJordan BGrimes D
DV r mmell:jn
/88 OFFICIAL RECORD COPY PDR AD~clCP PDC-
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 8, 1988 Docket No.:
50-206 FACILITY:
San Onofre Nuclear Generating Station, Unit 1 LICENSEE:
Southern California Edison Company
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 12, 1988 RE: TRANSSHIPMENT OF SPENT FUEL FROM UNIT 1 On August 12, 1988, the NRC staff met with representatives of Southern California Edison Company (SCE) to discuss the proposed transshipment of spent fuel from Unit 1 to Units 2 and 3. Attendees are identified in Enclosure 1. Enclosure 2 contains the viewgraphs presented at the meeting. The meeting was held pursuant to notice issued on August 1, 1988.
The meeting was centered on the additional information SCE provided in its letter of June 10, 1988. At the conclusion of the meeting, SCE committed to respond in writing to the questions the staff prepared (Enclosure 3).
In addition, the staff is awaiting additional information as follows:
- 1. Loads on walls and resulting stresses vs. allowables (FSAR) (to include consideration of a diagonal cask tip in the direction of the spent fuel storage racks).
- 2. Loads on the basemat and resulting stresses vs. allowables (FSAR).
- 3. Plans for repair of the leaking liner.
- 4. Resolution of 5-year load test on special lifting devices (load test vs.
NDE).
Charles M. Trammnell Project Directorate V Division of Reactor projects - III IV, V and Special Projects cc: w/enclosures See next page
Enclosures:
- 1. Attendees
- 2. Viewgraphs
- 3. NRC Staff Questions
Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Jack McGurk, Acting 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. Robert G. Lacy Manager, Nuclear San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS 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 1600 Pacific Highway Room 335 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, Suite 210 Walnut Creek, California 94596
ENCLOSURE 1 ATTENDANCE LIST AUGUST 12, 1988 NRC SCE D. Hickman T. Yee N. Wagner A. Llorens G. Knighton J. Rainsberry H. Ashar F. Rinaldi OTHERS S. Sharron -
Bechtel R. Erickson -
San Diego Gas & Electric
ENCLOSURE 2 NRC MEETING SPENT FUEL TRANSSHIPMENT SAN ONOFRE UNIT 1
LGENDA 0
PAST METHOD OF SPENT FUEL SHIPMENT 0
PROPOSED METHOD OF TRANSSHIPMENT 0
STRUCTURAL CONSIDERATIONS
PAST METHOD OF SPENT FUEL SHIPMENT 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 ONOFRE NUCLEAR GENERATING STATION UNIT 1 TAKE OFF CONTROL TOWER AND ADMINISTRATION HEATER DECK MIN EL. 35'6"TRNS DE OWR TURBINE GANTM -
TowAER CRANE POSITION 2 TURBINE GANTRY CRANE POS N POSITION I
CRANE RAIL IUHBINE PEDESTAL O
fEL 42-0 NORTH lURBINE SOUTH IUREIINE DECK EXTENSION GENERATOR DECK EXTENSION EL. 42-0TION EL. 42'-"
DECONTAMINA110 N
,HEATER DECK CONDENSATE SPU1 NAD EL. 2-0 0(TOAG)AX FUEL TANK TASF SPENT STORAGE 0c FUEL
(
0 STORAGEO 4
(lI D RAILROAD SPUR RACKS FUE 0
,PLANT NORTH FUEL STORAGE BUILDING PLAN VIEW
COLLAR RESTRAINT RODS SHEAR RING RESTRAINT'RODS BASE SHEAR RING 82 AIR PALLET TIE DOWN GEAR
PROPOSED METHOD OF TRANSSHIPMENT A.
TURBINE GANTRY CRANE LIFTS EMPTY CASK FROM TRAILER B.
THE CASK IS PLACED ON THE WEST A-FRAME HORIZONTAL BEAM AND RESTRAINED C.
TURBINE GANTRY CRANE TRANSFERS THE CASK ALONG THE TURBINE DECK TO THE DECONTAMINATION PAD D.
THE IMPACT LIMITER IS MOVED INTO PLACE E.
TURBINE GANTRY CRANE PLACES THE EMPTY CASK ON THE DECON PAD IN CONJUNCTION WITH THE IMPACT LIMITER F.
TURBINE GANTRY CRANE PLACES CASK IN THE CASK HANDLING AREA OF THE SPENT FUEL POOL G.
TURBINE GANTRY CRANE PLACES LOADED CASK ONTO THE WEST A-FRAME LEG IN CONJUNCTION WITH THE IMPACT LIMITER H.
TURBINE GANTRY CRANE TRANSFERS THE LOADED CASK To THE SOUTH END OF THE TURBINE BUILDING
poo~o a
1 OI iww Da}
lcif ewwR
SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 SETIO VIE
- 0.
L emnL aae W,
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SECTION VIEW
TURBINE GANTRY CRANE SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 RAW 3
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TURBINE GANTRY CRANE WITH CASK IAI~
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/OT~T-PDRP1EGT Pk~A FSt IEW
FUEL STORGE BUILDING cwMONV Tu9?iAP tECK XTAov vI Z q4
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xs=UNIT TWO UNIT TM2El
.NIT ONE r
O4 oo ao PPOTECTED APEA
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STRUCTURAL CONSIDERATIONS I. TURBINE GANTRY CRANE MODIFICATIONS A.
CASK SUPPORT ON THE WEST CRANE LEG BEAM B.
SPENT FUEL CASK RESTRAINTS DURING CRANE MOVEMENT ALONG THE TURBINE DECK II.
DECONTAMINATION PAD AREA A.
USE OF IMPACT LIMITER DURING TRANSFER OF CASK FROM CRANE To DECON PAD (VICE VERSA)
III. CASK AREA OF THE SPENT FUEL POOL A.
STAINLESS STEEL PLATE ON THE FLOOR OF THE CASK AREA IN THE SPENT FUEL POOL
CASK SUPPORT ON CRANE LEG 5Z 44,eV~A'~
3 N3-7 T -EX/ITAA CRAN/E 9HEAq~ LF&62
C.ASK -:EX 8PRNT -FUEL POOL. UNIT 1 CAKLMYDOWN AREA 5P'ENT FUEL POOL
[Low.
Pt\\~TIAL PLAN4
CABLE-RESTRAINT FOR CASK PRWIDE7~ 2Zi9A/P5YT rLL 54FiJ v4O0-KI"A6 LO9 TJ
7Yc07 E4 E-
CASK 89UPPORT ON CRANELE
-V~
7'/1 1D.0 6091 S.
IbM 4 1EWv
SONGS 1 Spent Fuel Transshipment ESGB Questions Regarding SCE's June 10, 1988 Submittal
- 1. The plan view (Figure 1) needs to be supplemented by one or more vertical sections through the Decontaimination Pad, Cask Laydown Area, Upender Area, Spent Fuel Pool and New Fuel Area, and the Turbine Deck Areas.
- 2. You identify a Category B seismic event and a 0.67g seismic event.
Define these events.
- 3. Discuss the basis for the selection of the 10'- 6" and 2'-8" heights for the postulated cask drop without the impact limiter.
The 2' - B" is close to the 2' - 3" cask lift height identified in your response to question 6.
Please clarify your assumptions. Also, expand your explanation of the values of 0.09" and 1.92" on page 3.
- 4. In your response to Questions 6 and 7 you address the potential impacts of the cask on the walls and components within the Decontamination Area and Spent Pool walls, as result of the postulated cask tipping after a 4',
2', 3', and 42 -7", height cask drops. Please address the bases for the various selected drop heights and provide results that Include forces and reactions related to the various postulated impacts and the respective stress levels as related to FSAR allowables.
- 5. Figure 4 shows a 3-D view of the impact limiter. However, it doesn't convey dimensional values of the limiter. Additional information is needed to fully describe the impact limiter and the various cask impact scenarios identified in your previous responses. Also, in the second paragraph of item 2 for the response to Question 6 you state conclusions with respect to portions of a postulated damaged wall falling in the new fuel areas. However, you do not provide analytical results supporting your conclusion that the new fuel racks will not be affected.
- 6. Your responses to Question 7 and 10 address the postulated cask drop in the spent fuel pool. More information with regard to the details of this analysis are required to allow the staff to reach the same conclusions.
This information should include: material properties, modeling, computational models, analysis procedures and results for the evaluation of the pool walls, slab, and liners. Also, you should address the drop orientations considered and the controlling drop orientation.
- 7.
In your response to Question 12 you describe the requirements for the turbine deck load bearing test. The loads address the previous mode of fuel movement (air pallet). State why the new load should not be the 105 tons resulting from the new load (70-Tons) increased by the dynamic factor.
-2 8:
In your response to Questions 9 and 10 you address several staff concerns. We request the following clarifications:
State the criteria that established the value of the 100 ton load used on the analysis of the gantry crane The seismic accelerations considered for Seismic Category B loads (0.13g and 0.2g) are considerably different then'the 0.67 g identified in your response to Question 5. Address these differences.
0 The 20 kips load on the crane identified in Item (c) fails to state if its direction was considered. Also, the rope capacity in item (e) is identified as 9 tons while the load on the crane is established as 20 kips. Discuss these staff concerns.
o Your response to Question 10 describes the structural components of the sliding roof. State if it is considered as a Seismic Category I structure and if it has been designed for the related FSAR requirements.
- 9. Your response to Question 17 identifies the daily discharge, from the wells for the leak chase system of the spent fuel pool, as 10 gallons perday.
From these results it appears that the liner is not providing adequate leakage protection. Describe your plans for repair of the liner.
- 10. Your responses provided in your submittal dated June 10, 1988, reworded some of the original questions provided by the staff. Although they include most of the requested information, they appear to have missed our Question 12 which said State if you plan to provide a technical specification equivalient to Item 4.13, Attachment 1, for the proposed transport mode." Please address this staff request.