ML20035B049
| ML20035B049 | |
| Person / Time | |
|---|---|
| Site: | 07109256 |
| Issue date: | 03/30/1993 |
| From: | Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9303310042 | |
| Download: ML20035B049 (28) | |
Text
IMTB:NLO DE 2' 71-9256 MEMORANDUM FOR:
The Files FROM:
Nancy L. Osgood, IMTB, IMNS, NMSS
SUBJECT:
MEETING
SUMMARY
REGARDING TRANSPORT OF YANKEE-ROWE STEAM GENERATORS Attendees i
NRC Yankee Atomic Chem-Nuclear Marissa Bailey Nancy Osgood Jane Grant Mirza I. Baig Ross Chappell Jack Parrott Pete Hollenbeck Curt Lindner Mort Fairtile Bernie White Bruce Holmgren Patrick L. Paquin Henry Lee Carl Withee Nancy Osgood Li Yang Introduction i
A meeting was held on March 3,1993, in Rockville, Maryland, at the request of Yankee Atomic Electric Company. The meeting was held to discuss the transport of the steam generators from the Yankee-Rowe plant, which is being decommissioned. The components will be shipped to Barnwell for disposal.
l Discussion The discussion centered on the attached meeting handouts.
The detailed transport plans are currently being developed by Chem-Nuclear and Yankee.
It was agreed to have a future meeting to discuss in detail the transport plans, including intermodal transfers and evaluation of the route.
l Yankee plans to submit an application for package approval on April 5,1993.
Or?:ici Siped By Nancy L. Osgood Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS Attachments: Meeting handouts (2)
DISTRIBUTION With Attachments:
NRC PDR NRC File Center CEMacDonald Without Attachments: NMSS r/f IMTB r/f Attendees Meeting Notebook OFC IMTBl#9 C
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NAME NL0sgood "CRChappell DATE 3 / M /93
'4 / 9 /93 i
C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY 4 ;
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TRANSPORTATION PLAN OVERVIEW SHIPMENT WILL COMPLY WITH 10 CFR 71.52 REQUIREMENTS FOR t
. EXCLUSIVE USE TYPE B QUANTITIES OF LSA MATERIALS.
I STEAM GENERATORS (SG's) WILL BE INJECTED WITH LOW DENSITY l
CONCRETE AND ADDITIONALSHIELDING ATTACHED AS REQUIREDTO MEET 10 CFR 71.47.
LOCKWOOD BROTHERS WILL COORDINATE (WITH YAEC OVERSIGHT)
ALL STEAM GENERATOR MOVEMENT ACTIVITIES FROM YNPS TO BARNWELL.
i ANTICIPATED MODES OF TRANSPORT:
TRUCK / TRAILER:-
LDCKWOOD TEN-FOOT WIDE DOUBLE GOOSENECK TRAILER RAILCAR:
BOSTON
& MAINE (B
M)
EIGHT AXLE FLATCAR ws 4 m
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ANTICIPATED TRANSPORT ACTIVITIES STEP 1 -
S/G SECURED TO LOCKWOOD TRAILER VIA TIEDOWN STRUCTURES AND TRUCKED TO B & M RAll LINE.
STEP 2 -
CONVEYANCE CHANGE:
TRAILER POSITIONED OVER RAILS SG,-
.WITH TIEDOWNS ATTACHED TO SG, HYDRAULICALLY JACKED TO CLEAR TRAILER (4
JACKS AT TIEDOWNS
-WITH CRIBBING SYSTEMATICALLY ADDED TO SUPPORT LOAD AS SG IS RAISED, REFER TO FIGURE 1)
TRAILER ' REPLACED. BY FLATCAR SG. HYDRAULICALLY LOWERED ONTO FLATCAR -
(SYSTEMATICALLY REMOVING CRIBBING 'AS SG IS LOWERED)-
SG SECURED TO FLATCAR VIA TIEDOWN STRUCTURES.
i L
ANTICIPATED TRANSPORT ACTIVITIES (continued)
STEP 3 -
SG RAILED TO CNSI'S DEFENSE CONSOLIDATION l
FACILITY (DCF) IN BARNWELL, S.C.
i STEP 4 -
CONVEYANCE CHANGE:
SG, WITH TIEDOWNS ATTACHED
- TO SG, HYDRAULICALLY JACKED TO CLEAR FLATCAR l
(4 JACKS AT TIEDOWNS:
WITH CRIBBING SYSTEMATICALLY ADDED TO SUPPORT LOAD AS SG IS RAISED)
FLATCAR REPLACED BY LOCKWOOD TRAILER SG. HYDRAULICALLY LOWERED ONTO TRAILER (SYSTEMATICALLY REMOVING CRIBBING AS SG IS LOWERED)-
SG SECURED TO TRAILER VIA TIEDOWN STRUCTURES.
STEP 5 -
SG TRUCKED TO BARNWELL LOW-LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY.
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TYPICAL JACKING / CRIBBING ARRANGEMENT l
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4 TIEDOWN REQUIREMENTS AND REGULATIONS TRUCK RAll BARGE lAEA Places responelbility onto the carrier.
Revilree that cask function not be Impaired if attachment points on the cask fell 10CFR71.4 5 Does not specify tiedown requiremente, but does longitudinal 10g NRC regulate the cask attachment pointe.
lateral 5
These load erlierte are almulteneously applied to the cask esater-et-gravity (e.g.) without materlet yleiding.
49CFR393.102 4sCFR174 1.53 appNed to cook e.g.
No specific requirement.
- laworst erlentetten Must be secured to prevent without reaching,tledown
. cargo movement during static breaking strength normal operating conditione Rule 88 Without yielding any meterial, the loading le applied almultaneously I
AAR n/a n/a longitudinal 7.5 g lateral 1.8 g vertical 4.0 g 1414.2 (Draft)
Applied N 14.24 Applied to cook c.g.
to cook conter-of-gravity collielon head beam evepenelon longitudinal 11.5g 11.4 g spring ele lateral
!0.5 g 11.6 g ANSI longitudinet. 12.3 g 11.8g vertical dynernie -
12.0g 22.0 g lateral 1.6 g 1.19 static 1.09 1.0g
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% DOT establishes baseline requirements
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ESTIMATED WElGHTS i
Dry Weight of the Steam Generator 187,200 lbs
=
Weight of the Concrete 27,300 lbs
=
Plugged Tubes, Crud, Misc.
5,500 lbs
=
Weight of the Grouted S.G.
220,000 lbs
=
Shielding Weight 50,000 lbs
=
Tie-Down & Misc.
30,000 lbs
=-
Gross Weight
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300,000 lbs t
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STEAM GENERATOR Shipping
& Handling Conditions The steam generator is handled and. shipped in a controlled j
u environment.
m Proper tie-down to the truck-trailer / rail-car / barge will ensure that l
3 the steam generator will not detach from the carner.
4 a
Based on the geometry of the steam generator (long and slender)-
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and the size of the carrier (totally encompassing the SG), the only possible' orientation for a 1-foot drop is on its side.
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m All the surfaces that the SG could impact during 1-foot drop are yielding (gravel road, pavement etc.).
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STEAM GENERATOR 1-Foot Drop Analysis a
The shipping and handling conditions of the Yankee Atomic Steam Generators are similar to the Millstone Steam Generators.
Because of the Shipping and Handling Conditions described earher, a
the only orientation for 1-foot drop is on the side of the steam t
generator.
u Per Reg. Guide 7.6 the stress allowables during the normal conditions are based on the material remaining elastic.
The preliminary analyses show that the steam generator can withstand a 1-foot drop on its side with only minor deformations.
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AGENDA FOR MEETING BETWEEN y
YANKEE ATOMIC ELECTRIC COMPANY i
AND
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NUCLEAR REGULATORY COMMISSION l
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MARCII 3,1993 i
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INTRODUCTION l
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STEAM GENERATOR CIIARACTERIZATION l
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TRANSPORTATION PLAN OVERVIEW i
STEAM GENERATOR TIE-DOWN CRITERIA w
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j-l REGULATORY DROP ANALYSIS-s
SUMMARY
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- MEETING OBJECTIVES i
t INFORM NRC OF YAEC PLANS 1.
I-SOLICIT INPUT j
ESTABLISH LINES OF COMMUNICATION ESTABLISH SCHEDULE t
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- 4 T
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ROWE, MASSACHUSETFS 185 MW PWR
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32 YEARS OF OPERATION 4
PERMANENTLY SHUTDOWN - FEBRUARY 1992 DECOMMISSIONING PLAN - OCTOBER 1993 PRESENTLY ENGINEERING FOR REMOVAL OF SELECTED COMPONENTS l
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i COMPONENT REMOVAL NOW e
i SAVINGS TO CONSUMERS j
FUTURE AVAILABILITY OF DISPOSAL SITES U~NCERTAIN R
COST OF LLW DISPOSAL NOT LIKELY TO GO DOWN 4
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ELIMINATES 90% OF ACTIVITY FROM CONTAINMENT 0
ELIMINATES UNNECESSARY SYSTEMS a
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WHAT ARE WE SHIPPING ?
t 4 STEAM GENERATORS
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PRESSURIZER REACTOR INTERNALS WHAT REQUIRES 10CFR71 CERTIFICATE OF COMPLIANCE?
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- (REACTOR INTERNALS WILL BE SHIPPED BY CN 3-55 CASKS)
- (PRESSURIZER IS BELOW A2 CRITERIA) 1 i
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l LESSONS' LEARNED FROM MILLSTONE II i
SIMILARITIES i
CONTRACTORS-CHEM-NUCLEAR 4
LOCKWOOD BROTHERS CONCRETE INJECTION OF SG's i
POSSIBLE BARGE SHIPMENTS UTILIZE DESIGN CHANGE (50.59) PROCESS FOR REMOVAL l
l DIFFERENCES l
YNPS STEAM GENERATORS ARE ONE QUARTER SIZE OF MILLSTONES's i
REMOVAL ONLY - NO REPLACEMENT i
CRITICAL PATH IS DISPOSAL SITE CLOSURE SCHEDULE i
r PROJECT SCHEDULE i
i SG C OF C APPLICATION / SAR WILL BE SUBMITTED TO a
NRC BY APRIL 5 i
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REQUEST NRC CONCURRENCE AND ISSUANCE OF C OF C l
IN EARLY JULY 1993 0-YAEC PREPARED TO SUPPORT AGGRESSIVE SCHEDULE F
FOR RESPONDING TO.NRC QUESTIONS 1.
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4 COMPONENT REVIOVAL :?ROGRAM 1993 1994 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dee Jan Feb Mar Apr May Jun Jul PLANNING & ENGINEERING we sdpea'cl spce 4 e eg'deyne se
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s ASBESTOS REMOVAL Ige p ce gj SUPPORT SYSTEM &
STRUCTURE CHANGES lege'nessw&Was'qm Me wge <Mt LOAD TEST
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. SAR Development IM wpm M M the4RH M M P** st SUBMfT SAR NRC APPROVE
- ^"
Remove SG & PZR SG & PZR REMOVAL
- de 'e*$ t*
idCUT id SG LAST SG REMOVAREMOVAL Prep SG & PZR for Shipment in seg*m+ raga ne ' ' gaugl Ship SG & PZR Iwer*i@2MfateeDmte s 1 SHJT.1ENT l # 2 SHIPMENT -
TO BARNWELL TO BARNWELL Tooting Design.
Fabrication and Test in Mt'ne me5%einw#sx
"+$S E P 'M al RPV INTER.NALS Segment internais REMOVAL
- gme "**** " *M BARNwEtt c^vi" i
CLOSURE-Load and Ship Casks c
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STFAM GENERATORS PHYSICAL DESCRIPTION OVERALL LENGTH - 40'-3" i
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STEAM DRUM DIAMETER - 8'-6" MAIN SHELL DIAMETER - 7'-1" DRY WEIGHT - 187,200 LBS i
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FLOODED WEIGHT - 268,110 LBS 1
VOLUME (PRIMARY +~ SECONDARY) - 1300 CUBIC FEET i
DESIGN CODE - ASME VIII,1956 i
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SHELL MATERIAL - ASTM A212 GRADE B 1620 U-TUBES WITH 5 SPACERS i
334 TUBES PLUGGED (APPROX. 5%)
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N WATER REMOVED IN j S EPARAT OR t g. TUDE ,g SUPPORT l \\ 4 ? WATER ENTER! y i HE ATING S [ a f i BOILING SECT N g UQUtcLEVELSdlCATORm s, ( [ i j e j /- f (
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i . BLDWDOWN 4-p f . TUDE PLATE VENT-- b._ - = ytyy .Y. y i n b h$bkh e o 1 r e t k\\ \\ i 1 l'RIMARY OUTLET .7, .-7 T I i 6
l TRANSPORTATION PLAN OVERVIEW i l .] TRANSPORT METHODS l ~ t l 4 .,_m.,....,...._.._ ROADWAY FROM PLANT TO HOOSAC TUNNEL f HOOSAC TUNNEL TO BARNWELL, SOUTH CAROLINA l i OR i HOOSAC TUNNEL TO BARGE FACILTIY TO BARNWELL ; l l
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^ ~ I l 1 YANKEE STEAM GENERATOR AND PRESSURIZER i REMOVAL AND DISPOSAL STRATEGY i EVALUATE AND DEVELOP DISPOSA. PIAN WITH i j CHEM NUCLEAR i EVALUATE SHIPPING AND DISPOSAL OPTIONS 3 (SHIPPING AS SINGLE PIECE) I EVALUATE NUCLIDE DISTRIBUTIONS (CHARACTERIZE) EVALUATE - LSA OR NOT i (CLASSIFY) OBTAIN NRC CONCURRENCE (APPR. OVAL OF SAITEY ANALYSIS REPORT) i SHIP GENERATORS AND PRESSURIZER TO ? BARNWELL BEFORE JUNE 1994. ) t i i l i t i h i l y
~ WEAM GFNFRATOR CHAR AFfERIZATION NUCLIDE DISTRIBUTION - PLANT RAD PROTECTION 50/61 SMEAR RATIO PROGRAM REVIEW OF 1992 50/61 -STEAM GENERATOR i ENT. SMEAR RESULTS_. _,._ _. REVIEW OF 50/61 ~ ANALYSES OF STEAM GENERATOR CORROSION PRODUCT SAMPLES COMPARISON OF GENERATOR SAMPLES AND TENT SMEAR RESULTS (TABLE 1) i DECAY OF 1992 SMEAR RESULTS TO 7/1/93 (TABLE 2) OBTAIN CONTACT DOSE RATE MEASUREMENTS ? PRELIMINARY RESULTS - (ASSUMING USE OF LOW DENSITY ~21 lbs/R' CONCRETE) 1 FRACTION OF LSA LIMIT (~0.3) FRACTION OF A LIMIT (~95.0) 2 ACTION PLANS - SUBMIT SAFTEY ANALYSIS REPORT TO OBTAIN CERTIFICATION REMEASURE DOSE RATES AFTER CONCRETE ADDITION ADD LOCALIZED STEEL SHIELDING TO MEET 10 CFR 71.47 DOSE RATE REQUIREMENTS ? SHIP AS LSA, TYPE B QUANTITY, EXCLUSIVE USE i
TABLE 1 STEAM GENERATOR TENT SMEAR AND CRUD ACTIVITIES l ACTIVITY FRACTION OF TOTAL ACTIVITY NUCLIOE TENT SMEAR (pC1) SW2 CRUD (pC1/mg) TENT SMEAR SW2 CRUD T=1992 T-1985 T=1992 T=1985 H-3 1.34e-05 0.00 3.41e-06 C-14 3.2Ee-05 0.00 B.30e-OS FE-55 8.47e-01 2.04e+00 5.21e-01 5.20e-J1 NI-59 2.31e-03 -7.13e-03 -1.42e-03 1.62e - - - --- N1-E3 2.70e-01 3.96e-01 1.66e-01 1.01e-01 SR-89 1.40e-03 0.00 3.57e-04 SR-90 4.64e-04 0.00 1.18e-04 t PU-238 6.66e-05 3.78e-05 4.10e-05 9.63e-06 PU-239/240 1.9Be-04 1.17e-04 1.22e-04 2.98e-05 r PU-241 9.91e-03 9.30e-03 6.10e-03 2.37e-03 AM-241 1.11e-04 2.93e-05 6.83e-05 7.46e-06 CM-242 1.28e-04 5.27e-04 7.87e-05 1.34e-04 CM-243/244 1.40e-04 3.60e-05 8.61e-05 9.17e-06 CR-51 2.49e-02 1.53e-02 0.00 MN-54 5.65e-02 2.70e-02 3.48e-02 6.8Be-03 FE-59 3.05e-03 6.40e-02 2.25e-03 1.63e-02 CD-57 3 91e-04 2.41e-04 0.00 4 CD-58 5.13e-02 1.12e-01 3.16e-02 2.85e-02 C0-60 2.92e-01 5.11e-01 1.80e-01 1.30e-01 NB-94 4.46e-05 0.00 1.14e-05 ZR-95 6.57e-03 2.52e-01 4.04e-03 6.42e-02 r NB-95 1.70e-02 1.08e-02 0.00 TC-99 3.06e-05 0.00 7.84e-07 RU-103 2.72e-03 1.50e-01 1.67e-03 3.82e-02 RU-106 1.19e-02 1.10e-01 7.32e-03 2.80e-02 3 SB-124 1.29e-03 7.94e-04 0.00 -5B-125 7.10e-04 4.37e-04 0.00 CS-134 0.00 0.00 CS-137 0.00 0.00 CE-141 B.60e-04 1.11e-01 5.29e-04 2.83e-02 CE-144 2.52e-02 1.34e-01 1.55e-02 3.41e-02 TOTALS 1.0255 3.9261 1.0000 1.0000 I Not e: H-3, C-14 and TC-99 were not analyzed for in the tent sample. hb-95 was not reported in the crud sample due to the high ratio with Zr-95 (-11 to 1). ( t i
TABLE 2 GENERATOR ACTIVITY I NUCLIDE TENT SMEAR (pC1) TENT SMEAR (pCl) FilAC TOTAL T=3/3/92 T=7/1/93 T=7/1/93 FE-55 8.47e-01 6.02e-01 5.19e-01 j NI 59 2.31e-03 2.31e-03 1.99e-03 NI-63 2.70e-01 2.6Be-01 2.31e-01 i SR-89 0.00 0.00 f SR-90 0.00 0.00 ~ PU-238 6.66e-05 6.59e-05 5.68e-05 PU-239/250 1.98e-04 1.9Be-04 1.71e-04 PU-241 9.91e-03 9.30e-03 8.01e-03 AM-241 1.11e-04 1.11e-04 9.55e-05 1 CM-242 1.20e-04 1.63e-05 1.40e-05 i l CM-243/244 1.40e-04 1.36e-04 1.17e-04 CR-51 2.49e-02 1.35e-07 1.16e-07 i j MN-54 5.E5e-02 1.92e-02 1,66e-02 1 FE-59 3.65e-03 1.91e-06 1.65e-06 I CO-57 3.91e-04 1.13e-04 9.73e-05 l CD-58 5.13e-02 4.43e-04 3.82e-04 CD-60 2.92e-01 2.45e 2.11e-01 j ZR-95 6.57e-03 3.39e-05 2.92e-05 I NB-95 1.76e-02 9.0Be-05 7.83e-05 I RU-103 2.72e-03 5.35e-07 4.61e-07 i RU-106 1.19e-02 4.77e-03 4.11e-03 i 50-124 1.29e-03 4.84e-06 4.17e-06 I' SB-125 7.10e-04 5.09e-04 4.29e-04 CS-134 0.00 0.00 t \\ CS-137 0.00 0.00 I i' CE-141 8.60e-04 2.73e-08 2,36e-08 CE-144 2.52e-02 7.71e-03 6.65e-03 l TOTALS 1.6255 1.1598 1.0000 i I l
PRESSURIZER CHARACTERIZATION DON'T NEED 10 CFR 71 CERT OF COMPLIANCE - REVIEW OF PRESSURIZER OPERATION USE GENERATOR DISTRIBUTION MEASURE CONTACT DOSE RATES PRELIMINARY RESULTS - (ASSUMING USE OF LOW DENSITY ~21 lbs/ft CONCRETE) FRACTION OF LSA LIMIT (~0.01) FRACTION OF THE A LIMIT (~0.6) 2 r REVIEW OF AVAILABLE SAMPLE ANALYSES SENSITIVITY ANALYSES WITH COMPOSITE DISTRIBUTION COMPOSITE DISTRIBUTION INDICATES i j FRACTION OF A LIMIT (~0.9) 2 l ACTION PLANS - FILL WITH LOW DENSITY CONCRETE CLASSIFY AS A STRONG, TIGHT CONTAINER SHIP AS LSA, TYPE A QUANTITY i -}}