ML19209A954
| ML19209A954 | |
| Person / Time | |
|---|---|
| Site: | 07106346 |
| Issue date: | 08/21/1979 |
| From: | Moore R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML19209A953 | List: |
| References | |
| 14039, GADR-55, NUDOCS 7910050664 | |
| Download: ML19209A954 (20) | |
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m....m,mem c:1 GENERAL ATOMIC COMPANY P. O. Box 81608 San Diego, CA 92138 GADR-55 ADDENDUM I REVISION C FINAL DESIGN REPORT FOR FORT ST. VRAIN FUEL SHIPPING CASK P00ROR!B!NAL Approved: Robert L. Moore 21 August 1979
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o'u GENERAL ATOMIC COMPANY P.O. Box 81608 San Diego, CA 92138 GADR-55 ADDENDUM I REVISION C FINAL DESIGN REPORT FOR FORT ST. VRAIN FUEL SHIPPING CASK m
l n
Approved:
Robert L. Moore 21 August 1979 9
1105 084
ADDENDUM I GADR-55 Revision C TABLE OF CONTENTS PAGE cs
. )
INTRODUCTION SECTION I SYSTEM DESCRIPTION A.
PURPOSE 1-1 B.
NORPAL OPERATING REQUIREMENTS 1-1 C.
ABNORPAL OPERATING REQUIREMENTS 1-1 D.
EQUIPMENT LIST 1-1 E.
NORPAL OPERATING PRCCECURE 1-2 F.
MAINTENANCE PROGRNi 1-8 G.
LEAKAGE TESTIN9 1-8 SECTION II PHYSICAL AND FUNCTIONAL DESCRIPTION A.
GENERAL 2-1 B.
SPENT FUEL CONTAINER LIO 2-1 C.
SHIPPING CASK CLOSURE 2-1 D.
IMPACT LIMITER 2-2 E.
DRAWINGS 2-2 SECTION III PROPERTIES OF MATERIALS A.
DEPLETED URANIUM 3-1 B.
STAINLESS STEEL PIPE 3-2 C.
STAINLESS STEEL FORGINGS 3-2 D.
ASTM AS79 ALLOY STEEL 3-3 E.
6061-T6 ALUMINUM 3-3 F.
PLYWOOD 3-3 G. ' URANIUM WELDS 3-3 H.
STAINLESS STEEL WELOS 3-3 I.
SEALS 3-4 1105 085
GADR-55 ADDENDUM I REVISION C INTRODUCTION Addendum 1 to GADR-55 provides the Safety Analysis for an alternate closure system for the model FSV-1 cask. This alternate closure system consists of the following major components:
Fuel Container Ltd Shipping Cask Cover Impact Limiter Associated with these major components are the seals, test ports, bolts, and retainers.
The alternate closure system is shown on General Atomic Company (GAC) Drawings GADR-55-2-1, GADR-55-2-2 and GADR-55-2-3. The detailed des-cription and the supporting analysis is presented in the folloiwng sections of Addendum 1.
These sections are numbered the same as the sections of GADR-55 and contain the additional analysis and description associated with
~
the alternate closure system for the model FSV-1 cask. The alternate closure system is designed to satisfy the requirements of 10 CFR 71 as effective June 1978, except that the leakage rates and tests are designed to satisfy the requirements of ANS N14.5, " Leakage Tests on Packages for Shipment of Radioactive Materials", dated November 1974.
Reference throughout this report has been made to GAC manufacturing drawings designated as 90-H1501-XXX. These individual drawings are not a part of this report.
Instead, GAC Drawings GADR-55-2-1, GADR-55-2-2 and GADR-55-2-3 have been included to provide the necessary design information.
~
1-1 1105 086
GADR-55 ADDENDUM I REVISION C f.
Using the 17-1/2 ton overhead crane, move a reactor isolation
,_j valve from stcrage and position it on top of the fuel loading
~
po.. Use alignment gage for positioning.
g.
Connect purge and control lines to reactor isolation valve and open valve.
h.
Inflate reactor isolation valve seals.
- i. Unfasten the 12 bolts in the spent fuel container lid.
- j. Remove shipping plug and primary plug from container lid.
k.
Install track and adapter guide onto shipping container lid.
Engage the track on the two keys in the RIV.
1.
Using the 170 ton overhead crane, move the auxiliary transfer cask from storage position to the top of reactor isolation valve located on the fuel loading port.
m.
Open the shutter of the valve of the auxiliary transfer cask and lower the auxiliary transfer cask grapple to engage track and adapter assembly for lifting the shipping container lid, n.
Raise the container lid into auxiliary transfer cask.
i o.
Close the reactor isolation valve.
p.
With the purge connection on the reactor isolation valve, purge the auxiliary transfer cask and backfill with air.
q, Close auxiliary transfer cask shutter.
r.
Move the auxiliary transfer cask to its storage position and bolt in place.
3.
Placing the Spent Fuel Elements in the Shipping Cask.
a.
Mount the fuel handling machine with 6 spent fuel elements to the RIV on the loading port.
b.
Open the reactor isolation valve.
c.
Evacuate fuel shipping cask through the reactor isolation valve and backfull with helium.
d.
Open fuel handling machine cask valve.
e.
Deposit 6 fuel elements into fuel shipping cask.
f.
Close and seal the fuel handling machine cask valve and the reactor isolation valve.
1105 087
GADR-55 ADDENDUM I REVISION C g.
Evacuate the reactor isolation valve interspace and backfill
)
with air.
h.
Remove the fuel handling machine to its stnrage position.
4.
Installing the Container tid.
a.
Move the auxiliary transfer cask from its storage position and mount to the reactor isolation valve over the fuel loading port.
b.
Evacuate the auxiliary transfer cask and backfill with helium.
c.
Open the reactor isolation valve.
d.
Lower and deposit the fuel shipping cask container lid.
e.
Evacuate auxiliary transfer cask to 20 m Hg and backfill with air.
f.
Remove and store the auxiliary transfer cask.
g.
Remove track and adapter assembly from the container lid, h.
Bolt dcwn the container lid using twelve 1/2 inch bolts.
Torque to 15 to 20 ft-lbs.
)
1.
Install primary plug in the container lid.
- j. Remove reactor isolation valve to its storage position.
5.
Leakage Testing the Container Ltd Seals.
Assembly verification testin (Done before each use except a.
when Step 5.b. is required.)g.
(1) Connect leakage test system with pressure gauge and shutoff valve to test port in container lid.
(2) Evacuate seal interspace to a pressure of 1 m Hg.
Close shutoff valve.
(3) Wait 2 minutes.* Maximum permissible pressure rise is 5.5 m Hg (6.5 m Hg on gauge).
- Test time is based on a total test cavity volume of I cubic inch (16.387 cm3)
I-5 1105 088
GADR-55 ADDEf1DUM I REVISI0tt C (4)
If pressure rise is greater than the permissible rise, G
replace main flange and primary plug seals.
Repea:
Step 5.b.
b.
periodic verification testirs (done prior to each third use or within 12 months prior to use or after each seal replace-ment).
(1) Connect leakage test system fitting with pressure gauge and shutoff valve to test port in container lid.
(2) Evacuate seal interspace to a pressure of 1 mm Hg.
Close shutoff valve.
(3) Wait five minutes.* Maxi,?um permissible pressure rise is 5.7 m Hg.
(6.7 m Hg on gauge)
(4)
If pressure rise is greater than the permissible rise, replace main flange and primary plug seals.- Repeat Stem 5.b.
c.
Disconnect leakage test system from vacuum source.
d.
Open shutoff valve to vent seal interspace and remove leakage test system.
e.
Install the shipping plug in the test port.
f.
Remove seal adapter from top of cask.
- Test time is based on a total test cavity volume of 1 cubic inch 3
(16.387 cm )
I-Sa 1105.39
GADR-55 ADDENDUM I SECTION I REVISION C F.
MAINTENANCE PROGRAM
)
The shipping cask with the fuel container, and all auxiliary equipment will be maintained to assure that all items are in proper operating con-di tion. A checklist will be developed which will list each component which requires specific maintenance actions.
The checklist will include the method of maintenance check to be used, the acceptance criteria for each, and the required maintenance frequency. Each checkpoir.t will re-quire sign-off by the individual makir.g the check.
Space will be pro-vided on the maintenance checklist to enter the equipment identification, supervisor's name, and the date maintenance is completed.
The maintenance checklist will also include all auxiliary equipment, such as the lifting yoke, tie-down assemblies, and trailer. Maintenance of the trailer will be carried out in accordance with standard industry-recommended procedures and schedules.
The cask operating procedure will contain steps requiring a review of the equipment maintenance program checklists to verify that all required maintenance and periodic testing has been accomplished.
G.
LEAKAGE TESTING In accordance with Regulatory Guide 7.4, the guidance contained in ANSI N14.5, " Leakage Tests on Packages for Shipment of Radioactive Materials",
was used to establish the maximum permissible leakage rate and the minimum leakage test sensitivity.
1.
The containment system assembly verification test will be conducted prior to each use (except when the periodic verification test is required) as follows:
Component Verification Fuel Container main flange (a)
(b) double seal Fuel Container primary (a)
(b) plug seal (a) Checklist verification of proper assembly.
(b) Leakage test by evacuating tne seal interspace to a pressure of 1 m Hg. Observe that pressure does not rise above 6.5 mm Hg in two minuto (maximum permissible leakage rate is 1 x 10 3 atm 3
cm/sec).
2.
The ' containment system periodic verification test will be conducted prior to each third use, within 12 months of any use and prior to any use following the replacement of any primary seals.
1105 090 1-8
GADR-55 ADDENDUM I
~
SECTION I REVISION C
~
Component Verification
)
Fuel Container main (a)
(b) flange seal Fuel Container primary (a)
(b) plug seal (a) Checklist verification of proper assembly (b) Leakage test by evacuating the seal interspace to a pressure of 1 m Hg. Observe tnat pressure does not rise above 6.7 m H in five minutes (maximum permissible leakage rate is 4.12 x 10 g4 atm em3/sec).
3.
The shipping cask seals that are not part of the centainment system will be tested as part of the annual maintenance procedure as follows:
a.
Pressurize the shipping cask cavity to 10 psig 01 rough the lower purge valve connection.
Reinstall the purge valve cover and apply soap solution around the purge valve cover and the lower cavity access port cover. No leak indications permitted.
b.
Remove the shipping plug from the cask cover. Evacuate the seal interspace to a pressure of 1 m Hg. Observe that pressure does not rise above 6.5 m Hg in two minutes (maximum permissible 3
leakage rate is 1 x 10 3 atm cm /sec).
4.
Calculations for pennissible leakage rate.
The maximum pennissible leakage rate and the minimum sensitivity of the leakage test were determined by using the guidance provided in ANSI N14.5, " Draft American National Standard for Leakage Tests on Packages for Shipment of Radioactive Materials",
a.
Containment: The FSV-1 cask with. alternate closure system is assumed to be a Type B (U) package, b.
Gaseous fission product inventory:
(1) Normal conditions of transport:
negligible quantity (Ref. 3).
(2) Accident conditions of transport:
Kr 85 470 curies (Ref. 3).
c.
Parameters:
'(1) A2 value for Kr 85 1000 curies (Ref. 1).
=
(2) R package containment requirements for normal
=
N conditions of transport, curies per second (Ci/sec).
R 2.78 x 10 Ci/sec (Ref. 2)
=
N 1105 091 I-9
GADR-55 ADDENDU11 I SECTION I REVISICJ C package containment requirements for accident (3) R
=
A
,.)
conditions of transport, curies per :econd (Ci/sec).
A2 x 1.65 x 10' Ci/sec (Ref.2).
R
=
A (4) ' Fuel container net volure:
235 x 103 cm3 (5) Volume of test port in container Tid and the test 1.0 in. 3 (16.387cm3) equipment, V
=
p d,
Normal conditions of transport:
Since the inventory of gaseous fission products during normal conditions of transport is negligible, the accident condition will establish tne permissible leakage rate.
e.
Accident conditions of transport:
3 permissible leakage rate, atm cm /sec (1) L
=
A RA L
r
= -
A CA specific activity of containment medium C
=
A 470 Ci CA 235 x 103 cm3 1000 x 1.65 x 10-3 = '.65 x 10 6 R
=
A 1.65 x 10 6 Ci/sec L
A 2.0 x 10 3 Ci/cm3 f.
Containment system periodic verification:
The periodic leakage test is required to have a sensitivity to detect leakage that is 1/2 of the permissible leakage.
3 8.25 x 10 4 cm /sec L
=
A 3
4.12 x 10 4 cm /sec 1/2 L
=
A Thus a " pressure rise" test with a nominal sensitivity of 3
1 x 10 4 atm cm /sec was selected.
(1) Duration of leakage test:
3 Using a test volume of 16.387 cm, a starting pressure of 1 m Hg and an ending pressure of 7.6 m Hg (Ref. 2), the volume of inleakage, V is:
4
'-2 1105 092
GADR-55 ADDENDUM I SECTION I REVISION C 3
7.6 1
O V
16.387 cm3
= 1.42 x 10 1 cm3
=
4 760 760
~
~
test time in seconds is:
t
=
1.42 x 10 1 cm3 344.7 sec t
=
=
3 4.12 x 10
- cm /sec The allowable rate of pressure rise is:
6.6 m Hg
.01915 m Hg/sec
=
344.7 see The allowable pressure rise for a five minute test is:
5.7 c... Hg
.01915 x 5 x 60
=
(2) Check of test sensitivity:
Y T P
P -
p 3 2
i (Ref. 2, Eq. Bil)
L
=
3 3600 H
_T2 T_
i
_ 7.6 1
16.387 x 298 760 760
=
s 3600 x 344.7
_298 298.
)
3600 3
4.12 x 10 4 atm cm /sec L
=
3 g.
Containment system assembly verification:
This test is used to verify that'no gross seal defects exist prior to each shipment, therefore, a less sensitive test 3
procedure is required. A test sensi tivi ty of 1x10-3 a tm cm / sec is assumed to provide a more reasonable test time although a atra cm /see test is allowed.
(Ref. 2) 3 1 x 10 1 1.42 x 101 cm3
= 142 seconds t
=
s 1 x 10 3 cm3/sec The allowable rate of pressure rise is:
6.6 m Hg
.0465 m Hg/sec
=
142 see The allowable pressure rise for a +.wo-minute test is:
5.6 m Hg
.0465 x 2 x 60
=
I-11 1105 093
GADR-55 ADDEf4DUM I SECTION I REVISI0ff C Ref. 1.
IAEA Safety Series, No. 6.
1973 revised.
2.
ANSI N14.5. November 1974 3.
GADR-55, Supplement A, page 9-5, 9-6 and 9-7.
9a 1-12 1105 094
.w
...w
GADR-55 ADDENDUM I SECTION II REVISION C The shipping cask closure is sealed to the cask body with a stainless
~
g steel / dual concentric silicon elastomer seal design similar to that used on the spent fuel container lid. A single test port is routed from the top of the closure to the innerspace between the concentric seals to allow for seal leak testing similar to that done on the container lid seal.
D.
IMPACT L' MITER An aluminum encased plywood impact limiter attaches to the top end of the cask and completely envelops the cask closure and container lid area.
The impact limiter is designed to protect the cask closure area from both top end and side drops as well as drops through all intermediate angles. The limiter is made up of about 40 layers of 3/4 inch thick marint grade ply-wood and is encasec in aluminum for weather protection and durability during handling. The impact limiter is clamped to the outer top end of the cask using a continuous mounting ring which is held to the impact limiter with six 1/2 inch diameter fasteners.
E.
DRAWINGS General Atomic Company: GADR-55-2-1, GADR-55-?-2, GADR-55-2-3.
"-2 1105 095
SECTION Y 5-2a GADR-55 ADDENDUM I REVISION C
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