ML20052G869
| ML20052G869 | |
| Person / Time | |
|---|---|
| Site: | 07002884 |
| Issue date: | 03/11/1982 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20052G857 | List: |
| References | |
| 68.003.01, NUDOCS 8205190100 | |
| Download: ML20052G869 (16) | |
Text
i 5abmL :
l
}
Approved:
(Plahf4fanager) r-
\\ \\
v i
1
=3 1
.iL5 A ( d
- 4 l
SP Number 68.003.01 Revision 3 Date Eff. 9/22/78 TPC TPC TPC RECEIVING RADIOACTIVE MATERIALS 1.0 PURPOSE To provide detailed instructions on the proper method of receiving packages and shipments of radioactive material.
2.0 RESPONSIBILITY The llealth Physics Engineer shall be responsible for assuring implementation of this procedure.
_. / '
'glO k
\\
8205190100 820430 PDR ADOCK 07002884 C
PDR j
/
/,
3.0 DISCUSSION 3.1
'It is necessary that packages of radioactive material be expeditiously delivered and that the existence of a possible leak be rapidly detected to minimize radiation exposure to transportation and plant personnel, to minimize the spread of contamination and to aid in identifying personnel and property that may have been exposed-or contaminated during the transport of the radioactive' material.
Pro =pt survey of radioactive packages upon receipt is required by law in 10CFR20.
3.2 For personnel safety the packages should be surveyed for radiation and contamination levels as they are being opened and the contents removed to minimize the spread of contamination and reduce personnel exposure.
3.3 Vehicles used for shipment of radioactive material shall be surveyed when the vehicle arrives and before the vehicle is released from the protected area to ascertain that removable contamination and radiation levels are within specified DOT limits. The package should also be surveyed to determine that the shipment was made in accordance with applicable NRC and DOT regulations.
3.4 Topics covered in this procedure include:
fa_gg 8.1 Ordering and Approving Acceptance of Radioactive thterials 3
8.2 Receiving Sole-Use Shipments 3
8.3 Receiving Packages from Freight Carriers 4
8.4 Receiving Packages by Mail 6
8.5 Opening Packages 6
8.6 Receival Record 7
8.7 Identification 7
~8. 8 Releasing Sole-Use Vehicles 8
4.0 PRECAUTIONS N/A 5.0 PREREQUISITES N/A 6.0 LIMITATIONS AND ACTIONS 6.1 If the radiation or contamination levels on the package exceed any of the applicable limits specified in this procedure, the Hecith Physics Engineer shall be notified.
7.0 MATERIALS OR TEST EOUIPMENT 7.!
Rvlint to i Cur' y Inst ruwnt s I,'
Sro ! r :v:o -
SP68.003.01 Rev. 3 9/22/78 Page 2
7.3, Survey forms 7.4 Radiation rope or tape and appropriate warning signs 8.0 PROCEDURE 8.1 Ordering and Approving Acceptance of Radioactive Materials 8.1.1 The Health Physics Engineer shall review and approve all requisitions for radioactive materials (other than fuel) "to ensure that the quantity ordered does not exceed the limits authorized by license.
8.1.2 Personnel who are informed lor' otherwise have knowledge that-an outside agency is shipping radioactive material to the plant site (such as maintenance persennel_being sent contaminated!special-purpose tools from another sit e) shall inform the Health Physics Engineer of such shipments.
The information should include the method of shipment (mail, freight or sole-use vehicle), expected date of arrival, and description of the radioactive material.
8.1.3 All radioactive material requisitions shall specify that the material shall be delivered directly to the plant site.
Any outside agency sending radioactive material shall be informed that the shipment is to be delivered directly to the plant site.
If a-carrier requests that a package be picked up at the carrier's facility instead 6f delivery to the plant site, inform the Health Physics Engineer.
8.1.4 Packages and shipments of radioactive material shall be accepted at all times at the site, but the shipper should be contacted to arrange the delivery of packages or shipments during normal working hours on weekdays. The weekday,-normal working hours delivery restriction should not be enforced if it extends the time that a shipment or package of radioactive material will be on the road or sitting in a freight terminal.
8.2 Receiving Sole-Use Shipments 8.2.1 When a sole-use shipment of radioactive material arrives on the site, the group receiving the shipment shall notify the Health Physics Section during normal working hours or the Watch Engineer during backshifts.
8.2.1.1 Sole-use shipments are vehicles which are carrying only radioactive material and no other type of cargo.
3.2.1.1 Vehicles arriving on site carrying a cask (or -transport shield) for shipment of radioactive naterial or vehicles ident ified as having ore'. xsly shipped radioactive naterial shall t< treate: ".w as a sole-use sh!pn:nt.
I f
SP68.003.01 Rev. 3 9/22/78 Page 3
8.2.1.3 Complete r:diation cnd centczin tion surveys chtl1 ba taken whan th2 vehicle arrivas et the site.
8.2.2 llealth Physics qualified personnel shall conduct-(outside the Radwaste Bldg.) and record a radiation survey (Reference 11.3) of the outside of the vehicle to determine that the dose rates are:
8.2.2.1
< 10 mrem /hr at 6 feet from the side or edge of the vehicle, and 8.2.2.2 dC200 mrem /hr at any point on the sides of an enclosed van or at the edge of an open trailer, and 8.2.2.3
<t2 mrem /hr in the driver's compartment.
8.2.3 llealth Physics qualified personnel shall conduct and record a contamination survey to determine that the removable contamination levels of the outside of the vehicle are:
2 8.2.3.1
<c2200 dpc/100 cm beta gamma, and 2
8.2.3.2 ac220 dpm/100 cm alpha.
8.2.4 If all survey data is within limits, have the vehicle moved to a designated receiving area to proceed with unloading with the support of Ilealth Physics qualified personnel.
8.2.5 If the survey data is not within limits, inform the Health Physics Engineer and have the vehicles moved to an area where the radiation 1cvels caused by the shipment will not exceed'the restricted area limits or establish an appropriate temporary area.
8.2.5.1 If the vehicle is contaminated above limits post warning signs.
8.2.5.2 If the vehicle is not placardeo with " RADIOACTIVE" signs and the radiation levels from the vehicle exceed 5 mrem /hr., establish and post a radiation or high radiation area as applicable (as per Reference 11.5).
8.3 Receiving Packages from Freight Carriers 8.3.1 When a package of radioactive material is delivered to the site by a f reight carrier, a company " chicle or other delivery service, the group receiving the shipment shall immediately notify the llealth Physics Section during normal working hours or the Watch Engineer during backshifts.
This includes any box, carton, drum or other package which is identified as 'containing radioactive material either by a label on the package or as stated in the shipping napers.
NmE 1: % socii package should be acened until it has been surveyed.
SP68.003.01 Rev. 3 9/22/78 Page 4
NOTE 2: If a pickage is picked up from a c rrier's or shipper'e'fccility,-
It should be surveyed (as per 8.3.2 and 8.3.3) before being loaded into LILCO vehicles.
8.3.2 As soon as practicable, within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after arrival of the package, Health Physics qualified personnel shall inspect the package for physical damage and conduct and record a radiation survey of the outside of the package to determine that it is within the following limits:
8.3.2.1
<i10 mrem /hr at:3 feet from any surface of. the' package, and 8.3.2.2 dC200 mrem /hr at any point on the package surface.
8.3.3 As soon as practicable, within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after arrival of the package, Health Physics qualified personnel shall conduct and.
record a contamination survey to determine that the removable contamination levels are:
2 8.3.3.1 4:2200 dpm/100 cm beta'& gamms, and 2
8.3.3.2
<C220 dpm/100 cm alpha 8.3.4 If all survey data are within limits, have the package moved to a posted radioactive material storage area (as per Reference 11.6) or a restricted area'with controlled ventilation, to be opened with
'~
the support of Health Physics qualified personnel following the steps outlined in Section 8.5.
/
8.3.5 If the radiation or contamination levels of the package ard above the limits of 8.3.2 and 8.3.3 immediately notify the Health Physics Engineer.
8.3.5.1 If the levels are above the contamination-limits prevent the spread of further contamination and take steps to locate and identify any area,' equipment, other packages
/
or personnel on site; contaminated by the' package.
8.3.5.2 Iftheradiationlimitsareexceededestablishand',dosta radiation or high radiation area as necessary and request <
further instructions from the Health Physics Engineer.
8.3.5.3 The llealth Physics Engineer sha 1 direct agother survey to ensure..that the limits have been exceeded (refer to Reference 11.2) and thus determine if the situation must be immediately reported to the final carr7Lr and the Nuclear Rehblatory Cr:r.niesion inspection and Enforcemant Regional Office (as n'- Reference 11.9).
Also notify the Dept. of 't,rm sportatio-and tbc Shipper if the limits
~ have been exeecded.
[3 V
SP68.043.01 Rev. 3 9/22/78 Page 5
<v k
n W
8.4 R;cciving P;ckageo by !bil 8.4.1 When a package of radioactive material arrives through the mail or by other parcel service, the Health Physics Section shall be notified.
NOTE:
No package known to contain radioactive material should be opened until it is surveyed.
8.4.2 As soon as practicable licalth Physics qualified personnel shall inspect the package for physical damage and survey the package to insure that it is below the following limits:
8.4.2.1
<,0.5 mrem /hr at the surface of the package, and 2
8.4.2.2 502200 dpm/100 cm beta gamma removable contamination, and 2
8.4.2.3
<0220 dpm/100 cm alpha removable contamination 8.4.3 If the radiation or contamination levels are above these limits notify the llcalth Physics Engineer.
8.4.3.1 If radiation levels are exceeded, establish and post the area as necessary.
8.4.3.2 If the levels are above the contamination limits prevent the spread of further contamination and take steps to locate and identify any areas, equipment or personnel on site, contaminated by the package.
S.4.4 If the package is within limits take the package to an approved, posted storage area or to a lab hood or other area with controlled ventilation before it is opened with the support of itealth Physics qualified personnel.
8.5 Opening Packages of Radioactive taterial 8.5.1 Conduct a radiation and contamination survey of the package unless such a survey was performed when the package was received.
Establish a radiation and contamination area when necessary.
8.5.2 If the package is small open it inside a hood.
If the package is large open it in an area with controlled ventilation.
8.5.3 Survey for spreadable contamination as the package is opened.
Treat the contents and packaging material as if it was contaminated until it is pravea clean.
R.5.4
+u ve; tim em o to d e rmine tb - radiat ion and contaminat z on
'i.
In t%
ce.
rs n-
!Iqui' radiona 1ide, and neaind c.il l br,t ica n-do sn
, are aot le,kinn.
Check nas cylinders SPon.0/>3.01 Rev. 3 9/22/78 Page 6
~
with a cosp solution or immeras in water to determine that thsy are not'icaking.
Open p.}ckages of source material (as per Reference 11.7).
8.5.5 8.5.6 ~ Store the radioactive material or release it for use making sure to post the storage or work area with appropriate warning signs.
3, 8.6 Receival' Record Records of radioactive material're,ccived shall be kept on Appendix 12.1.
These records contain the following:
,g 8.6.1 Date Rec d,- The date the radioactive material was received on site.
8.6.2 Isotope - The symbol and mass number.
j 8.6.3 Phy. Form - The physical form (eg. solid, liquid or gas).
'8.6.4 I.D.' No. - The source identification number if applicable.
8.6.5 Vendor - The company from which the material was receives, 8.6.6 Location - The assigned storage area.
8.6.7 Activity - The qucntity original activity and the date assigned.
8.6.8 Type - The category of material, such as the following:
8.6.8.1 Encapsulated 8.6.8.2 Disc Sources 4
8.6.8.3 Radioactive Standards 8.6.8.4 Check Sources E
8.6.8.5 Tools l
8.6.8.6 Equipment 8.6.9 Disposal - The date, method and the initials of the person making the disposal.
ti-8.7 Identification
- 4 The Health Physics Section shall attach the necessary labels or tags.
J
-These labels or tags chall contain the following:
V
~
R.7.1 The ords "Caut ion - Radioac tive tS t orial' (or equivalent) e ;doying tha convent I onal color 2, agenta on a yell ou backf;r ound.
SP68.003.01 Rev. 3 9/22/78 Page 7 i'
I
.g
8.7.2 R:dioisotopa - Tha symbol and mano number (eg. 60Cs, 137Cs) cf the particular cource.
8.7.3 Original Activity - The activity indicated on the certificate of assay.
Include radiation and/or contamination levels where applicable.
Include date of activity.
8.7.'
Identification Number (Sources Only) - The-number which is assigned to the source for identification purposes in accordance with Reference 11.10.
8.8 Releasing Sole-Use Vehicles 8.8.1 Af ter unloading sole-use vehicles which were transporting radioactive materials, the vehicle shall be surveyed and not released until the vehicle meets the following limits:
8.8.1.1
< 0.5 mrem /hr at any accessible surface, and 2
8.8.1.2
< 2200_ dpm/100 cm beta gamma spreadable contamination on any accessible surface, and 2
8.8.1.3 4 220 dpm/100 cm alpha spreadable contamination on any accessible surface.
8.8.2 Vehicles used only for the transport of radioactive material and placarded "For Radicactive 1bterials Use Only" must meet the following limits:
8.8.2.1 (10 mrem /hr on any accessible interior surface, and 8.8.2.2
< 2 mrem /hr at 3 feet from any interior surface-2 2
8.8.2.3 e:220 dpm/100 cm alpha and 2200 dpm/100 cm beta gamma spreadable contamination on any outside accessible surface.
(There are no internal limits for contamination but the vehicle cust be closed except when loading or unloading).
8.8.3 A completed and signed Material Release Tag (Reference 11.5) should accompany vehicles which carry radioactive materials that si a cleared for release.
The Security personnel shall' collect these Material Release' Tags from vehicles removed from the protected area.
9.0 ACCEPTANCE CRITERIA N/A Spod.003.01 Kev. 3 9/22/78 Page 8
P0.*0 FINAL CONDITIONS 10.1 'All applicable documentation shall be cotopiled and filed.
11.0 REFERENCES
11.1 Regulatory Guide 7.3, 5/75, Procedures for Picking Up and Receiving Packages of Radioactive Material 11.2 Code of Federal Regulations, Title 10, Part 20, Section 205 11.3 SP62.010.01, General Radiation Survey Techniques 11.4 SP62.020.01, General Contamination Survey Techiques 11.5 SP61.020.07, Tools and Equipment Contamination Guides and Cantrols 11.6 SP61.010.03, Radiation & Radioactive Materitl Area Designations and Signs 11.7 SP64.001.01, Source Leak Testing 11.8 Code of Federal Regulations, Titic 49, Part 173, Sections 389-399 11.9 SP12.009.01, Station Reporting Requirements 11.10 SP61.088 01, Control of Radioactive Sources 12.0 APPENDICES 12.1 Radioactive Materials Receival Record e
N 68.pi.G.0i ev. ",
9/22/78 Page 9
s
- T I
N I
D L
O A H S
T O E P M S
I D
ET 3
A 0
D 1
vee Rg a E
1P 8
PYT 38 67 D
- 0. /
2 R
O 82 C
E 6/
NE T
P9 OR Y A S
I T D 1
TL I
2 AA V
1 TV I'
SI T
X E
C I
RC A N D
EE A
N kR U
E 0
Q P
PS P
L t.
RA AI ER N
LE O
CT I
UA T
NM I.
C ME O
AV L
HI ET RC OA HO R
SI O
D D
A N
R EV D. O 1N
.M YR HO PF I
E P
O T
0
~ ;
iI 1
i 1
0 C
i F 3
[i
. ;j ! 1!
l ll
, i j,}i' 0
0 s.
k 8
r 6
T a
I F
N me P
I R
S
Page 5 in a series of slabs separated by neutron flux trap regions consisting of water filled stainless steel boxes.
The fuel' cell re-gions of the rack are made up of rectangular stainless steel boxes approximately 6" x 12" by 165" long with each cell providing storage space for two fuel assemblics.
A base plate at the bottom of each box contains two sockets to support and position the fuel assemblics.
The top end of each fuel as-sembly is supported by the box structure of the rack.
The flux trap. regions of the
~
rack are formed of similar boxes 3.25 inches in width.
Upper end caps fit over the top of these boxes and are shaped to provide
" lead in" for insertion of fuel assemblies into the adjacent storage locations.
This design provides large box-to-box bearing surfaces that would serve to absorb any seismic vibratory energy by means of friction damping.
In addition, the struc-ture is strong enough to require only base' support through embedments in the floor of the pool.
These storage racks are of the same design as the racks installed at Oyster Creek, except that the Shoreham racks contain more storage capacity and the water boxes are smaller.
Spaces between normal fuel storage positions are designed so that it is not possible to insert a fuel assembly, either deliberately or by accidental drop, in any position within the rack array not incended for fuel.
1.2.3.3 Reactor Building Polar Crane The Reactor Building Polar Crano is a top running type, dual load path, double girder electric overhead travelling crane.
The crane rotates on a circular runway and has one 125-ton main hoist and one 30-ton aux-iliary hoist.
Administrative controls, specific operating procedures and safe load paths will be established to prevent heavy 1
loads unnecessarily traversing the Spent Fuel Storage Racks.
The Reactor Building Polar Crane is rated for the normal plant operating lifts.
It is designed as a Seismic Category I crane,
.. ~.., ~
Page 8 keys controlled by'the Site Security-Supervisor.
Administrative controls and security measures will be established to prevent unauthorized personnel from gain-ing access to the refueling elevation via the service elevator.
A watchman will be posted for access control during those times when work is performed on the refueling level.
During other i[
times, surveillance will be provided by a watchman randomly patrolling the refueling level.
1.2.5.2 Interim Storage at 138KV Substation In the event that the'l;$KV Substation is used for interim storage prior to moving the new fuel into the Reactor Building, an equivalent form of security will be provided.
The interim storagd f
area will be a protected area that
[
is surrounded by a physical barrier r
,provided.with a perimeter intrusion detection system.
The intrusion detection r
system will signal an alarm when fence penetration is attempted.
Any intrusion f
alarm will be monitored and evaluated by a member of the security force to deter-mine what, _if any, action will be nec-essary.- During any time that the intrusion alarm system is inoperable, a member of the security force will be posted at or within the perimeter of the physical barrier.
Keys providing access to the area will be under the control of the Site Security Supervisor.
1.3 Physical Protection Because the enrichment of U235 in the new fuel assemblies is less than 20 percent, see Section 1.1.3 above, the Ap-plicant is exempt from the security requirements set out in 10CFR Sections 73.30 through 73.36, 73.60. 73.70 and
~
73.72.
See 10CFR Sections 73.l(b), 73.6; Regulat.ory Guide 3.15, paragraph 1.3.
- 1.4 Transfer of Special Nuclear Materials Transportation of the fuel assemblies from the fabrication location at Wilmington, North Carolina, to th'e reactor site at Shoreham will be the responsibility of the fuel fabricator, t
f n
7
Page 12
~
Spaces between. storage assemblies are designed-such that.it is not possible to insert a fuel-assembly either deliberately.or by accidental drop in any position within the rack array not intended for fuel.
See Section 1.2.3 above.
2.2.4 Fuel Handling Procedures Fuel assemblics will be inspected after removal from the shipping containers, but before channel-ization and storage in the Spent Fuel Storage Pool or New Fuel Storage Vault.
Under' normal cir-cumstances, the fuel will not be moved again until fuel loading takes place.
A fuel array of up to three fuel bundles outside of a normal storage area or normal shipping con-tainer will be maintained with an edge-to-edge spacing.of 12 inches or more from all other fuel.
y A fuel array of four or more fuel bundles outside of the normal fuel storage areas._or properly designed fuel shipping container will be' prohibited.
2.2.4.1 General Prerequisites for Fuel Handling Shoreham procedures specify detailed conditions and activities prior to handling of fuel.
These prerequisites ensure that zone cleanliness, equipment operability, and personnel safety satisfy operational requirements.
2.2.4.2 Removal of Fuel Bundles From Shipping Container and. Inspection Before fuel assemblies are removed, the metal shipping containers are placed in a vertical position.
The respective fuel assembly is then removed via the Polar Crane or Jib Crane, and transferred to the New Fuel Inspection Stand.
After the fuel is secured in the stand, the assembly will be inspected in accordance with Fuel Inspection procedure.
Any discrepancies will be documented on a site QA Noncon-formance Report and Reject Tags secured to the rejected fuel assembly.
2.2.4.3 Channeling in the New Fuel Inspection Stand Upon completion of the fuel inspection, each assembly is channeled in the New Fuel In-spection Stand.
A new channel is selected and positioned above the new fuel assembly.
7
-n_-.
.N
-pyL.,
j)(({
.Q]
p
, r
.s y\\
- q n %. N Cf:;.i 6 5,L:p,:
,..; 9 m m E ?L7**W 9*:
t [%. 2_fdf..'hfW%l
[&4;{\\ ;',. m; G n't i
8.,~
y,... =
1 ysAp:h -
,ti p ).A My 6
[T' h
- t. 2
'.)// ;,M :T
/
~
8
- pwa m @s
- HjW i
a f
{
t
.:22c.^.
':.'Ct.2:?,'2Y%7MtMT.C.23.MC~12'2.MG2H1%Q':5Xl2K'.tMZ"R.MI Harch 31, 1976 SIL No. 152 File Tab A Category 1 CRITICALITY MARGItis FOR STORAGE OF HEU FUEL Using optimum moderator conditions, calculations indicate that there is an extremely remote possibility for inadvertently establishing critical conditions in the new fuel storage racks, or in a dry spent fuel pool loaded with new fuel.
Potential sources for an optimum mederator are fire extinguisher foam, water mist, steam or other hydrogenous matacials.
This Service Information Letter (SIL) reccrrmends precautionary measures to BWR operators to further reduce the already very low probability of acb an event occurring.
DMCUSSIO:1 k (\\ >~]
An analysis by General Electric indicated that it would require the-introduction of a low equivalent water density material to completely occupy the space in and around an array of fuel assemblies in storage for the occurrence of a criticality.
Both 10 x 25 and 20 x 25 bundle arrays were analyzed, with and without gadolinia, to simulate reactivity conditions from initial _ core loads to the most reactive design basis reload fuel.
In all cases the optimum moderation occurred when 'the equivalent weter density was = 0.2 gram /cc.
In the worst case, a range of equivalent water densities from 0.05 to OAS grams /cc was undesirable in conforming to the design basis K limits. This concern has been judged by General Electric not$ be a reportable deficiency and the judgment has been supported by the tiRC.
Results of BWR site surveys have indicated the presence of-fire hose stations and sprinklers on the refueling floor at a significant number of plants. Also, a substantial number of hoses in these stations are providad with adjustable nozzles that are variable from a solid stream to a coarse spray.
In the interest of assuring safety margins on the refueling floor, additional controls that further reduce the prebability of a criticality occurrence should be ireplemented.
RE.C.CM G. _ 0 0 fC_T. I O:1 n
t;nn ml F '
' P reccc: md ' t h a t ti prc~' ural r %t rois lis t. d below
(
)
be consiuere;; at the earliest convenient opportu.lity to reduce the
!)'
remote probability for inadvertently establishing critical conditions for new fuel storage:
' OPERATING PLA'IT SERVICES SAN JOSE, CAL!FORNIA 95125 siUCL' EAR EMERGY OlVISlON o
NO WAHH ANTY 08 HEPHESENTATION EXPRESSED OR IMPLIED IS MADE WITil HFSPECT TO THE ACCURACY. COMPLETENESS OR U3EFULNES3 OF THIS INFOR-E M L M,_ff ELEMRI C f.* A D ON GENERAt. ELECTRIC COMPANY ASSUMES No HESPON3tBILITY FOR LIA-GE f:lLITY OH DAMAGE WHICH MAY HESULT FROM THE USE OF THIS INFORMATION.
s
s
\\
.f
\\
March 31, 1976 SIL f:o. 152
\\
( V(~
y 1.
The new fuel storage vault should always be dry. For example,
- t. N
~
it should be impossible to blo'ck the drain, or in any way produce the equivalent water densities in the ranges noted above.
The spent fuel pool should be flooded or covered with a fireproof 2.
cover if new fuel is in storage when construction activities or construction debris are present.
Flooding should provide at least enough water to cover the bundles.
In taking these steps, the plant owner should be careful to assure that the fuel pool cooling system is either inoperative or properly vented prior to startup to preclude an air clearing event through the The dispersion of many small bubbles is a potential spargers.
source of low equivalent water density.
3.
Fuel should not be stored in the new fuel vault when there are construction activities on the refueling floor or construction debris in the. vicinity of the new fuel vault unTess a solid cover is placed over the vault. This solid cover would help to prevent the introduction of low density water such as a fog or spray should the operation of fire hoses beccine necessary on the refueling floor.
4.
The attachment to this SIL entitied, " Procedural Recoamendations
( f) for flormal Fuel llandling Operations" should be reviewed by BWR plant personnel to assure a complete understanding of all
'( ;
v current procedural controls relevant to fuel handling operations.
It should be noted that for reasons of emphasis items 5, 6 and 14 in the attachment are identical to tiie procedural control recommendations 1, 2 and 3 listed above.
For addit ional information and assistance, consult your local General Electric service representative.
Prepared by:
C. J..Paone/L. A. Gonzalez Issued by:
W l
Approved by:
D. L. LaytAn, Acting Manager D. L. Layton,/ Manager Performarke Analysis &
l Product Service Service Comun. cations Product
Reference:
A71 - Plant Pecomendations Jil - icel and IL:lcaJs A
i lV r
(
l
~r SIL tio.152 Ilarch 31, 1976 Attachment h
Od
~
PROCEDURAL RECOP14Ei!DATI0ilS FOR it0?f!AL FUEL PA*iDLU.G 0?EP.MIO.iS 1.
tio more than one fuel bundle should be suspended above.the fuel storage array and this at a height no greater thar. 24 inches to limit penetration displacement if the bundle was dropped.
2.
Fuel handling in the fuel storage area shculd be limited to one
~
fuel assembly or the weight equivalent per crane. An exception to this requirement is a properly designed fuel shipping container or an.ovarload test weight. The shipping container or overload test weight should at no time be suspended above the fuel storage array.
3.
A fuel array of up to three fuel bundles outside of a normal storage
' area or normal shipping container should be maintained with an edge-to-edge spacing of 12 inches or more frca all other fuel.
4.
A fuel array of four or more fuel bundles outside-of the normal fuel storage areas or properly designed fuel shipping container should be prohibited.
5.
The new fuel vault should always be dry.
)
((S V 6.
The spent fuel pool should be maintained in a flooded condition
~
l if new fuel is in storage during construction activities or when construction debris are present.
Flooding should provide at least
~
enough water to cover the bundles.
If the spent fuei pool is not flooded when new fuel is in storage, the fuei should be covered by a solid, fireproof material to prevent possible inundation by low density fire extinguisher faara or water mist.
7.
tiew fuel should not be stored such that a fuel bundle could remain flooded without water existing between bundles _
8.
Fuel movement in the new fuel vault should not be permitted if an abnormal condition of vault flooding occurs.
9.
Fuel should not be placed in aisles or moved through aisles adjacent to and at the same level of the storage racks.
10.
Defective fuel should always be stored in defective fuel storage
~
containers and placed in the defective fuel storage rack or control rod storage rack.
11 If foal is stored in tecporary sarege rads belcw the fuel pool work table, the work table shoolf nr W ud te h ndle, fuel; 3
cone rs ly, if tb :ar6 ta512 is used to hndle fuel, fuel storage v/
belo./ the work table should be prohibits.
s/
?
A.
i n
m.
v
~!! arch 26, 1976 SIL fio. 152 Attachn ent
' f 12.
tio more than two fuel bundles should be allowed in or cround a fuel d^
prep raachine at any time. This fuel should be scparated from the k
main body of stored fuel by at least 12 inches.
13.
fuel should not be stored outside of designated storage cells.
14.
!!ew fuel should not be stored in the.new fuel vault when there are construction activities on the refueling floor or construction debris in the vicinity of the new fuel vault unless a solid, fireproof cover is placed over the fault which would preclude criticality due to inundation by low density water such as water fog or spray from a fire hose.
e D-i t
g_
]
we
\\
-r
. -.. - -.. -. -