ML19344A851
| ML19344A851 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/10/1978 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220348 | |
| Download: ML19344A851 (39) | |
Text
3 7 ~p Q oENIRAL OFFICE Nebraska Public Power District
" M'Et,inE%"osl0M"^>"^ '" 2 July 10, 1978
?
THIS DOCUMEtd CONTAINS
. POOR QUAUTY PAGES 5-Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Subj ect : Movement of Heavy Loads Near the Spent Fuel Facility -
Request for Information Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Dear Mr. Stello:
In your letter dated May 17, 1978 you requested the Nebraska Public Pover District to provide additional information regarding the movement of heavy loads near the spent fuel facility.
This letter transmits the information requested as Attachment 1. contains the procedure for the movement of the frel casks at Cooper Nuclear Station.
As you requested, the District has reviewed its current procedures for the covement of heavy loads over spent fuel and has concluded that the potential for a handling accident which could result in damage te suen; fuel is at a minimum.
Should you have any questions or desire additional information, please contact me.
In addition to one signed original, 39 copies of this information are also submitted for your use.
Sincerely yours, M
Ja
- d. Pilant Director of Licensing and Quality Assurance 3DV!cak Attachment SocS22.03'f3
Victor Stello, Jr.
July 10, 1978 Page 2 STATE OF NEBRASKA )
) ss PLATTE COUNTY
)
Jay M. Pilant, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a
public corporation at.d political subdivision of the State of Nebraska; that he is duly authorized to submit this information on behalf of Nebraska Public Power District; and that the statements in said application are true to the best of his knowledge and belief.
M a
Q ay M. Pilant Subscribed in my presence and sworn to before me this
((
day of July, 1978.
NOTARY PUBLIC My Commission expires Stutt4L 20f A2T - State W Battsshe MARILYN R. HOHNDOM Wy Comm. Ess. Oct.14,1se
r Attachment No. 1 Page 1 of 5 Question No.-l Provide a diagram which illustrates the physical relation between the reactor core, the fuel ~ transfer canal, the spent. fuel storage pool and the set.down, receiving or storage areas for any heavy loads moved oh the refueling floor.
fesponse FSAR drawings XII-2-6, 2-7, and 2-8 illustrate the physical relation l
between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas.
Question No. 2 Provide a list of all objects that are required to be moved over the reactor core (durint refueling), or the spent fuel storage pool. For each. object listed, provide its approximate weight and size, a diagram of
'the movement path utilized (including carrying height) and the frequency of movement.
Response
The. only object which is required to be moved over the reactor core (during refueling), or the spent fuel storage pool is the refueling platform which is on rails on either side of the cavities. Movement of the fuel cask is interlocked to include only that area of the spent fuel storage pool directly over the fuel cask storage area. The fuel cask does not move over the spent fuel racks. Discussion of the fuel cask physical dimensions and handling has been submitted in FSAR Amendment No. 33, sections 5.0 and 6.', respectively.
0
-Question No.__3 What are the dimensions and weights of the spent fuel casks that are or will be used at your facility.
Response
Dimensions and weights of the spent fuel cask were submitted in FSAR Amendment.No. 33 and is described in paragraph 5.1.
Question No. i Identify any heavy. load or cask drop analyses performed to date for your-rfacility. Provide-a copy of all such ' analyses not previously submitted to the'NRC staff.
Response
A cask' drop analyses has been previously submitted, FSAR Amendment No. 11, response to question No. 10.1.
1.
Attachment No. I Page 2 of 5 Question No. 5 Identify 2ny heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved.
Identify what equipment could be affected in the event of a heavy load 7. handling accident (piping, cabling, pumps. etc.) and discuss the
?
feasibility of such an accident affecting this equipment.
Desc' ribe the
{. basis for your conclusions.
Response
. Heavy loads are not carried over equipment required lor the safe shutdown of the plant.
Question No. 6 If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facilit), discuss the feasibility of a handling accident which could result in water 12-bage severe enough to uncover the spent fuel. Describe the basis for your conclusions.
Response
The spent fuel cask drop analyses was submitted in FSAR Amendment No. 11 (Question No. 10.1).
No other heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at Cooper Nuclear Station.
Question No. 7 Describe any design features of yost facility which affect the potential for a heavy load handling accident involving spent fuel, e.g.,
utilization of a single failure-proof crane.
Response
The design features which affect the potential for a heavy load handling accident involving spent fuel is discussed in FSAR Amendment No. 33, Sections 1.0, 2.0, 3.0 and'4.0.
- Question No. 8 Provide copies of all procedures currently in effect at you: facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.
Response
Administrnrive Drocedures insure that heavy loads are not transported over the exposed reactor core during refueling. Procedures that govern the removal of heavy objects from directly above the core (i.e. shield plugs,
Attachment Wo. 1 Page 3 of 5
.drywell head, etc.)'before the core is uncovered, insure that these objects do not pass over the reactor cavity or fuel pool cavity. These procedures are available at Cooper Nuclear Station for, review. The only heavy load to be carried over.a portion of the spent fuel storage pool will be the fuel cask 7hich is interlocked to include only that area of T
the spent fuel storage pool directly over the fuel cask storage area.
E The procedure _for the preparation and shipment of spent fuel 13 discussed
~
C in Attachment "2".
No heavy loads are carried over_ equipment required for' safe shutdown of the plant while the plant is operating.
2 Question No. 9
' Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1,
. December, 1975) regarding Spent Fuel ^ Storage Facility Design Basis.
The spent fuel storage facility (including its structures and a.
equipment except as noted in paragraph f below) should be designed to Category I seismic requirements, b.
The facility should be designed (a) to keep tornadic winds and missiles generated by these winds from causing significant loss of i
water tight integrity of the fuel storage pool and (b) to keep missiles generated by tornadic winds f rom contacting fuel within the pool, Interlocks should be provided to prevent cranes from passing over c.
stored fuel (or near stored fuel in a manner such that if a crane
-failed, the load could tip over on stored fuel) when fuel handling is not in progress. During fuel handling operations, the interlock may be bypassed and administrative control used to prevent the crane from carrying loads that are not necessary for fuel handling over the stored fuel or other prohibited areas. The facility should be designed to minimize the need for bypassing such interlocks.
d.
A controlled leakage building should enclose the fuel pool. The
-building should be equipped with an appropriate ventilation and filtration system to limit the potential release of radioactive iodine and other radioactive materialt. The building need not be designed to withstand extremely high winds, but leakage should be suitably controlled during refueling operations. The design of the f
-ventilation and filtration system should be based on the assumption
- that the cladding of all of the~ fuel rods in one fuel bundle might be breached. The inventory of radioactive materials available for
~ leakage from the building should be based on the assumptions given in Regulatory Guide 1.25, " Assumptions Used for Evaluating the Potential J
Radiological Consequences of a Fuel Handling Accident in the Fuel.
4 Handling and Storage Facility for Boiling and Pressurized Water Reactors" (Safety Guide'25).
Attachmeat No. 1 Page 4 of 5 e.
The spent fuel storage facility should have at least one of the following provisions with respect to the handling of heavy loads, including the refueling cask:
1.
Cranes capable of carrying heavy loads should be preven ~ted, preferably by design rather than by interlocks, from mdying into the vicinity of the pool.
' 2.
Cranes should be designed to provide single-failure-proof handling of heavy loads, so that a single failure will not result in loss of capability of the crane-handling system to perform its safety function; or 3.
The fuel pool should be designed to withstand, without leakage that could uncover the fuel, the impact of the heaviest load to be carried by the crane from the maximum height to which it can be. lifted. If this approach is used, design provisions should be made to prevent the crane, when carrying heavy loads, from moving in the vicinity of stored fuel.
f.
Drains, permanently connected mechanical or hydraulic system, and other features that by maloperation or failure, could cause loss of coolant that would uncover fuel should not be installed or included in the design. Systems for maintaining water quality and quantity should be designed so that any maloperation or failure of such systems (including failures resulting from the Safety Shutdown Earthquake) will not cause fuel to be uncovered. These systems need not otherwise meet Category I seismic requirements.
g.
Reliable and frequently tested monitoring equipment should be provided to alarm both. locally and in a continuously manned location if the j
water level in the fuel storage pool falls below a predetermined level or if high local-radiation levels are experienced. The high-radiation-level instrumentation should also actuate the filtration system.
h.
A seismic Category I makeup system should be provided to add coolant to the pool. Appropriate redundancy or a backup system for filling the pool from a reliable source, such as a lake, river, or onsite seismic Category I water-storage facility, should be provided.
If a backup system is used, it need not be a permanently installed system.
The capacity of the' makeup systems should be such that water can be supplied at a rate determined by consideration of the leakage rate that would be expected as the result of damage to the fuel storage pool from the dropping of loads, from earthquakes, or from missilec i
originating in high winds.
Attachment No. 1 Page 5 of 5
Response
a.
The design of the facility is described in the SAR,Section I-6.1.1.8, and Lection X-5.5, page X-5-3.
b.
The design of the fuel storage pool is such that tornadic ginds and missiles generated by these winds should not cause significant loss of watertight integrity of the fuel storaga pool. The wall panels and girts on the reactor building are designed to fail at 75 PSF. This pressure may act in either direction (in or out).
Special shear bolts are used to insure this failure. The design i
pressure for structures in this region is 30 PSF. A discussion of wind and tornado loading on the spent fuel storage facility is con-tained in SAR Section XII-2,3.3.1 and Amendment 9 as a response to part C of question 12.17.
c.
When the crane selector switch is on the " restricted" mode the crane can only be operated within the predetermined restricted boundary.
A diagram of the path of restricted movement is included in FSAR Amendment 33.
With the crane selector switch on " normal", the crane can be operated throughout the refueling floor.
d.
The Reactor Building Ventilation system is described in the SAR for Cooper Nuclear Station Sections X-10.3.3.3 and VII-12.5.
The description of the fuel pool design is included in Section X-3.4 of the SAR. The fuel pool cooling and demineralizer system is described in Volume IV Section X-5.0 of the SAR.
e.
1.
The movement of cranes over the vicinity of the fuel pool is discussed in the response to question c,.above.
2.
A description of the dual load path hoisting system is included in the FSAR, Amendment No. 33, Sections 1, 2, 3, 4 and 5.
3.
Pool design information was provided in FSAR Amendment No. 11
)
as a response to Question No.'10.1.
Crane movement is discussed in question "c" above.
f.
Systems for maintaining water quality and quantity are discussed in the SAR, Sect ion X-5.0.
g.
Monitoring equipment in the fuel storage pool is discussed in the SAR, Section X-3.0.
h.
Descriptions of the fuel pool makeup system is included in the SAR Section X-5.5.
Additional information on long term makeup water supplies was pro ded in FSAR Amendment No. 11 as a response to Question No. 10.4 4
e.
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COOPER NUCLEAR STATION OPERATIONS MANUAL Attachment No. 2
~
FC L HANDLING AND ACCOUNTABILITY PROC.-
3.7 SPENT FUEL H/J:DLI!*C A'?D SHIPPII:G 1.
PURPOSE to provide a detailed procedure to prepare and ship spent fuel off-site.
II.
h~ISCUSSION Spent irradiated fuel poses a radiation hazard and must be handled accord-ingly. Extreme distance or shielding is required to protect personnel from unnecessary radiation exposure. For this reason, spent fuel is handled at a specified minimum distance under water in the fuel storage pool.
Spent fuel will be shipped in a shielded container (cask) weighing up to 70 tons and holding up to 18 BUR fuel bundles. An empty spent fuel shipping cask will arrive at the site by truck / railroad car, located under the equip-ment access hatch, and hoisted to the refueling floor. The cask is then lowered into the spent fuel storage pool, loaded with spent fuel, and de-contaminated. The loaded shipping container (cask) is removed from the Reactor Building in the reverse order that it entered. All movements are t
wit'ain the restricted path.
III. REFERENCE MATERIAL
(
A.
Fuel Handling Procedure 3.1: Special Nuclear Materials Control.
B.
Operating Instructions for IF 300 Irramiated Fuel Shipping Cask; General Electric Document CEI-92817A.
IV.
PREREQUISITES, A.
All personnel performing the fuel handling are knowledgeable and ex-perienced in the usage of the equipment.
B.
The reactor crane shall be inspected using Procedure 7.2.32.
C.
Tag boards are available on the refueling floor and in the Control Room to display the current fuel location.
D.
All personnel in contact with fuel operations shall wear a film badge and dosimeter inside their protective clothing.
E.
Personnel assigned to fuel handling have bean instructed in radiation and criticality control procedures.
F..A limited access area is establ'shed around the spent fuel storage pool.
All loose and unnecessary mater. 1 and equipment are removed from this' area.
Revised Ey/Date Reviewed By/Date Approv,ed By/Date Rev.
Procedure Page 1
D.'Sadsrlin 5/12/77 C. Horn 6/14/77 4
3.7 Of 5 Pages
^
gf._/r ry
~
Attachment No. 2 G.
The Reactor Building crane shall be operated using Procedure 7.6.1.
H.
All decontamination equipment and facilities are operational.
1.
The refueling zone ventilating system is in service.
J.
The RPV head holding pedestals are removed from the essk decontamination area.
5 V.
LIMITATIONS A.
Technical Specifications.
1.
Section 3.2.D - Radiation Monitoring and Isolation;.
2.
Section 3.7 - Containment System.
3.
Section 3.10 - Spent Fuel Cask Handling.
4.
Section 5.5 - Fuel Storage.
B.
Administrative.
1.
The following requirements must be met under Facility Operating
. License No. DPR-46:
a.
Access to the fuel handling area on the refueling floor and to
(
the overhead bridge crane, when fuel handling is in progress, will be permitted only to authorized personnel.
i b.
All transfers of fuel must be in accordance with Procedure 3.1, Special Nuclear Material Accountability.
2.
Refer to Administrative Procedure 1.4.7:
Ecy Cout col and Mainten-ance Procedure 7.6.1:
Operation of Reactor Hu1Jdt.ng Crane for une of the crane in the key locked restrict mode f or fuel cask move-ments.
3.
No more than one fuel bundle should be suspended above the fuel storage array and this at a height no greater than 24 inches to limit penetration displacement if the bundle was dropped.
4.
Fuel handling in the fuel storage area should be '!nited to one fuel assembly or the weight equivalent per crane. An exception to this requirement is a properly designed fuel shipping container or overload test weight. The shipping container or overload test weight should at no time be suspended above the fuel storage array.
5.
Surveillance _Prscedure 6.3.10.10 shall be completed prior to VII.
A.6 of this procedure.
l k
2 Procedure Number 3.7 Date N',
Rcvision __4 Page 2 of.
5 Page.4 L.
No. 2 A2tachment VI.
PRECAUTIONS.*
[
A.
Irradiated fuel rods contain fission gases under pressure. The cladding may also be weakened af ter exposure to the reactor environment. There-fore, all handling of irradiated fuel cust be performed wi,th the greatest of care.
k.
Equipment used underwater in the spent fuel storage pool is " subject to radioactive contamination in verying degrees. Established radiation monitoring and protective measures will be strictly observed to avoid personnel contamination during operation of the equipment.
C.
Undue force or careless handling practices which might cause inadvertent radiation exposure or damage to fuel or equipment muct be avoided.
D.
Special care must be taken to prevent any material from falling into the spent fuci storage pool. Good housekeeping practices must be observed both for cicanliness and removal of all loose and unnecessary material.
In addition, personnel on the refueling floor shall have no loose material in their pockets or in their possession. ' Radiation monitoring badges and pencils shall be taped in place as well as being mechanically fastened to the clothing.
E.
When placing the cask in the spent fuel storage pool, do not suspend it over any fuel. Do not leave the cask suspended over the pool' longer than necessary.
l(
F.
Whenever the fuel cask is being moved above the 931' level of Reactor Building, the " Restricted Mode" of crane operation shall be in service.
C.
The fuel cask shall never be over 6" off the refueling floor except to set it on the Decontamination Pad.
H.
Spent fuel casks weighing in excess of 140,000 pounds shall not be handled.
i I.
All personnel shall be aware of Procedurn 5.3.5, " Refueling Floor High Radiation".
VI
I. PROCEDURE
Note:
Because of the many different types of fuel shipping casks, shipment of channels, etc. a special procedure will be written to provide a detailed proce ask movement.
,y g, g Caution: Ensure that the RPV head holding pedestals are removed from cask decontamination area.
A.
Moving the Spent Fuel Shipping Cask Into the Fuci Pool.
1.
Inspect the cask for damage and operability of all its component parts and wash off the road filn from the cask and trailer / car.
Procedure Number 3.7 Date 6';""
! Revision 4 __ __
Page 3 of _5_
Pages l
Attachment No. 2 2.
Back,the truck / rail car containing the horizontally mounted fuci shipment cask into the Reactor Building through the railroad air
((
lock. Remove the cask hold-down bolts.
3.
Using the Reactor Building crane and the lif ting yoke provided, pivot the cask to the vertical position by picking up the weight with the crane.
4.
Complete Surveillance Procedure 6.3.10.10.
CAUTION ALL CASK HANDLING ABOVE THE 931' LEVEL OF THE REACTOR BUILDING WILL BE DONE IN THE " RESTRICTED MODE" WHICH WILL CONFINE MOVEMENT TO THE CASK CONTROLLED PATH AS "MOUN IN ATTACHMENT "A".
5.
Place the Reactor Building crane in the "Restricte'd Mode" using the key operated selector switch prior to the tiac the cask reaches the 931' level.
Note: If during fuel cask movement an equipment failure prevents operation in the " Restricted Mode" movement of the fuel cask is permitted,as necessary to get the cask to the closest acceptable stable location.
i 6.
Set the cask down in the decontamination area on the refueling floor, unbolt and remove the cask lid and remove the cask plug.
Check radiation and contamination levels inside cask and decon-(
taminate as necessary.
CAUTION WHEN PLACING THE CASK IN THE SPENT FUEL STORACE POOL, IT SHALL DE SUSPENDED ONLY OVER THE SPENT TUEL CASK STORACE LOCATION. IT SHALL NOT BE SUSPENDED OVER ANY FUEL. DO NOT LEAVE CASK SUSPENDED OVER THE POOL LONCER THAN NECESSARY.
CAUTION THE SPENT FUEL CASK SHALL NOT BE RAISED ABOVE THE REFUELING FLOOR IN EXCESS OF 6" EXCEPT IT MAY BE RAISED TO A HEIGHT OF S 3' FOR INSPECTION IN THE DECONTAMINATION AREA.
Note: All leakers must be placed in encapsulation cans ;mfore entering the cash.
7.
Use the telescoping fuel grapple of the refueling platform to load the cask with those spent fuel bundles specified on a Special Nu-cicar Materials Transf er Form (See Procedure 3.1).
8.
Using the lif ting yoke and the Reactor Building crane, lower the cask plug into the cask cavity. Engage the lifting device.
Procedure Number 3.7~
Date (. t "
Revision 4 Page 4 of 5
Pages
Attac.hment No. 2 B.
Moving the Spent Fuel Shipping Cask Out of the Building.
Place the Reactor Building crane in the " Restricted Mode" ush.g the l(
l.
key operated selector switch.
Note:
1.
If during fuel cask covement an equipeent failu're prevents of th6 fuel operation in the " Restricted Mode" covement cask is permitted as necessary to get the cask to:the i
closest acceptable stable location.
A Special Nuclear Material Transfer form cust be executed in 2.
accordance with Procedure 3.1 when transferring a cask con-taining spent fuel.
raise the 2.
Using the lif ting yoke and the Reactor Building crane, loaded cask from the fuel storage pool. Perform a radiation survey and wash the cask down with demineralized water chile lif ting.
3.
Position the cask in the decontamination area.
Flush the cavity with decineralized water, sample for activity and 4.
If there is any indication of a leaking perform a radiation survey.
fuel bundle, the cask must be returned to the pool and the associated fuel bundle removed. Known leakers must be shipped in the defective fuel storage containers. Decontaminate ex*.ernal surface of the cask and survey until within shipping limits.
Detergents may also be used in the cask external decontamination
((
Note:
process to reduce the radioactive contamination of the cask to within the legal limits required prior to forwarding to commercial carriers.
Af ter the cask has reached a point of tcoperature equilibrium and the 5.
contamination of the externals is within shipping limits, bolt the cask lid in place.
Using the Reactor Building crane and the lifting yoke, lower the cask 6.
to the truck / railroad car, pivot it to the horizontal position and attach the cask hold-down bolts to secure it in place.
7.
Perform a final radiation survey.
After appropriate shipping paper 4 are prepared (FHP 3.1) required 8.
labels and placards are placed ou cash and truck / railroad car, and all shipping licenses are fulfil.'.ed, remove the cask from the Reactor Building.
VIII. ATTACHMENTS A.
Horizontal Controlled Path of Spent Fuel Cask.
MBA Transfer Forn (Figure 5 of Procedure 3.1).
B.
(
Procedurc Number 3.7 Date f-b~
~8 Revision 4
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GENERAL OFFICE
" ^ " " '
Nebraska Public Power District
" fE"%'RE7aWOf%^i E
c=..-
=
-. = _
July 10, 1978
~
~
Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Muclear Regulatory Commission Wash.ngton, DC 20555
Subject:
Movement of Heavy Loads Near the Spent Fuel Facility -
Request for Information Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Dear Mr. Stello:
In your letter dated May 17, 1978 you requested the Nebraska Public Power District to provide additional int'ormation regarding the movement of heavy loads near the spent fuel facility.
This letter transmits the information requested as Attachment 1. contains the procedure for the movement of the fuel casks at Cooper Nuclear Station.
As you requested, the District has reviewed its current procedures for the movement of heavy loads over spent fuel and has concluded that the potential for a handling accident which could result in damage to spent fuel is at a minimum.
Should you have any questions or desire additional information, please contact me.
In addition to one signed original, 39 copies of this informatien are also submitted for your use.
Sincerely yours, LA4 -
Ja.. Pilant Director of Licensing and Quality Assurance JDW/cmk Attachment
Victor Stallo, Jr.
July 10, 1978 Page 2 STATE OF NEBRASKA )
) ss PLAITE COUNTY
)
l JayEM. Pilant, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a
public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this information on behalf of Nebraska Public Power District; and that the statements in said application are truri to the best of his knowledge and belief.
M Q ay M. Pilsnt inth Subscribed in my presence and sworn to before me this
///
day of July, 1978.
[NOTARYPUBLIC Ny C-1ss1on e,1res /fd. #, /9/O 8 SINERAL NOI42T - State W Nekssha T
MARILYN R. t40HNDOM h My Comm. Eso, oct. 14,1900 l
Attachment No. 1 l
Page 1 of 5 Question No. 1
-Provinc a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the
- refueling floor.
Sesponse o
FSAR ' drawings XII-2-6, 2-7, and 2-8 illustrate the physical relation between the reactor. core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas.
Question No. 2 Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool. For each object listed, provide its approximate weight and size, a diagram of i
the movement path utilized (including carrying height) and the frequency of movement.
Response
The only object which is required to be moved over the reactor core (during refueling), or the spent fuel storage pool is the refueling platform which is on rails on either side of the cavities. Movement of the fuel cask is interlocked to include only that area of the spent fuel storage pool directly over the fuel cask storage area. The fuel cask does not move over the spent fuel racks. Discussion of the fuel cask physical dimensions and handling has been submitted in FSAR Amendment No. 33, sections 5.0 and 6.0, respectively.
1 Question No. 3 What are the dimensions and weights of the spent fuel casks that are or will be used at your facility.
l
Response
i Dimensions and weights of the spent fuel cask were submitted in FSAR
-Amendment No. 33 and is described in paragraph 5.1.
l
- Question No. 4 Identify any heavy load or cask drop analyses performed to date for your
. facility. Provide a copy of all such analyses not previe.usly submitted
- to the NRC staff.
Response
A cask drop analyses has been previously submitted, FSAR Amendment No. 11, response to question No. 10.1.
d -
i
+-
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~.
Attachment No. 1 Page 2 of 5 Question No. 5 Identify any heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved.
Identify what: equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc.) and discuss the feasibility of such an accident affecting this equipment. Describe the r
{ basis for your conclusions.
Response
Heavy loads are not carried over equipment required for the safe shutdown of the plant.
Question No. 6 If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to j
uncover the spent fuel. Describe the basis for your conclusions.
i
Response
The spent fuel cask drop analyses was submitted in FSAR Amendment No. 11 (Question No. 10.1).
No other heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at Cooper Nuclear i
Station.
1 question No. 7 4
I Describe any design features of your facility which affect the potential for a heavy load handling accident involving spent fuel, e.g.,
utilization of a single failure-proof crane.
Response
.The design features which affect the potential for a heavy load handling accident involving ~ spent fuel is discussed in FSAR Amendment No. 33, Sections 1.0, 2.0, 3.0 and 4.0.
Question No. 8 Provide copies of all procedures currently in effect.at your facility for.
the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment ~ required for the safe shutdown of a
- plant that is operating at the time.the move occurs.
Response
Administrative procedures insure that heavy loads are not transported over the exposed reactor core during refueling. Procedures that govern the removal of heavy objects from directly above the core (I.e. shield plugs, l
Attachment No. 1 Page 3 of 5 drywell head, etc.) before the core is uncovered, insure that these objects do not pass over the reactor cavity or fuel pool cavity. These procedures are available at Cooper Nuclear Station for review. The only heavy load to be carried over a portion of the spent fuel storage pool will be the fuel cask which is interlocked to include only that area of the spent fuel storage pool directly over the fuel cask storage area.
p The procedure for the preparation and shipment of spent fuel is discussed O
in Attachment "2".
No heavy loads are carried over equipment required for safe shutdown of the plant while the plant is operating.
Question No. 9 Discuss the degree to'which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December, 1975) regarding Spent Fuel Storage Facility Design Basis.
a.
The spent fuel storage facility (including its structures and equipment except as noted in paragraph f below) should be designed to Category I seismic requirements.
L.
The facility should be designed (a) to keep tornadic winds and missiles generated by these winds from causing significant loss of water tight integrity of the fuel storage pool and (b) te keep missiles generated by tornadic winds from contactian fuel within the pool.
c.
Interlocks should be provided to prevent cranes from passing over stored fuel (or near stored fuel in a manner such that if a crane failed, the load could tip over on stored fuel) when fuel handling is not in progress. During fuel handling operations, the interlock may be bypassed and administrative control used to prevent the crane from carrying loads that are not necessary for fuel handling over the stored fuel or _other prohibited areas. The facility should be designed to minimize the need for bypassing such interlocks.
d.
A controlled leakage building should enclose the fuel pool. The building should be equipped with an appropriate ventilation and filtration system to limit the potential release of radic...ve iodine and other radioactive materials. The building need not be designed to withstand ~ extremely high winds, but leakage should be suitably controlled during refueling operations. The design of the ventilation and filtration system should be based on the assumption that the cladding of all of the fuel rods in one fuel bundle might be 2 breached. The inventory of radioactive materials available for leakage from the building should be based on the assumptions given in Regulatory Guide 1.25,'" Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water
~
Reactors" (Safety Guide 25).
-,+.
~
AttachmentsNo. 1 Page 4 of e.
The spent fuel s.orage facility should have at least one of the following provisions with respect to the handling of heavy loads, including the refueling cask:
1.
Cranes capable of carrying heavy loads should be prevented, preferably by design rather than by interlocks, from moving
[
into the vicinity of the pool.
2.
Cranes should be designed to provide single-failute-proof handling of heavy loads, so that a single failure will not result in loss of capability of the crane-handling system to perform its safety function; or 3.
Die fuel pool should be designed to withstand, without leakage that could uncover the fuel, the impact of the heaviest load to be carried by the crane from the maximum height to which it can be lifted. If this approach is used, design provisions should be made to prevent the crane, when carrying heavy loads, from moving in the vicinity of stored fuel.
f.
Drains, permanently connected mechanical or hydraulic system, and other features that by maloperation or failure, could cause loss of coolant that would uncover fuel should not be installed or included in the design. Systems for maintaining water quality and quantity should be designed so that any maloperation or failure of such systems (including failures resulting from the Safety Shutdown Earthquake) will not cause fuel to be uncovered. These' systems need not otherwise meet Category 1 seismic requirements.
g.
Reliable and frequently tested monitoring equipment should be provided to alarm both locally and in a continuously manned location if the water level in the fuel storage pool falls below a predetermined level or if high local-radiation levels are experienced. The high-radiation-level instrumentation should also actuate the filtration system.
h.
A seismic Category I makeup system should be provided to add coolant to the pool. Appropriate redundancy or a backup system for filling the pool from a reliable source, such as a lake, river, or onsite seismic Category I water-storage facility, should be provided. If a backup system is used, it need not be a permanently installed system.
The capacity of the makeup systems should be such that water can be supplied at a rate determined by consideration of the leakage rate that would be expected as the result of damage to the fuel storage pool. from the dropping of loads, from earthquakes, or f rom missiles r
originating in high winds.
1 J
Attachment No. 1 Page 5 of 5
Response
The design of the facility is described in the SAR. Section 1-6.1.1.8, I
a.
and Section X-5.5, page X-5-3.
i
[
b.
The design of the fuel storage pool is such that tornadic winds and g
missiles generated by these winds should not cause signific~ ant loss of watertight integrity of the fuel storage pool. The wall panels and girts on the reactor bailding are designed to fail at 75 PSF. This pressure may act it. either direction (in or out).
Special shear bolts are used to insure this failure. The design pressure for structures in this region is 30 PSF.
A discussion of wind and tornado loading on the spent fuel storage facility is con-tained in SAR Section XII-2.3.3.1 and Amendment 9 as a response to part C of question 12.17.
t When the crane selector switch is on the " restricted" mode the crane c.
can only be operated within the predetermined restricted boundary.
A diagram of the path of restricted movement is included in FSAR Amendment 33.
With the crane selector switch on " normal", the crane can be operated throughout the refueling floor.
d.
The Reactor Building Ventilation system is described in the SAR for Cooper Nuclear Station, Sections X-10.3.3.3 and VII-12.5.
The description of the fuel pool design is included in Section X-3.4 of the SAR. The fuel pool cooling and demineralizer system is described in Volume IV, Section X-5.0 of the SAR.
1 e.
1.
The movement of cranes over the vicinity of the fuel pool is discussed in the response to question c, above.
2.
A description of the dual load path hoisting system is included in the FSAR, Amendment No. 33, Sections 1, 2, 3, 4 and 5.
- 3.. Pool design information was provided in FSAR Amendment No. 11 as a response to Question No. 10.1.
Crane movement is discussed in question "c" above, i
f.- Systems for maintaining water quality and quantity are discussed in the SAR, Section X-5.0.
g.
Monitoring equipment in the fuel storage pool is discussed in the SAR, Section X-3.0.
- h. ' Descriptions of the fuel pool makeup system is included in the SAR Section X-5.5.
Additional information on long term makeup water supplies was provided in FSAR Amendment No. Il as a response to Question No. 10.4.
l
COOPER NUCLEAR STATION CPERATIONS MANUAL Attachment No. 2 FCIL HANDL'ING AND ACCOUNTABILITY PROC.
3.7 SPENT FUEL IU.MDLI!*C AND SHIPPIMC I.
PURPOSE io provide a detailed procedure to prepare and ship spent fuel off-site.
fISCUSSION II.
Spent irradiated fuel poses a radiation hazard and must be handled accord-
-ingly.
Extreme distance or shielding is required to prettet personnel from unnecesse y radiation exposure. For this reason, spent fac1 is handled at a specifiad minimum distance under water in the fuel stcrage pool.
Spent fuel will be shipped in a shielded container (cask) weighing up to 70 tons and holding up to 18 EUR fuel bundles. An empty spent fuel shipping a
cask will arrivo at the site by truck / railroad car, located under the equip-ment access hatch, and hoisted to the refueling floor. The cask is then lowered into the spent fuel storage pc,ol, loaded with spent fuel, and de-contaminated. The loaded shipping co tainer (cask) is removed from the Reactor Building in the reverse order that it entered. All movements are within the restricted path.
III. REFERENCE MATERIAL
(
A.
Fuel Handling Procedure 3.1: Special Nuclear Materials Control.
B.
Operating Instructions for IF 300 Irra lated Fuel Shipping Cask; General Electric Document GEI-92817A.
IV.
PREREQUISITES, A.
All personnel performing the fuel handling are knowledgeable and ex-perienced in the usage of the equipment.
B.
The reactor crane shall be inspected uving Procedure 7.2.32.
C.
Tag boards are available on the refueling floor and in the Control Room to display the current fuel location.
D.
All personnel in contact with fuel operations shall waar a film badge and dosimeter inside their protective c'lothing.
E.
Personnel assigned to fuel handling have been instructed in radiation and criticality control procedures.
F.
A limited access area is estab] 'shed around the spent fucI storage pool.
All loose and unnecessary mater il and equipment are removed from this area.
(
.hvised Sy/Date Reviewed By/Date Approv,ed By/Date Rev.
Procedure Page 1
-D. Sedsrlin 5/12/77 G. Horn 6/14/77 4
3.7 Of-Pages
^
5 6.. w n
Attabhment No. 2 C.
The Reactor Building crane shall be operated using Procedure 7.6.1.
H.
All decontamination equipment and facilities are operational.
1.
The refueling zone ventilating system is in service.
J.
The RPV head holding pedestals are removed from the cask decontamination area.
y 4
V.
LIMITATIONS A.
Technical Specifications.
1.
Section 3.2.D - Radiation Monitoring and Isolation;.
2.
Section 3.7 - Containment System.
3.
Section 3.10 - Spent Fuel Cask Handling.
4.
Section 5.5 - Fuel Storage.
B.
Administrative.
1.
The following requirements must be met under Facility Operating License No. DPR-46:
r a.
Access to the fuel handling area on the refueling floor and to
- (
the overhead bridge crane, when fuel handling is in progress, will be permitted only to authorized personnel.
' i b.
All transfers of fuel must be in accordance wit'a Procedure 3.1, Special Nuclear Material Accountability.
2.
Refer to Administrative Procedure 1.4.7:
Key cont ot and Mainten-ance Procedurc 7.6.1:
Operation of Reactor liuflJ.;ag Crane for use of the crane in the key locked restrict mode f or riel cask move ~
ments.
3.
No more than one fuel bundle should be suspended above the fuel storage array and this at a height no greater than 24 inches to limit penetration displacement if the bundle was dropped.
4.
Fuel handling in the fuel storage area should be ' nit 0<! to one fuel assembly or the weight equivalent pec crane. An exception to this requirement is a properly designed fuel shipping container or overload test weight. The shipping container or overload test weight should at' no time _ be suspended above the fuel storage array.
5.
Surveillance Procedure 6.3.10.10 shall be completed prior to VII.
A.6 of this procedure.
-'~ -N" Procsdure-Number 3.7 Date _
Revision _,,4 Page 2 of 5
Pages
A2 tac.hment No. 2 VI.
PRLCAUTIONS A.
Irradiated fuel rods contain fission gases under pressure. The cladding There-may also be weakened af ter exposure to the reactor environrent.
fore, all handling of irradiated fuel must be performed with. the greatest of care.
6.
Equipment used underwater in the spent fuel storage pool is subject to
[
radioactive contacination in verying degrees. Established radiation monitoring and protective measures will be strictly observed to avoid personnel contamination during operation of the equipment.
C.
Undue force or careless handling practices which might cause inadvertent radiation exposure or damage to fuel or equipment cuct be avoided.
D.
Special care. must be taken to prevent any material from falling into the spent fuel storage pool. Good housekeeping practices must be observed both for cleanliness and removal of all loose and unnecessary material.
In addition, personnel on the refueling floor shall have no loose material in their pockets or in their possession. Radiation monitoring badges and pencils shall be taped in place as weil as being mechanically fastened to the clothing.
E.
When placing the cask in the spent fuel storage pool, do not suspend it over any fuel. Do not leave the cask suspended over the pool' longer than necessary.
F.
Whenever the fuel cask is being moved above the 931' level of Reactor l(
Building, the " Restricted Mode" of crane operation shall be in service.
C.
The fuel cask shall never be over 6" off the refueling floor except to set it on the Decontamination Pad.
H.
Spent fuel casks weighing in excess of 140,000 pounds shall not be handled.
I.
All personnel shall be aware of Procedurc 5.3.5, " Refueling Floor High Radiation".
VI
I. PROCEDURE
Note: Because of the many different types of fuel shipping casks, shipment I
of channels, etc. a special procedure will be written to provide a detailed procedure for cask movement.
Caution: Ensure that the RPV head holding pedestals are removed from cask f
decontamination area.
A.
Moving the Spent Fuel Shipping Cask Into the Fuel Pool.
1.
Inspect the cask for damage and operability of all its component parts and wash of f the road filn from the cask and trailer / car.
(
Procedure Number 3.7 Date 6 1;
! Revision 4___
Page 3 of 5_
Pages I
Attachment No. 2 2.
Back,the truck / rail car containing the horizontally counted fuel shipment cask into the Reactor Building through the railroad air lock. Remove the cask hold-down bolts.
((
3.
Gains the Reactor Building crane and the lif ting yoke provided, pivot the cask to the vertical position by picking up the weight with the crane.
[
4.
Complete Surveillance Procedure 6.3.10.10.
~
CAUTION ALL CASK HANDLING ABOVE THE 931' LEVEL OF THE REACTOR BUILDING WILL BE DONE IN THE " RESTRICTED MODE" WHICH WILL CONFINE MOVEMENT TO THE CASK CO.VrROLLED PATH AS SHOWN IN ATTACHMENT "A".
5.
Place the Reactor Building crane in the " Restricted Mode" using the key operated selector switch prior to the time the cask reaches the 931' level.
Note: If during fuel cask movement an equipment failure prevents operation in the " Restricted Mode" movement of the fuel cask is permitted,as necessary to get the cask to the closest acceptable stable location.
6.
Set the cask down in the decontamination area on the refueling floor, unbolt and remove the cask lid and remove the cask plug.
Check radiation and contamination icvels inside cask and decon-(
taminate as necessary.
CAUTION WHEN PLACING THE CASK IN THE SPENT FUEL STORACE POOL, IT SHALL DE SUSPENDED ONLY OVER THE SPENT TUEL CASK STORAGE LOCATION. IT SHALL
- NOT BE SUSPENDED OVER ANY FUEL. DO NOT LEAVE CASK SUSPENDED OVER THE POOL LONCER THAN NECESSARY.
CAUTION
.THE SPENT FUEL CASK SHALL NOT BE RAISED ABOVE THE REFUELING FLOOR IN EXCESS OF 6" EXCEPT IT MAY BE RAISED TO A HEIGHT OF % 3' FOR INSPECTION IN THE DECONTAMINATION AREA.
Note: All leakers must be pinced J n encapsulation c.tus ;,efore entering the cask.
7.
Use the telescoping fuel grapple of the refueling platform to load the cask with those spent fuel bundles specified on a Special Nu-clear Materials Transfer Form (See Procedure 3.1).
8.
Using the lif ting yoke and the Reactor Building crane, lower the cask plug into the cask cavity. Engage the lifting device.
Procedure Number. - 3. 7 -
Date (
1" Revision 4 Page 4 o f __5 Pages l
l e -
Attachment No. 2 B.
Moving the Spent Fuel Shipping Cask Out of the Building.
Place the Reactor Building crane in the " Restricted Mode" using the
(
1.
key operated selector switch.
Note:
1.
If during fuel cask covecent an equipcent failu're prevents operation in the " Restricted Mode" covement of the fuel cask is permitted as necessary to get the cask to-the closest acceptable stable location.
h.
A Special Nuclear Material Transfer form must be executed in 2.
accordance with Procedure 3.1 when transferring a cask con-taining spent fuel.
Using the lif ting yoke and the Reactor Building crane, raise the 2.
loaded cask from the fuel storage pool. Perform a radiation survey and wash the cask down with denineralized water while lif ting.
3.
Position the cask in the decontamination area.
Flush the cavity with domineralized water, sample for activity and 4.
If there is any indication of a leaking perform a radiation survey.
fuel bundle, the cask must be returned to the pool and the associated fuel bundle removed. Known leakers must be shipped in the defective fuel storage containers. Decontaminate external surface of the cask and survey until within shipping limits.
Detergents may also be used in the cask external decontamination
((
Note:
process to reduce the radioactive contamination of the cask to i
within the legal limits required prior to forwarding to commercial carriers.
After the cask has reached a point of temperature equilibrium and the 5.
contamination of the externals is within shipping limits, holt the cask lid in place.
6.
Using the Reactor Building crane and the lif ting yoke, lower the cask to the truck / railroad car, pivot it to the horizon al position and attach the cask hold-down bolts to secure it in place.
7.
Perform a final radiation survey.
Af ter appropriate shipping papers are prepared (FhP 3.1) required 8.
labels and placards are placed on cask and truck / railroad car, and all shipping licenses are fulfilled, resove the cask from the Reactor Building.
VIII. ATTACHMENTS A.
Horizontal Controlled Path of Spent Fuel Cask.
B.
- SA Transfer Form (Figure 5 of Prot - dure 3.1).
(
Revision 4
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H Nebraska Public Power District GENERAL OFFICE
" ?El'E%'nCos'0M"*>"' '"
- July 10, 1978 T
i-Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Subj ect: Movement of Heavy Loads Near the Spent Fuel Facility -
Request for Information Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Dear Mr. Stello:
In your letter dated May 17, 1978 you requested the Nebraska Public Power District to provide additional information regarding the movement of heavy loads near the spent fuel facility.
This letter transmits the information requested as Attachment 1. contains the procedure for the movement of the fuel casks at Cooper Nuclear Station.
As you requested, the District has reviewed its current procedures for the movement of heavy loads over spent fuel and has concluded that the potential for a handling accident which could result in damage to spent fuel is at a minimum.
Should you have any questions or desire additional information, please contact me.
In addition to one signed original, 39 copies of this information are also submitted for your use.
Sincerely yours, lab Ja, d. Pilant Director of I.icensing and Quality usurance JDW/cmk Attachment w
Victor Stello, Jr.
July 10, 1978 Page 2 STATE OF NEBRASKA )
) ss PLAITE COUNTY
)
~
Jay M. Pilant, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this information on behalf of Nebraska Public Power District; and that the statements in said application are true to the best of his knowledge and belief.
M Q ay M. Pilant Subscribed in my presenco. and sworn to before me this
((
day of July, 1978.
[NOTARYPUBLIC My Commission expires /
!/
81 bit 4L A0718Y State al Beersehe MARILYN R. HOHNDOFF w comm. Ess. oct. t 4.1ses r
4 4
Attachment No. 1 Page 1 of 5 Question No. 1 Provide a diagram which illustrates the physical relation between the reac*or core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.
dResponse
=
FSAR drawings XII-2-6, 2-7, and 2-8 illustrate the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas.
Question No. 2 Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel. storage pool. For each object listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying height) and the frequency of movement.
Response
The only object which is required to be moved over the reactor core (during refueling), or the spent fuel storage pool is the refueling platform which is on rails on either side of the cavities. Movement of the fuel cask is interlocked to include only that area of the spent fuel storage pool directly over the fuel cask storage area.
The fuel cask does not move over the spent fuel racks. Discussion of the fuel cask physical dimensions and handling has been submitted in FSAR Amendment No. 33, sections 5.0 and 6.0, respectively.
_uestion No. 3 Q
What are the dimensions and weights of the spent fuel casks that are or will be used at your facility.
Response
l Dimensions and weights of the spent fuel cask were submitted in FSAR Amendment No. 33 and is described in paragraph 5.1.
Question No. 4 Identify any heavy Irad or cask drop analyses performed to date for your
- facility. Provide a copy of all such analyses not previously submitted to the NRC staff.
Response
A cask drop analyses has been previously submitted, FSAR Amendment No. l!,
response to question No. 10.1.
I
Attachment No. 1 Page 2 of I r
Question No. 5 Identify'any heavy loads that'are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved.
Identify what equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc.) and discuss tQe i
p feasibility'of such an accident affecting this equipment. Describe the basis for your conclusions.
I
Response
4 Heavy loads are not carried over equipment required for the safe shutdown of the plant.
7 Question No. 6 If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to uncover the spent fuel. Describe the basis for your conclusions.
Response
+
i The spent fuel cask drop analyses was submitted in FSAR Amendment No. 11 (Questien No. 10.1).
No other heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at Cooper Nuclear Station.
Question No. 7
. Describe any. design features of your facility which affect the potential for a heavy load' handling accident involving spent fuel, e.g.,
utilization of a single failure-proof crane.
Response
The design features which affect the potential for a heavy load handling accident involving spent fuel is discussed in FSAR Amendment No. 33, Sections 1.0, 2.0, 3.0 and 4.0.
Question No. 8 Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a
~
- plant that is operating at the time the move occurs.
1
Response
Administrative procedures insure that heavy loads are not transported over the exposed reactor core during refueling. Procedures that govern the removal of heavy objects from directly above the core (i.e. shield plugs, 4
.. ~.
~
Attachment No. 1 4
Page 3 of 5 drywell head, etc.) before the core is uncovered, insure that these objects do not pass over the reactor cavity or fuel pool cavity. These procedures are available at Cooper Nuclear Station for review. The only heavy load to be carried over a portion of the spent fuel storage pool will be the fuel cask which is interlocked to include only that area of i
the spent fuel storage pool directly' over the fuel cask storage area.
9 The procedure for the preparation and shipment of spent fuel Es discussed O
in Attachment "2".
No heavy loads are carried over equipment required for safe shutdown of the plant while the plant is operating.
Question No. 9 Discuss the degree to which your facility complies with the eight (8) l regulatory positions delineated in Regulator / Guide 1.13 (Revision 1 December, 1975) regarding Spent Fuel Storage Facility Design Basis, j
a.
The spent fuel storage facility (including its structures and equipment except as noted in paragraph f below) should be designed to 4
Category I seismic requirements.
b.
The facility should be designed (a) to keep tornadic winds and missiles generated by these winds from causing significant loss of water tight integrity of the fuel storage pool aad (b) to keep missiles generated by tornadic winds from contacting fuel within the pool.
c.
Interlocks should be provided to prevent cranes from passing over stored fuel (or near stored fuel in a manner such that if a crane failed, the load could tip over on stored fuel) when fuel handling is not in progress. During fuel handling operations, the interlock may be bypassed and administrative control used to prevent the crane from carrying loads' that are not necessary for fuel handling over the stored fuel or other prohibited areas. The facility should be designed to minimize the need for bypassing such interlocks.
J d.
A controlled leakage building should enclose the fuel pool. The building should be equipped with an appropriate ventilation and filtration system to limit the potential release of radioactive iodine and other radioactive materials. The building need not be designed to withstand extremely high winds, but leakage should be suitably controlled during refueling operations. The design of the ventilation and filtration system should be based on the assumption that the cladding of all' of the fuel rods in one fuel bundle might be breached. The inventory of radioactive materials available for leakage f rom the building should be based on the assumptions given in Regulatory Guide l.25, " Assumptions Used for Evaluating the Potential
' Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors" (Safety Guide 25).
c Attachment No. 1 Page 4 of 5 e.
.The spent fuel storage facility should have at least one of the following provisions with respect to the handling of heavy loads, including the refueling cask:
~
1.
Cranes capable of carrying heavy loads should be prevented, I
I preferably by design rather than by interlocks, from miving L
into the vicinity of the pool.
2.
Cranes should be designed to provide single-failure-proof handling of heavy loads, so that a single failure will not result in loss of capability of the crane-handling system to perform its safety function; or 3.
The fuel pool should be designed to withstand, without leakage that could uncover the fuel, the impact of the heaviest load to be carried by the crane from the maximum height to which it can be lifted. If this approach is used, design provisions should be made to prevent the crane, when carrying heavy loads, from moving in the vicinity of stored fuel.
f.
Drains, permanently connected mechanical or hydraulic system, and other features that by maloperation or failure, could cause loss of i
coolant that would uncover fuel should not be installed or included in f
the design. Systems for maintaining water quality and quantity should be designed so that any maloperation or failure of such systems (including failures resulting from the Safety Shutdown Earthquake) will not cause fuel to be uncovered. These systems need not otherwise meet Category'I seismic requirements.
g.
Reliable and frequently tested monitoring equipment should be provided to alarm both locally and in a continuously manned location if the water level in the fuel storage pool falls below a predetermined level or if high local-radiation levels are experienced. The high-1 radiation-level instrumentation should also actuate the filtration j
system.
h.
A seismic Category I makeup system should be provided to add coolant to the pool. Appropriate redundancy or a backup system for filling the pool from a reliable source, such as a lake, river, or onsite seismic Category I water-storage facility, should be provided. If a backup system is used, it need not be a permanently installed system.
The capacity of the makeup systems should be such that water can be supplied at a rate determined by consideration of the leakage rate that would be expected as the result of damage to the fuel storage pool from the dropping of loads, from earthquakes, or from missiles r
-originating in high winds.
4 L
. 0. I Page 5 of 5
Response
a.
the design of the facility is described in the SAR,Section I-6.1.1.8, and Section X-5.5, page X-5-3.
b.
The design of the fuel storage pool is such that tornadie qinds and L
missiles generated by these winds should not cause significant loss of watertight integrity of the fuel storage pool. The wall panels and girts on the reactor building are designed to fail at 75 PSF.
This pressure may act in either direction (in or out).
Special shear bolts are used to insure this failure. The design pressure for structures in this region is 30 PSF.
A discussion of wind and tornado loading on the spent fuel storage facility is con-tained in SAR Section XII-2.3.3.1 and Amendment 9 as a response to part C of question 12.17.
c.
When the crane selector switch is on the " restricted" mode the crane can only be operated within the predetermined restricted boundary.
A diagram of the path of restricted movement is included in FSAR Amendment 33.
With the crane selector switch on " normal", the crane can be operated throughout the refueling floor, d.
The Reactor Building Ventilation system is described in the SAR for Cooper Nuclear Station, Sections X-10.3.3.3 and VII-12.5.
The description of the fuel pool design is included in Section X-3.4 of the SAR.
The fuel pool cooling and demineralizer system is described in Volume IV, Section X-5.0 of the SAR.
e.
1.
The movement of cranes over the vicinity of the fuel pool is discussed in the response to question c, above.
2.
A description of the dual load path hoisting system is included in the FSAR, Amendment No. 33, Sections 1, 2, 3, 4 and 5.
3.
Pool design information was provided in FSAR Amendment No. 11 as a response to Question No. 10.1.
Crane movement is discussed in question "c" above, f.
Systems for maintaining water quality and quantity are discussed in the SAR, Section X-5.0.
g.
Monitoring equipment in the fuel storage pool is discussed in the SAR, Section X-3.0.
h.
Descriptions of the fuel pool makeup system is included in the SAR r
Section X-5.5.
Additional information on long term makeup water supplies was provided in FSAR Amendment No. 11 as a response to Question No. 10.4.
i 1
COOPER NUCLEAR STATION OPERATIONS MANUAL Attachment No. 2
.FUZ~ HANDL'ING AND ACCOUNTABILITY PROC.
3.7 SPENT FUEL HAMDLING AND SHIPPIMG J
I.
PURPOSE To provide a detailed proceduce to prepare and ship spent fuel off-site.
II.
IlSCUSSION Spent irradiated fuel poses a radiation hazard and must be handled accord-ingly. Extreme distance or shielding is required to protect personnel from unnecessary radiation exposure.
7or this reason, spent fuel is handled at a specified minimum distance under water in the fuel storage pool.
Spent fuel will be shipped in a shicided container (cask) weighing up to 70 tons and holding up to 18 BWR fuel bundles. An empty spent fuel shipping cask will arrive at the site by truck / railroad car, located under the equip-ment access hatch, and hoisted to the refueling floor. The cask is then lowered into the spent fuel storage pool, loaded with spent fuel, and de-contaminated. The loaded shipping container (cask) is removed from the Reactor Building in the reverse order that it entered. All movecents are within the restricted path.
III. REFERENCE MATERIAL l(
A.
Fuel Handling Procedure 3.1: Special Nuclear Materials Control.
B.
Operating Instructions for IF 300 Irra lated Fuel Shipping Cask; General Electric Document GEI-92817A.
IV.
PREREQUISITES A.
All personnel performing the fuel handling are knowledgeable and ex-perienced in the usage of the equipment.
B.
The reactor crane shall be inspected using Procedure 7.2.32.
C.
Tag boards are available on the refueling floor and in the Control Room to display the' current fuel location.
D.
All personnel in contact with fuel operations shall wear a film badge and dosimeter inside their protective clothing.
E.
Personnel assigned to fuel handling have been instructed in radiation and criticality control procedures.
F.
A limited access area is estab1 'shed around the spent fuel storage pool.
All loose and unnecessary mater.al and equipment are removed from this
~
-area.
I ascised Ey/Date Reviewed By/Date
.Approv,ed B,y/Date Rev.
Procedure Page 1
D. Scdsrlin 5/12/77' G. Horn 6/14/77
- ^
4 3.7 Of-5 Pages 6;. /f-9 ')
Attachment No. 2 C.
The Reactor Building crane shall be operated using Procedure 7.6.1.
H.
All decontamination equipment and facilities are operational.
1.
The refueling zone ventilating system is in service.
J.
The RPV head holding pedestals are removed from the cask decontamination I
area.
E V.
LIMITATIONS A.
Technical Specifications.
1.
Section 3.2.D - Radiation Monitoring and Isolation;.
2.
Section 3.7 - Containment System.
3.
Section 3.10 - Spent Fuel Cask Handling.
4.
Section 5.5 - Fuel Storage.
B.
Administrative.
1.
The following requirements must be met under Pacility Operating License No. DPR-46:
a.
Access to the fuel handling area on the refueling floor and to
(
the overhead bridge crane, when fuel handling is in progress, i
will be permitted only to authorized personnel.
b.
All transfers of fuel must be in accordance with Procedure 3.1, Special Nuclear Material Accountability.
2.
Refer to Administrative Procedure 1.4.7:
Key Cont col and Mainten-ance Procedure 7.6.1:
Operation of Reactor building Crane for une of the crane in the key locked restrict mode for riel cask move-ments.
3.
No more than one fuel bundle should be suspended above the fuel storage array and this at a height no greater than 24 inches to limit penetration displacement if the bundle was dropped.
4.
Fuel handling in the fuel storage area should be intted to one fuel assembly or the weight equivalent per crane. An exception to this requirenent is a properly designed fuel shipping container or overload test weight. The shipping container or overload test I
weight should at.no time be suspended above the fuel storage array.
5.
Surveillance Procedure 6.3.10.10 shall be completed prior to VII.
A.6 of this procedure.
' Procedure Number 3.7 Date
' ~ ' J 'l Revist on _4 Page 2 of 5
- Pager,
Attachment No. 2 VI.
PRECAUTIONS A.
Irradiated fuel rods contain fission gases under pressure. The cladding may also be weakened af ter exposure to the reactor environment. There-fore, all handling of irradiated fuel must be performed wi,th the greatest of care.
k.
Equipment used underwater in the spent fuel storage pool is'~ subject to radioactive contamination in verying degrees. Established radiation monitoring and protective measures will be strictly observed to avoid personnel contamination during operation of the equipment.
C.
Undue force or careless handling practices which might cause inadvertent radiation exposure or damage to fuel or equipment must be avoided.
D.
Special care must be taken to prevent any material from falling into the spent fuel storage pool. Good housekeeping practices must be observed both for cleanliness and removal of all loose and unnecessary material.
In addition, personnel on the refueling floor shall have no loose material in their pockets or in their possession. Radiation monitoring badges and pencils shall be taped in place as well as being mechanically fastened to the clothing.
E.
When placing the cask in the spent fuel. storage pool, do not suspend it over any fuel. Do not leave the cask suspended over the pool' longer than necessary.
l(
F.
Whenever the fuel cask is being moved above the 931' level of Reactor Building, the " Restricted Mode" of crane operation shall be in service.
G.
The fuel cask shall never be over 6" off the refueling floor except to set it on the Decontamination Pad.
H.
Spent fuel casks weighing in excess of 140,000 pounds shall not be handled.
1.
All personnel shall be aware of Procedurc 5.3.5, " Refueling Floor High Radiation".
VI
I. PROCEDURE
Note: Because of the many different types of fuel shipping casks, shipment of channels, etc. a special procedure will be written to provide a detailed procedure for cask movement.
Caution: Ensure that the RPV head holding pedestals are removed from cask decontamination area.
A.
Moving the Spent Fuel Shipping Cask Into the Fuel Pool.
-1.
Inspect the cask for damage and operability of all its component parts and wash off the road film from the cask and trailer / car.
-Prccedure Number 3.7 Date
(-
l Revision 4
Page 3 of 5_
Pages I
Attachment No. 2 2.
Back,the truck / rail car containing the horizontally rounted fuel shipment cask into the Reactor Building through the railroad air
(_
lock. Remove the' cask hold-down bolts.
3.
Using the Reactor Building crane and the lifting yoke provided, pivot the cask to the vertical position by picking up the weight with the crane.
_T L
4.
Complete Surveillance Procedure 6.3.10.10.
CAUTION ALL CASK HANDLING ABOVE THE 931' LEVEL OF THE REACTOR BUILDING WILL BE DONE IN THE " RESTRICTED MODE" WHICR WILL CONFINE MOVEMENT TO THE CASK CONTROLLED PATH AS SHOWN IN ATTACHMENT "A".
5.
Place the Reactor Building crane in the " Restricted Mode" using the key operated selector switch prior to the time the cask reaches the 931' level.
Note:
If during fuel cask movement an equipment failure prevents operation in the " Restricted Mode" movement of the fuel cask is permitted,as necessary to get the cask to the r%sest acceptable stable location.
6.
Set the cask down in the decontamination area on the refueling floor, unbolt and remove the cask lid and remove the cask plug.
Check radiation and contamination levels inside cask and decon-(
taminate as necessary.
CAUTION WHEN PLACINC THE CASK IN THE SPENT FUEL STORAGE POOL, IT SHALL BE SUSPENDED ONLY OVER THE SPENT TUT.L CASK STORAGE LOCATION. IT SilALL NOT BE SUSPENDED OVER ANY FUEL. DO NOT LEAVE CASK SUSPENDED OVER THE POOL LONGER THAN NECESSARY.
CAUTION THE SPENT FUEL CASK SHALL NOT BE RAISED ABOVE THE REFUELING FLOOR IN EXCESS OF 6" EXCEPT IT MAY BE RAISED TO A HEIGHT OF % 3' FOR INSPECTION IN THE DECONTAMINATION AREA.
Note: All lenkers must be placed j n encapsulation cans ;,efore entering the cask, r
7.
Use the telescoping fuel grapple of the refueling platform to load the cask with those spent fuel bundles specified on a Special Nu-clear Materials Transf er Form (See Procedure 3.1).
'8. ' Using the lif ting yoke and the Reactor Building crane, lower the cask plug into the cask cavity. Engage the lifting dev!ce.
1
-?rocedure Number 3' 7 Date
(-1" Revision
__4_
Page 4 of _5 Pages L
Attachment No. 2 Moving the Spent Fuel Shipping Cask Out of the Building.
B.
Place the Reactor Building crane in the " Restricted Mode" using the
[
1.
key operated selector switch.
If during fuel cask movement an equipnent failu're prevents Note:
1.
operation in the " Restricted Mode" movement of the fuel p
cask is permitted as necessary to get the cask to;the closest acceptable stable location.
i.
A Special Nuclear Material Transfer form must be executed in 2.
accordance with Procedure 3.1 when transferring a cask con-taining spent fuel.
Using the lifting yoke and the Reactor Building crane, raise the 2.
loaded cask from the fuel storage pool. Perforn a radiation survey and wash the cask down with denineralized water while lifting.
3.
Position the cask in the decontamination area.
4.
Flush the cavity with demineralized water, sample for activity and If there is any indication of a leaking perform a radiation survey.
fuel bundle, the cask must be returned to the pool and the associated fuel bundle removed. Known leakers must be shipped in the defective fuel storage containers. Decontaminate external surface of the cask and survey until within shipping limits.
Detergents may also be used in the cask external decontamination
((
Note:
process to reduce the radioactive contamination of the cask to i
within the legal limits required prior to forwarding to commercial carriers.
Af ter the cask has reached a point of temperature equilibrium and the 5.
contamination of the externals is within shipping limits, holt the cask lid in place.
1 Using the Reactor Building crane and the lif ting yoke, lower the cask 6.
to the truck / railroad car, pivot it to the horizontal, position and I
1 attach the cask hold-down bolts to secure it in place.
7.
Perform a final radiatio. survey.
i Af ter appropriate shipping papers are prepared (FHP 3.1) required 8.
labels and plac_rds are placed on cask and truck / railroad car, and all shipping licenses are fulfilled, remove the cask from the Reactor Building.
VIII. ATTACHMENTS A.
Horizontal Controlled Path of Spent Fuel Cask.
B.
IGA Transfer Form (Figure 5 of Procedure 3.1).
(
Revision 4
Page 1 of 5 Pages
-Procedurc Number _ 3. 7 Date /- I I
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