ML20133G922
| ML20133G922 | |
| Person / Time | |
|---|---|
| Site: | 07003000 |
| Issue date: | 10/08/1985 |
| From: | Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20133G866 | List: |
| References | |
| NUDOCS 8510160188 | |
| Download: ML20133G922 (13) | |
Text
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OCT 8 1985 Docket No:
70-3000 Applicant:
Co'mmonwealth Edison Company (Ceco)
Facility:
Braidwood Station, Unit 1
SUBJECT:
SAFETY EVALUATION REPORT - REVIEW 0F LICENSE APPLICATION DATED JUNE 8, 1984, AND ITS SUPPLEMENTS DATED SEPTEMBER 18 AND NOVEMBER 19, 1984 AND JUNE 7 AND JULY 31, 1985, FOR A MATERIALS LICENSE I.
INTRODUCTION A.
General By application dated June 8,1984, Commonwealth Edison Company (CECO) requested authorization to receive, possess, inspect, and store uranium enriched in the U-235 isotope contained in fuel assemblies necessary for the operation of Braidwood Station, Units 1 and 2.
In supplements dated September 18 and November 19, 1984, CECO provided additional information needed by the staff to complete its review and requested additional special nuclear material in the form of post accident neutron monitoring detectors.
The June 7 and July 31, 1985, supplements provided additional modifications to the application and requested authorization to possess a plutonium sealed source. The present review will be limited to review of the requirements for the storage of special nuclear material for Unit I and the sealed plu-tonium source.
The fuel assembly, New Fuel Vault, and Spent Fuel Pool stcrage rack designs are the same as those for Byron Station, Units 1 and 2.
B.
Fuel Assembly Design The finished fuel assemblies will be supplied by the Westinghouse Electric Corporation.
Each fuel assembly contains 264 fuel pins, 24 guide thimble tubes, and one instrumentation thimble tube.
The fuel, guide and instru-mentation thimbles are spaced and supported in a 17 x 17 array by eight spacers and a top and bottom nozzle.
Table 1 gives general fuel rod param-eters that describe the fuel which will eventually be used in Braidwood Station, Units 1 and 2.
The materials license is being issued to allow early receipt of the fuel for the purpose of inspection and preparation of the fuel for reactor loading. The license will automatically terminate upon issuance of the Part 50 operating license for Unit 1.
C.
Location Description The Braidwood Station is located in northeastern Illinois, 3 miles south-west of the Kankakee River, 20 miles south-southwest of the tovn of Joliet, and 60 miles southwest of Chicago, Illinois.
Construction Permit Nos.
CPPR-132 (Docket No. 50-456) and CPPR-133 (Docket No. 50-457) were issued i
for Braidwood Station, Units 1 and 2, respectively on December 31, 1975.
B I
P C
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OCT 8 1995 Table 1 Braidwood Station, Units 1 and 2 General Fuel Data Fuel Assembly Data Inches Overall Length 159.8 Nominal Active Fuel Length 144 Fuel Rod Pitch 0.496 Rod Array 17 x 17 Rods Per Assembly 264 Fuel Rod Data Outside Diameter 0.360 Cladding Inside Diameter 0.315 Cladding Thickness 0.0225 Fuel Pellet Immersion Density (% theoretical) 95.0 Fuel Pellet Diameter 0.3088 Fuel Pellet Length 0.507 II.
AUTHORIZED ACTIVITIES The license will authorize the receipt, possession, and storage of 263 finished fuel assemblies per unit with a maximum pin enrichment of 3.55 w/o in U-235 in their shipping containers and in the New Fuel Storage Vault and with a maximum pin enrichment of 3.22 w/o in U-235 in the Spent Fuel Storage Pool.
The license will also authorize the repackaging of any assembly, if necessary, for delivery to a carrier.
It should be noted that this license does not authorize insertion of a fuel assembly into a reactor vessel.
The license will also authorize the receipt, possession, storage and use of 5 post accident neu-tron monitoring detectors containing special nuclear material (now authorized by License No. SNM-1938, dated January 14, 1985) and a plutonium-239 sealed source to be used for calibrating portable alpha instruments.
III. SCOPE OF REVIEW The safety review of the CECO request for a materials license includes an evaluation of the Braidwood Station organization, administration, nuclear crit-icality safety, radiation protection, and fire protection programs.
Since the fuel assembly and storage rack designs are the same as those at Byron Station, no new nuclear criticality safety analyses were required.
Discussions were held with the NRR Project Manager, the Resident Inspector, and the applicant's staff members during the course of the review.
The evaluation of the " Fuel Storage Physical Security Plan" was made by the Safeguards Material Licensing and International Activities Branch, Division of Safeguards, Office of Nuclear Material Safety and Safeguards.
2
OCT H 1985 IV.
POSSESSION LIMITS Conditions 6, 7, and 8 of the license specify the type, form, and quantity of material the licensee may possess at any one time under this license and will read ag follows:
6.
Material 7.
Form 8.
Quantity A.
Uranium enriched in A.
In unirradiated A.
3150 kg of 4
the U-235 isotope reactor fuel U-235 in uranium assemblies enriched to no more than 3.55 w/o in U-235 B.
Uranium enriched in B.
Contained in B.
40 g of U-235 the U-235 isotope sealed neutron at any enrich-detectors ment a
C.
Plutonium-239 C.
Sealed calibra-C.
2 microcuries tion source V.
ORGANIZATION A.
Nuclear Criticality Safety and Radiation Protection Responsibilities 1.
Station Superintendent The Station Superintendent exercises overall managerial and super-visory responsibility for the safe operation of the plant and its equipment.
He is responsible for compliance with the station's NRC licenses, government regulations, ASME code requirements, and the applicant's quality assurance program, i
j 2.
Fuel Handling Foreman New fuel is handled under the supervision of the Fuel Handling Fore-He is responsible for developing and implementing procedures man.
involving the control and handling of nuclear fuel.
3.
Station Health Physicist TheStationHealthPhysicistisresponsiblefordailyheafthphysics activities.
He reviews health physics surveys, dose data, internal deposition data, meteorological data, and environmental data.
He has access to the Station Superintendent on matters of radiation protec-tion during unusual or abnormal radiological conditions.
4.
Operating Engineer The Operating Engineer is responsible for the operation of the mechan-ical and electrical equipment and certain common plant systems, such as radioactive waste processing and fuel handling.
He is also responsible for authorizing functional acceptance tests to be con-i ducted by Operation and/or Technical Staff personnel.
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OCT 8 E65 5.
Technical Staff Supervisor The Technical Staff Supervisor provides technical support for plant operations, refueling, maintenance and modification, evaluates process data and equipment performance, and adequacy of station procedures.
He also has the responsibility and authority for implementation of the onsite review function.
Procedures and changes thereto, for the control and handling of nuclear fuel, are reviewed and approved by an Operating Engineer and by the Technical Staff Supervisor.
At least one of these individuals holds a Senior Reactor Operator's (SRO) License or SR0 Certification.
This commitment is highlighted in Condition 11, i
Condition 11.
Procedures, and changes thereto, for the control and handling of nuclear fuel, shall be reviewed and approved by an Operating Engineer and the Technical Staff Supervisor.
At least one of these individuals shall hold a Senior Reactor Operator's (SRO) License or SR0 Certification.
8.
Minimum Qualifications The qualifications of the aforementioned safety-related personnel have been reviewed.
They meet the minimum qualifications specified in Regula-tory Guide 1.8, " Personnel Selection and Training," or ANSI N18.1-1971,
" Selection and Training of Nuclear Personnel," or both.
ANSI N18.1-1971 requires the specified personnel must meet the related minimum qualifica-tions at the time of core loading or appointment to the active position.
CECO has clarified the time when the positions will be filled by qualified personnel; namely before receipt of fuel onsite.
By letter dated June 7, 1985, CECO stated the Fuel Handling Foreman may not have his AEC license (required by ANSI N18.1-1971 by the time of initial core loading), by the time of fuel receipt.
The first NRC Operator License Exam for Braidwood is scheduled to be given in the fall of 1985, and the results of the exam may not be known by date of fuel receipt.
However, the Fuel Handling Foreman will have all other qualifications required (by the Standard) by the date of fuel receipt.
The latter are adequate to fulfill the Foreman's responsibilities under the Part 70 license.
The staff recom-mends the minimum qualifications for the safety-related personnel be high-lighted in Conditions 12-16.
Condition 12.
The minimum technical qualifications for the Station Superintendent shall be in accordance with Section 4.2.1,
" Plant Manager," of ANSI N18.1-1971 before receipt of fuel onsite.
Condition 13.
The minimum technical qualifications for the Fuel Handling Foreman shall be in accordance with Section 4.3.1, " Super-visors Requiring AEC Licenses," of ANSI N18.1-1971, with the exception of licensing requirements, by the date of fuel receipt onsite.
4 e
OCT 8 1985 Condition 14.
The minimum technical qualifications for the Station Health l
Physicist shall be in accordance with the requirements for Radiation Protection Manager of Regulatory Guide 1.8, i
September 1975.
l Condition 15.
The minimum technical qualifications for the Operating Engineer shall be in accordance with Section 4.3.2, " Super-visors Requiring AEC Licenses," of ANSI N18.1-1971 before i
receipt of fuel onsite.
However, the Operating Engineer i
need not have a Senior Reactor Operator's (SRO) License or SRO Certification provided the Technical Staff Supervisor i
has one.
Condition 16.
The minimum technical qualifications for the Technical i
Staff Supervisor shall be in accordance with Section 4.6.1,
" Engineer in Charge," of ANSI N18.1-1971 before the receipt of fuel onsite.
C.
Training i
The applicant has committed to the training of both radiation safety and fuel handling personnel.
Prior to receipt of fuel onsite, radiation safety
{
personnel are trained in radiation safety as outlined in Section 3.2.1.7 i
of the Byron /Braidwood FSAR and in the CECO radiation protection procedures j
related to the fuel assembly handling.
Fuel handling personnel receive
{
training.in proper fuel handling procedures, including the related health i
and safe.ty aspects of the activities.
The staff has concluded that the applicant's radiation-safety and fuel handling training programs are ade-quate to allow them to responsibly carryout the activitiec for which a license is requested.
It is recommended that Condition 17 be added high-
]
lighting the training program.
Condition 17.
The following training shall be conducted prior to receipt of fuel onsite:
a.
All radiation safety personnel shall be trained in j
radiation safety and CECO radiation protection procedures j
related to fuel assembly handling.
b.
All operations personnel involved in fuel handling shall receive training in proper fuel handling procedures, l
including the related health and safety aspects of the activities.
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0.
Administrative Procedures i
The Fuel Handling Foreman will develop and implement administrative proce-3 dures for the control and handling of nuclear fuel bundles.
These proce-i dures and any change to these procedures require review and approval of an i
Operating Engineer and the Technical Staff Supervisor.
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OCT S1995 VI.
NUCLEAR CRITICALITY SAFETY The applicant requests authorization to store fuel assemblies in the New Fuel Storage Vault, the Spent Fuel Storage Pool, and in their shipping containers in the New Fuel unloading area of the fuel handling building and the area immediately outside the fuel handling building.
In order to Le sure the fuel handling equipment is ready to safely handle the fuel assemblies, it is recommended the following license condition be added.
Condition 18.
All preoperational testing of fuel handling equipment, related to activities authorized by this license, shall be completed and the test results shall be reviewed and approved by CECO engineering before receipt of fuel onsite.
This includes the testing of the following:
a.
The fuel assembly handling fixture tool, b.
The Rod Cluster Control Assembly (RCCA) handling fixture, c.
The fuel storage racks in the new fuel vault, and d.
The fuel handling building crane.
After the fuel assemblies are removed from their containers, they will be stored dry in the New Fuel Storage Vault.
The New Fuel Storage Vault has a capacity of 132 fuel assemblies.
A.
New Fuel Storage Vault In the New Fuel Storage Vault there will be 3 groups of fuel assemblies with each group having 2 rows of 22 assemblies each.
The fuel sssemblies within a group are spaced on 21 inches center-to-center.
There are two 50-inch aisles between the three groups.
The fuel storage cells have 0.125-inch thick square stainless steel tubes with an inner diameter of 9 inches.
The staff has determined the maximum k for the array to be lessthan0.89independentofthedegreeofwater*$$derationwithinand between assemblies or the degree of concrete reflection surrounding the array.
The licensee plans to wrap the fuel assemblies in protective covers to protect them from the environment while in storage.
If the covers were sealed at their bottoms, the assemblies could become internally moderated with water while the spaces between assemblies will be occupied only with air.
This could occur if the bottoms were closed, the storage area flooded and drained, and water retained in the covers.
Large arrays under these conditions may become critical.
The licensee did not state that the covers will either be opened on the bottom or have a slit near the bottom of the fuel assemblies to prevent the postulated accident from occurring.
Therefore, it is recommended the licensee take this precaution to prevent such a situation.
Accordingly, Condition 19 should be added to the license.
Condition 19.
Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
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j OCT S 95 It is the staff's opinion that with this condition, the licensee has established responsible and satisfactory precautions to avoid accidental criticality.
B.
Spent Fuel Storage Pool i
j The fuel assemblies in the racks in the Spent Fuel Storage Pool are spaced on 14 inch-centers.
The racks consist of square stainless steel tubes having a thickness of 1/8 inches.
The tubes are held together in an array 1
pattern by type 304 stainless steel plates welded to the side of the tubes 1
at four elevations.
The racks have a total capacity of 1050 fuel assem-blies.
However, an infinite array of assemblies at this spacing between i
I assemblies and moderated by water at optimum mist density would be super-critical even with an enrichment of 3.22 w/o U-235.
Therefore, the licensee specified the assemblies would be stored in the spent fuel pool in a checker-board pattern.
An independent nuclear criticality safety analysis by the staff indicates the k of an infinite array of fuel assemblies at the specified enrichment b positioned in the racks in a checkerboard pattern is less than 0.90 at optimum water mist density.
Therefore, any size array of fuel assemblies in a checkerboard pattern in the Spent Fuel Storage Pool 1
Racks is safe from inadvertent criticality.
It is recommended Condition 20 r
I be added to specify the fuel assemblies stored in the Spent Fuel Storage i
j Pool shall be limited to a maximum U-235 enrichment of 3.22 w/o and be stored in a checkerboard pattern.
j The licensee, in the application, committed to the verification of the l
placement of the fuel assemblies in a checkerboard pattern by two independent persons but neither identified the positions of personnel responsible for making I
the verification nor specified the frequency for making the verification.
There-1 fore, Condition 20 is also recommended to provide the required assurance; namely:
1 Condition 20.
New fuel assemblies may be stored in the Spent Fuel Storage l
Pool subject to the following additional conditions:
I j
a.
The maximum U-235 enrichment shall be 3.22 w/o.
j b.
The fuel assemblies shall be stored in a checkerboard pattern.
i c.
The Fuel Handling Foreman shall verify correct fuel assembly location af ter insertion of each fuel assembly into the assigned storage rack in accordance with a prepared written procedure approved by an Operating l
Engineer and the Technical Staff Supervisor, i
d.
An independent loading verification shall be made by a Quality Control Inspector.
t e.
The Fuel Handling Foreman and the Quality Control In-spector shall each sign a document assuring proper storage of each fuel assembly.
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OCT 8 1985 i
i In the event the hinged gate between the Spent Fuel Storage Pool and the 4
Fuel Transfer Canal needs repair and fuel assemblies are in the Spent Fuei Pool, the fuel assemblies should be protected against possible damage and from becoming dirty.
It is recommended the requirement for protection c' the fuel assemblies i
be covered in Condition 20f.
1 i
Condition 20f. The fuel assemblies shall be protected to preclude damage and preserve fuel assembly cleanliness while i
fuel is stored in the Spent Fuel Storage Pool.
C.
Shipping Container Storage t
The fuel assemblies may also be stored in the shipping containers (Westinghouse Models RCC-1 or RCC-3).
Since 60 of the containers filled with fuel assemblies may be shipped in a single Class III shipment, they may be stored safely as a group independent of stacking or the degree of water moderation and reflection.
Therefore, the staff recommends the storage of shipping containers of fuel assemblies be limited to 60 (Condition 21).
i Condition 21.
No more than 60 shipping containers, containing fuel, shall l
be stored onsite at any one time.
1 Calculations have indicated that two assemblies could be made critical at optimum conditions of water moderation and reflection; however, one assem-bly, separated from another assembly by another 12 inches, cannot be made critical under any conditions.
Because of this, the applicant has commit-j ted to have no more than one fuel assembly outside its shipping container or storage rack at a given time, but did not specify the minimum separa-tion between this assembly and others.
Therefore, the staf f recommends the following license conditions limiting the number of fuel assemblies out of storage and the minimum distance from all other fuel:
Condition 22.
No more than one fuel assembly shall be out of its shipping container or storage location at any given time.
Condition 23.
The minimum edge-to edge distance between the fuel assembly outside its shipping container or storage rack and all other fuel assemblies shall be 12 inches.
The licensee has requested, pursuant to 10 CFR 70.24(d), an exemption from i
the provisions of 10 CFR 70.24.
Because of the inherent features asso-ciated with the storage and inspection of unirradiated fuel containing l
uranium enriched to less than 5 percent in the U-235 isotope when no fuel pro-j cessing activities are to be performed and the inherent features in handl-ing limited quantities of sealed neutron monitoring detectors and a sealed 4
plutonium calibration source, the staff hereby determines that granting 4
such an exemption will not endanger life or property, or the common defense i
and security, and is otherwise in the public interest.
This exemption is i
authorized pursuant to 10 CFR 70.14.
It is recommended that the exemption be identified as Condition 24.
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OCT 8185 Condition 24.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to material held under this license.
VII. RADIATION SAFETY Since the radioactive rnaterial (fresh fuel assemblies) are sealed sources, the principal pathway to an individual is via external radiation from the fuel assemblies.
For a low enriched uranium fuel bundle (< 4 percent U-235 enrichment),
the exposure rate at 1 foot from the surface is normally less than 1 mr/hr; therefore, it is estimated that the exposure level to workers from these sources would be less than 25 percent of the maximum permissible exposure specified in 10 CFR 20. At Braidwood Station, Unit 1, personnel external exposures are continuously monitored using pencil dosimeters and film badges. The pencil dosimeters are evaluated daily for control purposes. An individual dose is normally estimated every 2 weeks from the film badge results and entered into Commonwealth Edison Company's Computerized Radiation Exposure Record System.
The neutron detectors, licensed under SNM 1938, are sealed sources.
In order to incorporate these detectors into the license authorizing the receipt of fuel assemblies, it is recommended the three conditions incorporated in the former license be incorporated as Conditions 25-27 in the new (revised) license as follows:
Condition 25.
Records of the radiation surveillance of the shipping containers with the neutron detectors and of the detectors, when surveyed shall be maintained and a copy of the results of each surveillance submitted to the Station Health Physicist.
Condition 26. The Post Accident Neutron Monitoring Detectors shall be stored in their shipping containers in the locked calibration facility.
The key to the calibration facility shall be under the control of the Shift Engineer.
Condition 27. A physical inventory of the neutron monitoring detectors shall be taken monthly to confirm the presence of all the detectors.
l The staff has concluded that the Braidwood Radiation Protection Program, together with the proposed license conditions, is adequate for the protection of the public, Braidwood Station personnel, and the environment.
VIII.
ENVIRONMENTAL PROTECTION The Final Environmental Statement related to the operation of Braidwood Station, Units 1 and 2, dated June 1984 has been prepared and issued by the NRC as NUREG-1026. An Environmental Assessment has also been prepared for the 10 CFR Part 70 fuel storage license in accordance with 10 CFR 51.21.
This assessment supports a Finding of No Significant Impact which was published in the Federal Register on May 9, 1985.
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OCT 8 1985 IX.
FIRE SAFETY The materials used in the fuel storage areas are steel and concrete with the exception of wooden (Douglas Fir) pads covering the bottom of the New Fuel Storage Vault.
There is also a significant quantity of wood (timber supports and plywood) on the refueling floor required during construction.
The fire fighting equipment consists of portable extinguishers and several firehose stations.
There are also automatic fire detectors located throughout the fuel storage areas.
If the automatic alarm system for the fuel handling building is not functional whenever fuel assemblies are onsite, a 24-hour fire watch will be provided.
This commitment is highlighted as Condition 28.
Condition 28.
A 24-hour fire watch shall be present in the areas adjacent to the fuel storage locations whenever fuel assemblies are onsite and the automatic alarm system is not functional.
The staff has cetermined that, with the addition of Condition 28, the fire protection measures provided are adequate for the facility.
X.
PHYSICAL PROTECTION The Division of Safeguards, NMSS, has reviewed CECO's Physical Security Plan and has determined that it meets the requirements of 10 CFR 73.67.
To ensure that the physical security plan shall be fully implemented and remain in effect whenever fresh fuel is stored onsite, the staff recommends Condition 29.
Condition 29.
The licensee shall maintain and fully implement all provisions of the Commission approved Physical Security Plan, including changes made pursuant to the authority of 10 CFR 70.32(e).
The approved Physical Security Plan con-sists of Revision 1 to the " Security Plan for Special Nuclear Materials Security for Commonwealth Edison Company, Braidwood Station," submitted with the letter dated April 19, 1985.
The Physical Security Plan shall be with-held from public disclosure pursuant to 10 CFR 2.790(d).
XI.
CONCLUSIONS 1.
After reviewing the application and its supplement, the staff finds that:
a.
The application meets the requirements of the Atomic Ener0y Act, as amended, and of the regulations of the Commission, b.
Issuance of the license would not be inimical to the common defense and security, and c.
Issuance of the license would not constitute an unreasonable risk to the health and safety of the public.
2.
With the recommended license conditions, the NRC staff finds that:
a.
The applicant is qualified by reason of training and experience to use the material for the purpose requested in accordance with the regulations in 10 CFR 70.23.
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~._. _. _ _. _ - - -
T OCT ' 81985 b.
The applicant's proposed equipment and facilities are adequate to protect health and minimize danger to life or property.
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c.
The applicant's proposed procedures to protect health and to minimize danger to life or property are adequate.
XII. RECOMMENDATIONS I
The staff recommends approval of the application and its supplement subject j
to the following conditions which the staff finds are appropriate to protect
}
health or to minimize danger to life or property.
11.
Procedures, and changes thereto, for the control and handling of 1
nuclear fuel shall be reviewed and approved by an Operating Engineer and the Technical Staff Supervisor.
At least one of these individuals shall hold a Senior Reactor Operator's (SRO) License or SRO Certification.
1
- 12. The minimum technical qualifications for the Station Superintendent j
shall be in accordance with Section 4.2.1, " Plant Manager," of ANSI j
N18.1-1971 before receipt of fuel onsite.
13.
The minimum technical qualifications for the Fuel Handling Foreman shall be in accordance with Section 4.3.1, " Supervisors Requiring i
AEC Licenses," of ANSI N18.1-1971, with the exception of the licensing requirements, by the date of fuel receipt onsite.
14.
The minimum technical qualifications for the Station Health Physicist 1
shall be in accordance with the requirements for Radiation Protection Manager of Regulatory Guide 1.8, September 1975.
15.
The minimum technical qualifications for the Operating Engineer shall be in accordance with Section 4.3.2, " Supervisors Requiring AEC Licenses," of ANSI N18.1-1971 before receipt of fuel onsite.
- However, the Operating Engineer need not have a Senior Reactor Operator's (SRO)
License or SR0 Certification provided the Technical Staff Supervisor has one.
i i
16.
The minimum ~ technical qualifications for the Technical Staff Supervisor i
shall be in accordance with Section 4.6.1, " Engineer in Charge," of f
ANSI N18.1-1971 before the receipt of fuel onsite.
l i
17.
The following training shall be conducted prior to receipt of fuel i
onsite:
j a.
All radiation safety personnel shall be trained in radiation safety and CECO radiation protection procedures related to fuel j
assembly handling.
b.
All operations personnel involved in fuel handling shall receive training in proper fuel handling procedures, including the related health and safety aspects of the activities.
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OCT 8 1995
- 18. All preoperational testing of fuel handling equipment, related to activities authorized by this license, shall be completed and the test results shall be reviewed and approved by CECO engineering before receipt of fuel onsite.
This includes the testing of the following:
a.
The fuel assembly handling fixture tool, b.
The Rod Cluster Control Assembly (RCCA) handling fixture, c.
The fuel storage racks in the new fuel vault, and d.
The fuel handling building crane.
19.
Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
20.
New fuel assemblies may be stored in the Spent Fuel Storage Pool subject to the following additional conditions:
a.
The maximum U-235 enrichment shall be 3.22 w/o.
b.
The fuel assemblies shall be stored in a checkerboard pattern.
c.
The Fuel Handling Foreman shall verify correct fuel assembly location af ter insertion of each fuel assembly into the assigned storage rack in accordance with a prepared written procedure approved by an Operating Engineer and the Technical Staff Supervisor, d.
An independent loading verification shall be made by a Quality Control Inspector.
e.
The Fuel Handling Foreman and the Quality Control Inspector shall each sign a document assuring proper storage of each fuel assembly, f.
The fuel assemblies shall be protected to preclude damage and preserve fuel assembly cleanliness while fuel is stored in the Spent Fuel Storage Pool.
- 21. No more than 60 shipping containers, containing fuel, shall be stored onsite at any one time.
22.
No more than one fuel assembly shall be out of its shipping container or storage location at any given time.
23.
The minimum edge-to-edge distance between the fuel assembly outside its shipping container or storage rack and all other fuel assemblies shall be 12 inches.
24.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to material held under this license.
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_~
r 00T 8 1985
- 25. Records of the radiation surveillance of the shipping containers with the neutron detectors and of the detectors, when surveyed shall be maintained and a copy of the results of each surveillance submitted to the Station Health Physicist.
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- 26. The Post Accident Neutron Monitoring Detectors shall be stored in their shipping containers in the locked calibration facility, f
The key to the calibration facility shall be under the control of the Shift Engineer.
I j
- 27. A physical inventory of the neutron monitoring detectors shall be J
taken monthly to confirm the presence of all the detectors.
l
- 28. A 24-hour fire watch shall be present in the areas adjacent to the fuel storage locations whenever fuel assemblies are onsite and the j
automatic alarm system is not functional.
i
- 29. The licensee shall maintain and fully implement all provisions of the 1
Commission approved Physical Security Plan, including changes made l
pursuant to the authority of 10 CFR 70.32(e). The approved Physical Security Plan consists of Revision 1 to the " Security Plan for Special l
Nuclear Materials Security for Commonwealth Edison Company, Braidwood i
Station," submitted with the letter dated April 19, 1985. The Physi-j cal Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
i I
j Original Signed by 1
N. Xetzlach l
Norman Ketzlach i
Uranium Process Licensing Section Uranium Fuel Licensing Branch i
Division of Fuel Cycle and Material Safety, NMSS l!
Original s'iped byr
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1 Approved by:
- w. r _,%.
W. T. Crow, Section Leader I
l CRESS FCUP"2 FC P(
FCUP tl>
l 5520 NKetz h
V arpe WTCrow 09/30/85 09/fo/85 09/Y/85 W/ /85 l
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