ML20133Q441
| ML20133Q441 | |
| Person / Time | |
|---|---|
| Site: | 07002997 |
| Issue date: | 10/28/1985 |
| From: | Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20133Q414 | List: |
| References | |
| NUDOCS 8511010546 | |
| Download: ML20133Q441 (11) | |
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! Docket No.: 70-2997
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1 Applicants: Carolina Power & Light Company t
l North Carolina Eastern Municipal Power Agency '
Facility: Shearon Harris Nuclear Power Plant Unit 1 l l
Subject:
SAFETY EVALUATION REPORT - REVIEW OF LICENSE APPLICATION !
DATED APRIL 12, 1984, ITS REVISION DATED SEPTEMBER 17, 1984, AND !
SUPPLEMENT DATED OCTOBER 10, 1985, FOR A MATERIALS LICENSE '
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- I. Introduction 1
A. General 1
By application dated April 12, 1984, its revision dated September 17, 1984, and !
l supplement dated October 10, 1985, Carolina Power & Light Company (CPL) on behalf l
{ of itself and the North Carulica Eastern Municipal Power Agency (NCEMPA) l 4
requested an NRC materials license for the receipt, possession, inspection, and :
j storage of special nuclear material in the form of unirradiated nuclear fuel !
) assemblies, the packaging of such fuel assemblies for delivery to a carrier, i and the receipt, possession, inspection, and use of incore fission chambers and sealed sources for irradiation surveilla .ce capsules as follows: !
! Byproduct, source and Chemical and Maximum amount !
special nuclear material physical form to be possessed ,
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) A. Uranium enriched in In unirradiated 4,157 pounds of the U-235 isotope reactor fuel U-235 in uranium l f assemblies enriched to no more than 3.1% i in U-235 l
enrichment j C. Uranium-neptunium Contained in 120 mgm Np 237 and
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j sealed sources 72 mgm U-238 '
i D. Californium-252 Primary startup 300 millicuries !
sources .
CPL requested authorization for the above by January 1,1985. ,
- 8. Fuel Assembly Desian '
The finished fuel assemblies will be supplied by Westinghouse Electric Corpora-tion. Each fuel assembly contains 264 fuel rods, 24 control rod guide tubes, ,
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COT 0 ( C3 l 4
and 1 instrument tube. The rods are spaced in a 17 x 17 array pattern, are supported laterally by 8 inconel spacer grids, and are supported on top and bottom by stainless steel end fittings. Table 1 gives general fuel rod para-I meters that describe the fuel which will eventually be used in the Shearon j Harris Nuclear Power Plant, Unit 1. Unit 1 is a pressurized water reactor l (PWR). The materials license is being requested to allow early receipt of the
, fuel for the purpose of inspection and preparation of the fuel for reactor i loading. The license will automatically terminate upon issuance of the Part 50 operating license.
Table 1 l Shearon Harris Station. Unit 1
- . General Fuel Data
- Fuel Assembly Data Inches
. Overall tength 159.8 Nominal Active Fuel Length 144 Fuel Rod Pitch 0.496 Rod Array 17 x 17 j Rods Per Assembly 264 1
Fuel Rod Data l Outside Diameter 0.374 ..
l Cladding Inside Diameter 0.329 Cladding Thickness 0.0225 t
j Fuel Rod Data Inches i
j Fuel Pellet Immersion Density 95.0 a
(*4 theoretical) i Fuel Pellet Diameter 0.3225
! C. tocation Description i The Shearon Harris Station is located in the southwest corner of Wake County j
and the southeast corner of Chatham County, North Carolina. The site is approx-l imately 16 miles southwest of Raleigh and 15 miles northeast of Sanford, North Carolina. The Construction Permit, CPPR-158 was issued on January 27, 1978,
- (Docket No. STN 50-400),
j II. Authorized Activities j The license will authorize the receipt, possession, and storage of 157 fin-1shed fuel assemblies (no spares) required for the first core. The maximum pin enrichment will be 3.15 w/o. The applicant also requests authorization to repackage any assembly, if necessary, for delivery to a carrier. It should be
- noted the license will not authorize insertion of a fuel assembly (*to the reactor vessel. Authorization is also requested for the receipt, possession, i
' inspection, and use of incore fission chambers and sealed sources for irradia-tion surveillance capsules.
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- OCT ^ ' G
!!I. Scope of Review I
The current safety review of the CPL request for a materials license included an evaluation of the Shearon Harris Nuclear Power Plant organization, admints-J tration, nuclear criticality safety, radiation protection, and fire protection programs. During the course of the review, discussions were held with the NRR Project Manager, the Resident Inspector, and the applicant's staf f members.
The evaluation of the Fuel Storage Physical Security Plan was made by the j
1 SG Material Licensing and International Activities Branch Olvision of Safeguards, Office of Nuclear Material Safety and Safeguards.
1 IV, possession Limits Although the applicant requested authorization for a maximum of 4,157 pounds (1890 kilograms) contained U-235 in uranium enriched to no more than 3.1 w/o,
! we propose to license a maximum of 1,900 kilograms U-235 in uranium enriched j
to no more than 3.15 w/o because of measurement and enrichment variations usually encountered.
i j The ippilcant also requested the possession of incore and encore fission 1
chambers sealed sources for irradiation surveillance capsules, and j californium-252 primary startup sources.
It is recommended Conditions 6, 7, and 8 of the license specify the type, 4
d form, and quantity of material the licensee may possess at any one time under this license and will read as follows:
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- 6. Material 7. Form 8. Quantity i
A. Uranium enriched in A. In unirradiated A. 1,900 kilograms
! the U-235 isotope reactor fuel of U-235 in j assemblies uranium enriched to no more than 3
3.15% in U-235 B. Uranium enriched in B. Contained in B. 2.5 grams of I the U-235 isotope sealed sources uranium at any
{ enrichment
! C. Uranium-neptunium C. Contained in C. 130 milligrams j
l sealed sources Np-237 and 80 milligrams
. U 238 I
j 0. Californium-252 0. Primary startup D. 300 millicuries sources i
V. Oraanization l The facility organization chart was included as part of the Part 50 " storage ll only" license application. The Manager, Plant Operations, has overall respon-l sibility for the facility-and safety-related functions. Reporting to him and 3
O C T a 7 t." 5 having safety-related responsibilities are the Manager, Operations, and the Manager, Environmental and Radiation Control.
A. Nuclear Criticality Safety and Radiation Protection Responsibilities The Manager, Operations, is responsible for approval of fuel handling proco-dures and a certified Reactor Operator is in overall charge of criticality safety for movement of fuel assemolles outside their shipping containers. The applicant also states the movement and inspection of new fuel assemblies are a
" team effort" whose leader is responsible for criticality safety and direction of new fuel handling. The leader has either held a reactor operator's license at another facility and had direct fuel handling experience or has been in a responsible position in charge of new fuel receipt and handling at another facility. The team also includes a radiation control technician directly responsible for radiation safety during shipping container and fuel handling operations.
The Manager, Technical Support, is responsible for fuel inspections, account-ability, and storage procedures as well as for overall coordination of the receipt and storage of new fuel.
The Manager, Environmental and Radiation Control, is responsible for the review and approval of Radiation Control Procedures for the receipt and survey of new fuel. He is also responsible for periodic surveys for radiation and contamina-tion of special nuclear material handling and storage areas. He is respon-sible for the overall activities of the Radiation Control Subunit including developing and approving Radiation Control Procedures and instructions to ensure ALARA philosophies have been incorporated.
The Radiation Control Supervisor reporting to the Manager, Environmental and Radiation Control, is responsible for ensuring that the Radiation Control Programs and related procedures meet the facility needs and regulatory require-ments.
The applicant did not specify the technical position responsible for approval of the nuclear criticality safety aspects of the procedures. It is recommended this responsibility be included in Condition 11.
Condition 11. Procedures, and changes thereto, for the control and handling of nuclear fuel shall include the review and approval of the Reactor Operator and the Manager, Tech-nical Support.
B. Minimum flualifications The appilcant has identified the responsibilities for the safety related personnel, submitted resumes of present holders of the positions, and specified minimum qualifications for the positions. However, the minimum qualifications are identified with a September 1979 draft of AN51/ANS-3,1, " Selection Qualifi-cation and Training of Personnel for Nuclear Power Plants," as modified by CP&L's position on Regulatory Guide 1.8 as discussed in FSAR Section 1.8. The minimum technical qualifications for the Reactor Operator responsible for the criticality safety for fuel assembly hantiling were specified by the applicant in terms of previous fuel receipt and handling experience. Conditions 12 15 4
007 CJ t-;5 are recommended to more clearly identify the minimum qualifications of the safety-related personnel and shall read as follows:
Condition 12. The minimum technical qualifications of the Manager, Operations, shall be in accordance with Section 4.2.2,
" Operations Manager," of ANS!/ANS-3.1-1978.
Condition 13. The minimum technical qualifications of the Manager, Technical Support, shall be in accordance with Section 4.2.4, " Technical Manager," of ANSI /ANS-3.1-1978.
Condition 14. The minimum qualifications for the Reactor Operator responsible for criticality safety for fuel assembly handling shall be in accordance with the following:
- a. The Reactor Operator shall have held a Commission Reactor Operator's license at another facility and have had direct fuel handling experience, or
- b. The Reactor Operator shall have held a responsible position in charge of new fuel receipt and handling at another facility.
Condition 15. The minimum qualifications of the Manager, Environmental and Radiation Control, and the Supervisor, Radiation Con-
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trol, shall be in accordance with that of the Radiation Protection Manager specified in Regulatory Guide 1.8,
" Personnel Selection and Training."
C. Training The applicant has committed to the training of personnel who will handle fuel assembites. The training includes classroom instruction and actual manipula-tion of fuel handling equipment. The Harris Training Unit is responsible for the training.
The training for Radiation Control personnel is the responsibility of the Radiation Control Supervisor. This includes radiological control functions during fuel receipt, procedural instruction, and " walk-through exercises."
The staff has concluded that the applicant's fuel handling and radiation safety training programs are adequate to allow them to responsibly carryout the activities for which the license is requested.
VI. Nuclear Criticality Safety The applicant requests authorization to store fuel assemblies in their shipping containers in the unloading bay and the staging area or in the storage racks in the New Fuel Pool. The storage racks in the pool have a capacity (for new and spent PWR fuel) for 480 PWR fuel assembifes, a capacity of more than 3 cores.
The applicant has committed to the completion of " major construction and testing of the necessary portions of the FHB (Fuel Handling Duilding) prior to 5
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OCT 23 3 1 the receipt and storage of new fuel." CPL considers the FHB complete for
! receipt of the first core when the new fuel system (New Fuel Handling Tool, j Rod Cluster Control Assembly Handling Tool, and Unit 1 New Fuel Elevator), the FHB Auxiliary Crane, and the Spent Fuel Pool Bridge Crane are tested in addi-tion to the installation of all new fuel storage racks in the storage locations.
A. New Fuel Storage pool l The fuel assemblies (enriched to the 3.15 w/o maximum U-235 enrichment) in the
- racks in the New Fuel Storage Pool are spaced on 10.5-inch centers. The racks consist of square stainless steel tubes having a thickness of 0.075 inches.
I The tubes are fastened together through top and bottom supporting grid struc- :
i tures to form integral modules. Boraflex sheets are encapsulated into the !
stainless steel walls of each tube with stainless steel welded to the outside !
of the tubes. The staff calculated the k for an infinite array of assemb-i lies in racks of the above design and fou,nd it to be 0.92 at optimum water '
- density (full density water). Even if the center-to-center spacing between j
- all assemolies was reduced to 10.05 inches (based on the most conservative con- i
' siderations of the mechanical tolerances of each rack design specification), the '
staff calculated the k to be 0.96. The latter assumptions are overly conserv-ative since reduction Tn the space between adjacent tubes on one side (<10.5 inches center-to-center) would increase the corresponding center-to-center
! distance between adjacent tubes on the opposite side. Therefore, the assembly ,
' storage racks, filled with fuel assemblies, are safe independent of the degree {
of water flooding.
I CPL has committed to a quality assuranc1 program to assure the presence of '
- Boraficx in the storage racks as designed. This includes inspection and i
verification of insertion of the correct sheet of Boraflex on all four sides t
of each storage tube per design and the necessary related welding operations.
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- 8. Shippino Container Storage i
The fuel assemblies may also be stored in the shipping containers (Certificate
{ of Compliance No. 5450). Although the applicant concluded that the shipping
{ containers may be stored in any array, no basis was given for the safety of j the array. Certificate of Compliance No. 5450 authorizes the shipment of the '
' assemblies as a Class II Shipment (Transport Index of 1.2/ shipping container) or as a Class III (exclusive use of vehicle) shipment with a maximum of 60 j
containers per shipment, independent of container stacking. Therefore, the i
j staff recommends Condition 16 be added limiting the number of shipping con-tainers in a single array to 60.
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Condition 16. No more than 60 shipping containers, containing fuel, '
shall be stored in a single array.
Should there become a need for the storage for more than 60 loaded shipping i contafners, additional containers may be stored in an array at least 20 feet ,
4 (edga-to-edge) from the first array. It is recommended Condition 17 be added l to permit the additional storage.
j condition 17. There shall be an edge-to-edge separation of at least ,
?J feet between groupings of 60 fuel assembly-bearing
- shipping containers.
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OCT 20 ..~25 Calculations have indicated that two assemblies could be made critical at optimum conditions of water moderation and reflection; however, one assembly, separated from another assembly by 12 inches edge-to-edge, cannot be made cri-tical under any conditions. Because of this, the applicant has committed to have only one fuel assembly at a time handled or inspected "in any single
- pool, canal, or inspection (staging) area." However, the applicant did not i
specify the minimum separation between this assembly and others. Therefore, the staff recommends the following license conditions limiting the number of
- fuel assemblies out of storage in the staging area or New Fuel Pool and the minimum distance from all other fuel
Condition 18. No more than one fuel assembly shall be out of its i'
shipping container or storage location in the staging area or New Fuel Pool at any given time.
l Condition 19. The minimum edge-to-edge distance between a fuel assembly j outside its shipping container or storage rack and all j
other fuel assemblies shall be 12 inches.
In response to an NRC request to describe the type of covers to be used to protect the fuel assemblies from dust while in storage, the applicant re-sponded that the top of the assemblies will be covered by a fire resistant plastic sheet while stored in the New Fuel Pool and the plastic shipping sleeves in which the assemblies arrive will not be re-used. This does not indicate whether the sleeves will be used in assembly storage if they are not removed. If the covers are used in assembly storage and are 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 l the bottoms were closed, the storage area flooded and drained, and water retained inside the covers. Large arrays, under these conditions, may become critical. Therefore, it is recommended Condition 20 be added to preclude the above from happening in the event plastic covers are used.
a Condition 20.
I 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 j area.
It is the staff's opinion that, with this condition, the licensee has estab-lished responsible and satisfactory precautions to avoid accidental criticality.
' The licensee has requested, pursuant to 10 CFR 70.24(d), an exemption from the provisions of 10 CFR 70.24 Because of the inherent features associated with the storage and inspection of unirradiated fuel containing uranium enriched to less than 5 percent in the U-235 isotope when no fuel processing activities are to be performed and the inherent safety features in handling limited quantities of incore fission chambers and sealed sources for irradiation surveillance, the staff hereby determines that granting such an exemption will not endanger
- life or property, or the common defense and security, and is otherwise in the i public interest. This exemption is authorized pursuant to 10 CFR 70.14. It
! is recommended that the exemption be identified as Condition 21.
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. 1 OCT ^C T:3 Condition 21. 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 material (fresh fuel assemblies) are sealed sources, the principal pathway to an individual is via external radiation from the fuel as-semblies. 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 speci-fied in 10 CFR 20. At the Shearon Harris Nuclear Power Plant, Unit 1, personnel external exposures are continuously monitored using devices such as thermal l luminescent dosimeters (TLDs) and self-reading pocket dosimeters (SRPDs). Since the appif cant did not specify the minimum frequency for reading the personnel monitoring devices, it is recoumended they be read daily (Condition 22).
Condition 22. The personnel exposure monitoring devices shall be read daily and an individual's dose shall be estimated at least every two weeks and recorded.
i Each fuel assembly shipping container is gamma surveyed and tested for smearable beta gamma contamination. If smearable contamination in excess of 1000 dpm/
100 cm2 is found, the container is isolated, an investigation initiated, and corrective action is taken.
Each fuel assembly is smeared and checked for alpha contamination. If a smearable alpha greater than 20 dpm/100 cm 2 is found, the assembly is isolated and an inspection is conducted to determine the cause of contamination.
Each instrument will be calibrated on a 6-month basis. The sources used for cali-l bration will be traceable to the National Bureau of Standards or other stanaards
- laboratory.
The incore fission chambers are sealed sources. The sealed sources containing Np-237 and U-238 are enclosed in a stainless steel capsule, sealed in a steel block, and enclosed in a second stainless steel capsule. Prior to installa-tion, the fission chambers and sealed sources will be stored in their shipping containers in an area for which access controls are established by Radiation Controls. The controls for the handling and storage of fuel assemblies, incore fission chambers, and sealed sources are adequate for the protection of personnel, property, and the environment.
Since the licensee did not specify the leak tests made periodically to determine the integrity of the sealed sources, it is recommended Condition 23 be added.
,, Condition 23. The licensee shall comply with the provisions of i Annex A," License Conditions for Leak Testing Sealed Sources Which Contain Alpha and/or Beta-Gamma Emitters."
VIII. Environmental Protection The Final Environmental Statement related to the operation of Shear : Harris Nuclear Power Plant, Units 1 and 2, dated October 1983 has been prepared and l
. 1 OCT 0 0 .TuS issued by the NRC as NUREG-0972. An Environmental Assessment has also been prepared for the 10 CFR Part 70 fuel storage license in accordar.ce with 10 CFR 51.21. This Assessment supports a Finding of No Significant Impact which was published in the Federal Register on January 7, 1985.
IX. Fire Safety The FHB is separated from other structures by 3-hour fire barriers. Combustible loading is minimal. Hand portable extinguishers and standpipe hose stations are installed throughout the building. Manual fire alarm stations are located throughout the FHB near hose stations with local alarm and annunciation in the control room.
X. Physical Protection The Division of Safeguards, NMSS, has reviewed CP&L's Physical Security Plan and has determined that it meets the requirements of 10 CFR 73.67. To insure that the security plan shall be fully implemented and remain in effect when-ever fresh fuel is onsite, the staff recommends Condition 24.
Condition 24. The licensee shall maintain and fully implement all provisions of the Commission approved Physical Secu-rity Plan, including changes made pursuant to the authority of 10 CFR 70.32(e). The approved Physical Security Plan consists of Revision 1 to the Plan for Receipt, Possession, Storage, and Preparation for Transport of Special Nuclear Material of Low Strategic Significance for Shearon Harris Nuclear Power Plant, Unit No. 1, dated April 12, 1984, and as revised July 8, 1985. The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
XI. Conclusions
- 1. After reviewing the application and its revision, the staff finds that;
- a. The application meets the requirements of the Atomic Energy 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 i 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.
- 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 The staff recommends approval of the application and i" , revision subject to i
the following conditions which the staff finds are appropriate to protect health or to minimize danger to life or property:
Condition 11. Procedures, and changes thereto, for the control and handling of nuclear fuel shall include the review and approval of the Reactor Operator and the Manager, <
Technical Support.
Condition 12. The minimum technical qualifications of the Manager, Operations, shall be in accordance with Section 4.2.2,
" Operations Manager," of ANSI /ANS-3.1-1978.
Condition 13. The minimum technical qualifications of the Manager, Technical Support, shall be in accordance with Section 4.2.4, " Technical Manager," of ANSI /ANS-3.1-1978.
I i Condition 14. The minimum qualifications for the Reactor Operator responsible for criticality safety for fuel assembly handling shall be in accordance with the following:
- a. The Reactor Operator shall have held a Commission Reactor Operator's license at another facility and have had direct fuel handling experience, or
- b. The Reactor Operator shall have held a responsible position in charge of new fuel receipt and handling at another facility.
Condition 15. The minimum qualifications of the Manager, Environmental and Radiation Control, and the Supervisor, Radiation Control, shall be in accordance with that of the Radiation Protection Manager specified in Regulatory Guide 1.8, " Personnel Selection and Training."
Condition 16. No more than 60 shipping containers, containing fuel, shall be stored in a single array.
Condition 17. There shall be an edge-to-edge separation of at least 20 feet between groupings of 60 fuel assembly-bearing shipping containers.
Condition 18. No more than one fuel assembly shall be out of its I
i shipping container or storage location in the staging area !
or New Fuel Pool at any given time.
Condition 19. The minimum edge-to-edge distance between a fuel assembly outside its shipping container or storage rack and all other fuel assemblies shall be 12 inches.
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Condition 20. Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of 1 flooding and subsequent draining of the fuel storage area.
Condition 21. The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to material held under this license.
Condition 22. The personnel exposure monitoring devices shall be read daily and an individual's dose shall be estimated at least every two weeks and recorded.
Condition 23. The licensee shall comply with the provisions of Annex A,
" License Conditions for Leak Testing Sealed Sources Which Contain Alpha and/or Beta Gamma Emitters."
Condition 24. The licensee shall maintain and fully implement all pro-visions 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 consists of Revision 1 to the Plan for Receipt, Possession, Storage, and Preparation for Transport of Special Nuclear Material of Low Strategic Significance for Shearon Harris Nuclear Power Plant, Unit No. 1, dated April 12, 1984, and as revised July 8, 1985. The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
Origir.al si gna c ht:
N. Kot:lach Norman Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS Original Signed By:
W. T.Crcr Approved by:
W.T. Crow, Section Leader 0FC: :FCUP :FCUF , :FCUP : :
_________ _ {_{_ ,_________________________
______________q7g _ ______________
NAME: :HKetz ach :VLTr.arpe :WTCrow . . :
DATE /h/ 85 h/ 85 Ah/hh/85 0FFICIAL RECORD COPY
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