ML20010E929
| ML20010E929 | |
| Person / Time | |
|---|---|
| Site: | Waterford, 07002946  |
| Issue date: | 07/27/1981 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20010E924 | List: |
| References | |
| 19441, NUDOCS 8109090132 | |
| Download: ML20010E929 (22) | |
Text
T APPLICATION FOR A t
SPECIAL NUCLEAR MATERIAL LICENSE i
I FOR WATERFORD SES UNIT NO. 3
}
I LOUISIANA POWER & L2GHT COMPANY i
i l
I l
i 19441 8109090132 810727 PDR ADOCK 05000382 A
PDR-
Louisiana Power & Light Company is an investor-owned public utility incorporated under the laws of the State of Louisiana with its principal office in New Orleans, Louisiana. The names, addresses, and citizenship of its principal of ficers are listed in Table 1-1.
Louisiana Power & Light Company is not owned or controlled by any alien, foreign corporation or foreign government.
1.0 General Information 1.1 Reactor and Fuel 1.1.1 This application for a Special Nuclear Material (SNM) License is submitted for Waterford Steam Electric Station Unit No. 3 (Waterford 3) located on the Wes* (right descending) Bank of the Mississippi River near Taf t, Louisiana in St. Charles Parish, approximately twenty-five miles west-northwest of Downtown New Orleans. The NRC Docket Number assigned to the project is 50-382 and the Applicant has been granted construction permit number CPPR-103.
1.1.2 The Fuel Assembly, Figure 1-1, consists of 236 fuel and poison rods, five control element assembly guide tubes, 11 fuel rod spacer grids, upper and lower end fittings, and a holddown desice.
The outer guide tubes, spacer The grids, and end fittings form the structural frame of the assembly.
principal components of the fuel assembly and the material compositions are shown in Table 1-2 and are fully detailed in Sections 4.2.1 and 4.2.2 of the Waterford 3 Final Safety Analsis Report (FSAR) on file with the NRC.
1.1.3 The core design provides for three fuel batches.
Batch A will contain 73 assemblies with a design enrichment of 1.87% U-235 by weight.
Batch B will contain 80 assemblies with a design enrichment of 2.41% U-235 by weight, except that the three pins on each corner of each Batch B assembly will have a design enrichment of 1. 87% U-235 by weight.
Batch C will contain 64 assemblies with a design enrichment of 2.91% U-235 by weight, except that the three pins on each corner of each Batch C assembly will have a design enrichment of 2.41%
1
U-235 by weight.
The total weight of each fuel assembly is approximately 1450 pounds.
1.1. 4 The total number of fuel assemblies for which a license is requested is 225, consisting of the 217 first core fuel assemblies described above plus an allowance for 8 spare fuel assemblies with enrichments no greater than 3.5 wt%
Based on the preceeding, a license is requested for the following:
A total amount of Uranium 235 in fuel assemblies not to exceed 2,400 kilograms, and a total weight of contained Uranium in fuel asseinblies not to exceed 96,000 kilograms.
J2 Storage conditions 1.2.1 Arrangement of the Fuel Storage and Handling Area is shown in Figures 1-2 and 1-3 of this application.
The fuel will be stored in the spent fuel and new fuel storage racks, or in the spent fuel storage racks only.
Inspection of the fuel assemblies will also be performed in the Fuel Storage and Handling Area on the +46 elevation of the Fuel Handling Building.
1.2.2 To the extent practical, no operations other than Fuel, CEA and startup source storage and handling will be performed in the fuel storage area while fuel is being handled or stored.
Since Watorford 3 has a separate Fuel Handling Building and since limited areas within this building will be utilized
[
for storage, the effects of activities conducted in adjacent areas on the safety of fuel storage will be minimized.
1.2.3 The New Fuel Storage Area provides dry storage for 80 fuel assemblies in Seismic Category I storage racks. The fuel storage racks consist of vertical storage cells, grouped in parallel rows, such that fuel assemblims.re removed from the top.
The storage racks are divided into 2 units, each consisting of a uniform 4 by 10 array.
Each fuel array has a design minimum edge-to-edge spacing of 12 inches or a center-to-center spacing of 21 inches.
This
arrangement provides a geometrically safe configuration, resulting in a suberitical array, even in the event of flooding with unborated water and/or under all design loadings.
The racks and their associated anchorages are designed to maintain the minimum allowable fuel spacing, to prevent new fuel assemblies from being inserted in other than prescribed locations, to support the contained fuel assemblies without damaging them and to allow subsequent fuel assembly removal.
The new fuel storage racks are designed in accordance with the following:
a) AISC - Specification for the Design, Fabrication and Erection of Structural Steel for Building, July 1970 b) American Society of Mechanical Engineer ( ASME) 1974 Edition, up to and including the Summer 1976 addenda:
ASME Section 11, Material Specifications ASME Section IX, Welding Qualifications c) American Society for Testing Material (ASTM) - ASTM A-167 Type 304 Standard Finish (1974) d) American Welding Society-AWS D1.1-1972, Structural Welding Code The racks are designed to safely withstand all external loads and forces, (including a SSE) and transmit these loads and forces to the surrounding concrete vault structure.
The spent fuel storage area provides storage for 1088 fuel assemblies in Seismic Category 1 storage racks.
The function of the spent fuel storage racks is to vertically support, physically separate, and facilitate cooling of spent fuel assemblies with control element assemblies inserted.
The spent fuel storage rack _ o e designed to remain suberitical assuming the racks are flooded l
with nonborated water, and to maintain a suberitical array under all design
(
loadings.
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The spent fuel storage racks are constructed entirely of stainless steel, and a leak detection system is provided to monitor 100 percent of the pool liner welds.
The governing codes used in the design of the spent fuel storage racks are as follows:
a) American Society of Mechanical Engineers ( ASME) 1974 Edition, up to and including Summer 1976 addenda: ASME Section II -Material Specifications, ASME Section V -Non-Destructive Examination and ASME Section IX -Welding Qualifications.
b) American Society for Testing and Matertials ( ASTM),1974:
ASTM E 165
-Standard Methods for Liquid Penetrant Inspection ASTM A 240
-Standard Specification for Heat-Resisting Chromium Nickel Stainless Steel Plate, Sheet, and Strip for Fusion-Welded Unfired Pressure Vessels ASTM A 276
-Standard Specification for Stainless and Heat Resisting Steel Bars and Shapes In addition to the pools and racks described above, other major equipment which may be utilized during fuel handling activities include:
- 1) The Spent Fuel Handling Machine, 2) The Fuel Handling Building Cranes, and
- 3) The Fuel Handling Tools.
The Spent Fuel Handling Machine and the Fuel Handling Building cranes are Seismic Category I Equipment, and are designed so that they will not become dislodged from their railings. The Fuel Storage and Handling Systems are fully described in Section 9.1 of the FSAR.
Interlocks and travel limits for the handling machine and cranes are described in Subsections 9.1.2 and 9.1.4 of the FSAR.
1.2.4 The Fire Protection System is fully described in Subsection 9.5.1 of the FSAR.
The amount of combustible material in the fuel storage area will be 4
minimized.
Ionization detectors will be utilized in the Fuel Handling Building.
Fire extinguishers have been provided in accordance with NFPA-10,1978, within the fuel storage areas the primary means of fire protection.
Hose stations provide a secondary means of fire protection such that all areas of the Fuel Handling Building are within 75 feet of a hose station.
Signs will be posted to warn against the use of foam fire-fighting agents within the new fuel storage area.
1.2.5 Access to the fuel storage area of the fuel handling building will be restricted to employees and agents on a need-to-enter basis.
For prevention of unauthorized access into the fuel storage area, temporary physical barriers will be erected.
An armed guard or locked door will be utilized to enforce the restrictions of access into this area.
A station administrative procedure will be implemented which will describe the necessary special security measures to be followed during storage of the initial core.
The measures will be in effect upon fuel receipt and will remain in effect until 30 days prior to fuel load when the provisions of the Waterford 3 Physical Security Plan will be implemented.
- 1. 3 Physical Protection 1.3.1 The New Fuel Storage Area and the Spent Fuel Storage Area are located in the Fuel Handling Building which is a controlled access area. A description of the physical security program for Waterford 3 has been provided to the NRC and has been withheld from public disclosure pursuant to 10 CFR 2.790(d).
The fuel assemblies furnished for the first core of Uaterford 3 do not contain any Uranium-233 or Plutonium. They do, however, contain sufficient Uranium-235 to be classified a special nuclear material of low strategic significance as defined in 10 CFR 73.2(y).
Therefore, the applicant will implement appropriate procedures to comply with the applicable protective 5
requirements of 10 CFR 73 and, in particular, the provisione of paragraph 73.67(f), in storing the New Fuel Assemblies for the first core of Waterford 3.
A physical security plan as required by 10 CFR 70.22(8)(k) is submitted under separate cover and should be considered proprietary as described under 10CFR 2.790(d) and withheld from public disclosure.
1.4 Transfer of Special Nuclear Material 1.4.1 Transportation of the new fuel assemblies covered by this application from the fabrication location to Waterford 3 will be the responsibility of the fuel fabricator, Combustion Engineering, Inc.
The fuel assemblies will be delivered to the station site in shipping containers, CE Model 927C, which are licensed with the NRC under license No. SNM-1067.
1.4.2 As soon as practical af ter their arrival, the New Fuel Assemblies will be removed from their shipping container and placed in the fuel storage racks.
Should a fuel assembly be damaged or otherwise be unacceptable for use, the applicant will be responsible for packaging the fuel assembly for return to the fuel fabricator (CE).
The fuel assemblies will be reloaded into the shipping containers, CE Model 927C, should the need arise for returning a New Fuel l
Assembly.
In support of the above activities, the applicant hereby requests to register as a user of the CE Model 927C shipping container in accordance with the provisions of 10 CFR 71.
1.5 Financial Protection and Indemnity.
1.5.1 Nuclear Energy Liability Policy No. NF-263 for $1,000,000 standby coverage with ANI/MAELU has been obtained to cover the storage of the fuel assemblies described in this application.
l Eight (8) certified copiss of the policy are enclosed with this application 6
i
so that when the Special Nuclear Materials License for Waterford 3 is issued, an indemnity ag reement can be issued simultaneously.
2.0 Health and Safety 2.1 Radiation Control 2.1.1 The persons responsible for radiation safety at Waterford 3 are Ralph W.
Kenning, Health Physics Engineer; Laurence R. Simon, Health Physics Engineering Technician; and Donald H. Espenan, Health Physics Associate Engineer I. The training and experience of these persons is shown in Tables 2-1 through 2-3.
2.1.2 Each sealed source containing radioactive material in excess of either 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be tested for leakage and/or contamination.
The tests shall be performed using a gas flow proportional counter or a G-M counter with scaler by either LP&L personnel or by other persons specifically authorized by the Nuclear Regula try Commission or an Agreement State. The test method shall have a detecti n sensitivity of at least 0.005 microcuries per test sample.
Each sealed source with removable contamination in excess of the above limit shall be imr ediately withdrawn from use and either decontaminated and repaired or disposed of in accordance with Nuclear Regulatory Commission regulations.
See Waterford 3 Technical Specification 1
4.7.10.1.2 for test frequencies and the applicable exemptions due to storage.
2.1.3 The calibration of most ranges of the gamma and beta-gamma detection instruments is performed inside a shielded calibrator.
Neutron sources are used to check neutron monitoring equipment. Additional smaller alpha, beta, 1
l and gamma sources may be used as needed to calibrate or check the lower ranges of the various instruments.
The instruments are calibrated semianually, and the sources used for calibration are traceable to the National Bureau of Standards or other standards laboratories. At least daily prior to use, the 7
instrument response is checked with an internal or external source to verify that the instrument is functioning properly.
2.2 Nuclear Criticality Safety 2.2.1 All of the fuel assemblies will be transferred individually from their shipping containers to either the new fuel storage racks or the spent fuel storage racks.
This will occur as soon as is practical af ter the arrival of the fuel.
2.2.2 The nuclear safety analysis for storage of fuel in the new fuel storage racks and the spent fuel storage racks is discussed in detail in section 9.1 of the FSAR.
The new fuel racks are designed to provide protection against damage to the new fuel and to prevent new fuel assemblies from being inserted in other than prescribed locations.
In order to place the new fuel in a storage cell, the checkered-plate, hinged cover of the storage cell must be opened.
By keeping all the other hinged covers closed and by having fixed checkered plate over all areas between these hinged covers, new fuel assemblies are prevented from being inserted in other than prescribed locations.
Criticality design calculations consider the effects of manufacturing tolerances in the rack, wear of the racas over their design life, and uncertainty of fuel assembly position Ln the racks.
Suf ficient margin to criticality is maintained under all conditions for the storage of new fuel assemblies with a maximum enrichment of 3.5 wef ght percent U-235.
The spent fuel storage rack design permits only one fuel assembly to be inserted into each appropriate storage location.
The spacing between fuel assemblies is such as to maintain a subcritical array with a Keff of less than 0.95 when fully loaded with assemblies (without CEA's) of maximum enrichment 3.5 weight percent U-235 and flooded with pure water. The criticality design
' cts of manuf acturing tolerances in the racks,
calculations consider the 8
variation in the fuel pool water density, and uncertainty of the fuel assembly position in the racks. The array is maintained in the subcritical condition described above during all design loadings.
2.2.3 The condition of water retention around or within an assembly due to the fuel packaging was also considered.
This condition is not credible for the following reasons:
(1) No packaging material is placed within the assemblies at any time.
(2) The fire-resistant plastic cover in which the assemblies are shipped will be removed prior to placing the assemblies in the spent fuel storage racks, and no other packaging material will be placed around the assemblies while they are in storage.
If the assemblies are placed in the new fuel vault, a plastic cover 2.) be placed around each assembly, but the bottom end will be lef t open to allow drainage.
(3) Each storage cell in the new fuel and spent fuel racks is open at the top and bottom to allow drainage of water from the racks.
Hence, the water level inside and outside the storage cells will always be the same.
2.2.4 No more than one fuel assembly will be out of its shipping container and not in the storage racks at any given time.
All other fuel assemblies shall be located either in the storage racks or in an approved shipping container.
Procedures describing the handling of fuel and the associated precautions will be used in fuel handling activities.
Gene.
s steps involved in handling and storing new fuel assemblics are listed beloc.
A.
Dry storage (New Fuel Vault) 1.
Dismantle shipping container (if applicable).
Verify fuel assembly identification and documentation.
2.
Upright fuel assembly in the shippit.g container.
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3.
Attach fuel handling tool to crane hook and secure tool to fuel assembly.
4.
Remove assembly from shipping container.
5.
Remove and discard polyethylene cover and transfer fuel assembly to the fuel inspection area.
6.
Complete visual inspection of the fuel assembly.
7.
Remove fuel assembly from the inspection space and, if a plastic cover is used, ensure lower end is open to provide sufficient water drainage capability.
8.
Move the fuel assembly to its designated place in the storage rack and with cover plate open lower the fuel assembly until sented in the rack.
9.
Disengage fuel handling tool from fuel assembly and close cover plate.
10.
Record fuel assembly storage location.
11.
Repeat procedure for remaining fuel assemblies.
B.
Dry Storage (Spent Fuel Fool) 1.
Dismantle shipping container (if applicable). Verify fuel assembly identification and documentation.
2.
Upright fuel assembly in the shipping container.
3.
Attach fuel handling tool to crane hook and secure tool to fuel assembly.
4.
Remove fuel assembly from shipping container.
5.
Remove and discard polyethylene cover and transfer fuel assembly to the fuel inspection area.
6.
Complete visual inspection of the fuel assembly.
7.
Move the fuel assembly to its designated place in the storage rack and lower the fuel assembly until seated in the rack.
8.
Disengage fuel handling tool from fuel assembly.
9.
Record fuel assembly location.
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10.
Re peat procedure for remaining fuel assemblies.
11.
Place polyethylene cover over rack location containing fuel assemblies.
The fuel handling methods will be accompanied by appropriate administrative and document controls.
Personnel supervising the new fuel handling operations will be trained in the use of fuel handling tools and will also be familiar with the operating procedures dealing with receiving, handling and storing new fuel assemblie s.
A dummy fuel assembly will be utilized for testing and training.
The Nuclear Engineerf ag Department will be responsible for the on-site control and accountability of special nuclear material.
2.2.5 An exemption is requested from the requirements of 10 CFR 70.24 as provided in 70.24(b). A criticality accident is not credible under the storage and handling conditions previously described.
2.3 Accident Analysis 2.3.1 The potential for accidents affecting the safety of storage in the storage area is limited to tl'c dropping of fuel assemblies over the storage The seismic design of the Fuel Handling Building, bridge, crane, racks, area.
and pools preclude the credibility of more severe accidents.
In the unlikely event of dropping a fuel assembly in the storage area, the consequences affecting safety would be minimal.
Due to the spacing of the storage array, a criticality condition would not be possible under these conditions. The consequences of the accident would be limited to the minimal effect of possible rupture of fuel rods and releasing unirradiated low-enrichment uranium dioxide fuel.
3.0 Other Materials Requiring NRC License
(
3.1 Startup Sources 3.1.1 Authorization is requested to receive title to, own, receive, transfer 11 f
1
.~
and store two plutonium beryllium (PuBe) net tron sources or equivalent, the total amount of each not to exceed 20 curies, in addition to and at the same time as the fuel assemblies previously described in this Application.
The plutonium in each source will contain an amount not to exceed 1.5 grams per source. Each Po238-Be source will produce no more than 4.4X10+7 neutrons per second + 10%.
Two 6-inch long Pu238-be doubly encapsulated sources are contained in welded stainless steel rods.
A complete description of the source assembly is contained in CE Drawing No. E-STE-165-220, Rev. 02.
The source will be shipped in a paraf fin-filled steel drum approximately 55" OH and 18" OD, which meets DOT Type A package specifications.
The source is positioned within a 2-in Schedule 40 steel pipe which is centered in the drum and surrounded by paraffin shielding.
The pipe is sealed by a 3/8-inch steel plate and neoprene rubber gasket.
This shipping container is licensed with the NRC under License No. SNM-567.
Any additional information required can be found in Monsanto Drawing, Nos.
C-2507-AA00, Rev. 3, and C-2507-AB00, Rev. 3.
Although later revisions may be applicable, the changes are not considered significant.
The paraffin-filled steel drum is designed to physically hold only one source. The source is contair.ed in the 2-inch Schedule 40 steel pipe which is connected to a threaded plug at the top which positions the source within the container. The source is also restrained on a fixed lateral plug at the bottom of the drum. Removal of the cover plate bolts allows the outer drum head to be withdrawn.
3.1.2 In addition to storage, authorization is requested for provisions to cover return shipping of the sources in their shipping containers to the suppliers in case of damage to the source or excessive decay of sources because of startup delays. Appropriate procedures and precautions will be utilized should this need arise.
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3.1. 3 In addition to the shielding provided for the startup sources, radiation protection provisions will include:
- 1) proper posting of storage location,
- 2) radiation surveys of the area, and 3) personnel radiation monitoring 5.o r individuals in the area.
The estimated dose rate in air at 3 feet from the source is 35 mrem /hr to tal.
The estimated dose rates at the surface of the shipping container are 88 mrem /hr neutron plus 18 mrem /hr gamma.
The estimated dose rate at :hree feet from the shipping container surface is 7.0 mrem /hr neutron plus 2.0 mrem /hr gamma.
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TABLE l-1 The names of LP&L's principal officers, all of whom are citizens of the United States, are as follows Jack M. Wyatt President and Chief Executive Officer Gerald M. McLendon Senior Vice President - Operations D. L. Aswell Vice President - Power Production Kenneth M. Brumfield Vice President - Administration Jack Davey Vice President and Chief Engineer Cus F. Delery Vice President - Consumer Services John H. Erwin, Jr.
Vice President and Treasurer William H. Talbot Secretary and Controller Joseph M. Mooney Vice President - Governmental and Public Af fairs j
The address of all of the foregoing principal officers of LP&L is:
P. O.
Box 6008 New Orleans, Louisiana 70174
TABLE l-2 MECRANICAL DESIGN PARAMETERS Fuel Rod Array, Square 16 X 16 Fuel Rod Pitch, in.
0.506 Spacer Grid Type Leaf spring Ma terial Zircaloy-4 Number per assembly 10 Weight each, lbm 1.8 Bottom Spacer Grid Type Leaf Material Inconel 625 Number per assembly 1
Weight each, lbm 2.6 Fuel Rod Fuel rod material (sintered pellet)
UO2 s
Pellet diameter, in.
0.325 Pellet length, in 0.390 Pellet density, g/cm 10.38 l
Pellet theoretical density, g/cm 10.96 l
Pellet density (% theoretical) 94.75 Stack density, g/cm 10.06 i
Clad material Zircalo
-S Clad ID, in.
0.332 Clad OD, (nominal), in.
0.382 Clad thickness, (nominal), in.
0.025 l
l l
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TABLE 1-2 (cont)
Diametral gap, (cold, nominal), in.
0.007 Active length, in 105 Plenum length, in.
9.677 CEA Guide Tubes Material Zircaloy-4 Number per assembly 5
End Fittings Material 304 Stainless Steci
TABLE 2-1 Training and Experience Ralph W. Kenning Training / Education Location Duration B.S. Physics & Astronomy Louisiana State University 4 yeart.
Baton Rouge, Louisiana M.S. Physics & Astronomy Same as above 2 years M.S. Health Physics Georgia Institute of Technology 1 year Atlanta, Georgia Emergency Planning NRC 1 week Austin, Texas Health Physics Training Louisiana State University, I week
- h. ton Rouge, Louisiana Environmental Radiation Harvard School of Public Health I week Surveillance Boston, Massachusetts Radioled cal Emergency FEMA 1 week i
Response Planning Metairie, Louisiana Health Physics in Radiation REAC/Ts I week Accidents Oak Ridge, Tennessee Experience Location Duration Review of shielding calculations LP&L Nuclear Project Group 6 Months New Orleans, Louisiana Health Physicist Arkansas Nuclear One 22 Months Russellville, Arkansas St. Lucie Nuclear Plant, 2 Months Ft. Pierce, Florida Health Physics Engineer Waterford SES Unit No. 3 2.8 years Taft, Louisiana
Table 2-2 Training and Experience Laurence R. Simon Training / Education Location Duration B.S. Indurtrial Technology Louisiana State University 4.5 years Baton Rouge, Louisiana Health Physics Course Oak Ridge Associated University 10 weeks Oak Ridge, Tennessee Seminar on the radiological Savannah River Project I week safety aspects of CF-252 Savannah, Georgia sources Workshop in the environmental Austin, Texas I week aspects of nuclear power USAEC orientation course Bethesada, Maryland 2 weeks on regulatory practices ASME/EPRI workshop on rad-Atlanta, Georgia I week waste & volume reduction 1
Experience Location Durati.n Health Physicist Louisiana Division of Radiation 3.5 years I
Control, Baton Rouge, Louisiana Radiation Safety Officer American Testers, Inc.,
1.5 years Amelia, Louisiana Bayou Testers 1.5 years Amelia, Louisiana Health Physics Engineering Waterford SES Unit No. 3 3.25 years Technician Taft, Louisiana Health Physicist Arkansas Nuclear One 2.5 months Russellville, Arkansas
4 Table 2-3 Training and Experier..e Donald H. Espenan Training / Education Location Duration M.S. Nuclear Engineering University of Florida 6 years Sciences - llealth Gainesville, Florida Physis Experience Location Duratior.
Associate Engineer LP&L, Waterford 3 1 year Health Physicist Killona, Louisiana Health Physicist Arkansas Nuclear one 3 weeks Russellville, Arkansas I roject Manager University of Florida, 1 year Graduate Assistant on the Gainsville, Florida Crystal River Project (Environ-mental Surveillance of Crystal River Unit 3)
Radiochemist on the Crystal University of Florida River Project 1 year Gainsville, Florida Assistant X-Ray Technician Drs Huston, Ray, Faust, Evin, 9 months New Orleans, Louisiana
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