ML20003D465
| ML20003D465 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, 07002882  |
| Issue date: | 10/27/1980 |
| From: | Cotton G, Dietch R SAN DIEGO GAS & ELECTRIC CO., SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20003D464 | List: |
| References | |
| 17728, NUDOCS 8103270238 | |
| Download: ML20003D465 (25) | |
Text
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of SOUTHERN CALIFORNIA
)
COCKET NO. 50-361 UNIT 2 EDISON COMPANY and SAN DIEGO GAS &
)
ELECTRIC COMPANY San Onofre Nuclear
)
COCKET NO. 50-36 2 UNIT 3 Generating Station, Units 2 and 3
)
Amendment No. 2 to Application for a Special Nuclear Material License SOUTHERN CALIFORNIA EDISON COMPANY and SAN DIEGO GAS &
ELECTRIC COMPANY hereby amend the above-numbered Application by submitting herewith Amendment No. 2 to the application for a Special Nuclear Material License.
This amendment consists of information to provide for revised new fuel storage conditions.
In the event of a conflict, the information in this Amendment No. 2 to the Application for a Special Nuclear Material License supersedes the information previously submitted.
D e
e 8103270288 _
o Subscribed on this JO day of ((/./#v / 9 f'C Respectfully submitted, SOUTHERN CALIFORNIA EDISOt1 COMPANY By Charles R. Kocher James A.
Beoletto Attorneys for Southern California Edison Company s\\
By k
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AGNES CRABTREE I
v'? PJSUC CAUFCRNIA qNCIPAL CPCf IN LOS ANGELES Cot;NTV
_ _ _ 1 _ _Md "_* _* M E A g 2f d H 2 Subscribed and sworn to before me this 165 day of de2W &s,/9/0 w J lsMd $Lu s Notayy Public in and for the County of Los %ngeles, State of California G
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SAN DIEGO GAS & ELECTRIC COMPANY Byg i &#-f g l
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a David R. Pigott Frank S. Bayley, III Samuel B. Casey Chickering & Gregory Attorneys for San Diego Gas & Electric Company By David R. Pigot(f. ~
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Subsc ibed and suorn to before me "Y
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ANiiE SC MIDT y le0TAff PUSUC CAUF04ntA h-
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Notary Public in and for the City and County of San Diego, California d
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SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 APPLICATION FCR LICEuSE, ArtENLMENT 2 FOR STORAGE CNLY OF UNIRRADIATED REACTOR FUEL AND ASSCCIATED RADICACTIVE MATERIAL Southern California Edison Conpany and San Diego Gas &
Electric Company (hereinafter called " Applicants"), pursuant to Title 10, Code of Federal Regulations Part 70, hereby apply for a license to permit the receipt, possession and storage of special nuclear material of unirradiated nuclear fuel assemblies, fission chambers, calibration sources, and startup sources as herein described for San Onofre Nuclear Generating Station, Units 2 and 3.
The term of the license requested is for the period oeginning December 1,1980, until such time as it may be 2
supplemented by a permanent operating license.
Southern California Edison Company is a public utility incorporated under the laws of the State of California, with its principal office in Rosemead, California, and is engaged in the generation, distribution, and sale of electricity.
The names, addresses, and citizenship of its principal of ficers are listed in ' Appendix A of this application.
Southern California Edison Company is not. owned, controlled or dominated oy an alien, foreign corporation, or foreign government.
San Diego Cas and Electric Company is a public utility incorporated under the laws of the St;te of California, with its principal office in San Diego, California, and is engaged in the generation, distribution, and cale of electricity.
The names, addresses, and citizenship of its principal officers are listed in Appendix B of this application.
San Diego Gas and Electric Cowpany is not owned, controlled, or dominated by an alien, foreign corporation, or foreign government.
Applicants make this application pursuant to author-ization by their board of directors and are acting on their behalf and not as agent or representative of any other person.
Applicants request exemption from the requirements of Title 10 CFR Section 70.24 as provided in Subsection 70.24(d).
As descrioed herein, the fuel assemblies will be stored in critically safe storage racks.
In addition, other administrative procedures as discussed herein preclude the-achievement of conditions which could cause criticality.
1.0 GENERAL INFORMATION 1.1 Reactor and Fuel Tne special nuclear materials provided for in this license application will oe stored at the San Cnofre Nuclear Gener-ating Station, Units 2 and 3 reactor site located on the
, n., m 2.0 Lw s e
_2_
Louthern California Coast in San Diego County.
The site is 2.5 kilometers southeast of the City of San Clemente, California.
Construction of these units was authorized under Permit CPPR-97 and 98 issued Octocer 18, 1973, in response to the Southern California Edison and San Diego Gas and Electric Company application of May 28, 1970 (Docket 50-361 and 50-362).
Tne fuel assemolies requiring storage are constructed of fuel rods arranged in a square array with 16 rod locations per side and a fuel rod pitch of 0.506 inches.
The fuel assemuly arrangement (Figure 1) consists of 236 fuel rod positions, 5 Zircaloy-4 CEA guide tubes (each guide tube displaces 4 rod locations), 11 Zirealoy-4 spacer grids, 1 Inconel 625 spacer grid (lower end), stainless steel upper end and lower end fittings and a holddown devi.ce.
The holddown device consists of the upper cast plate (one of two plates in the upper end fitting) and five helical Inconel X-750 springs.
Tne fuel rods (Figure 2) contained in a fuel assembly consist of sintered uranium dioxide pellets encased in a cold worked and stress relief annealed Circaloy-4 tube.
During assembly, the fuel pellets are stacked in the cladding tube to the required fuel height.
A round wire type 302 stainless steel compression spring and an aluminum spacer cisc are inserted at each end of the fuel column.
The end plugs are installed and welded into the clad tubing.
Vne fuel rod is internally pressurized with helium during this asseucly.
Tne total-weight of U-235 which is to be covered by this application is approximately 4,260 kilograms in 434 fuel assemulies (217 assemblies per core).
The core design calls for three regions.
Region 1 will contain 73 assecolies with a cesign enrichment of 1.87% U-235 by weight.
Region 2 will contain 80 assemblies with an average enrichment of 2.38%
U-235 oy weight (with a maximum of 2.41% U-235 by weight).
Region 3 will contain 64 assemblies with an average enrich-2 ment of 2.88% by weight (with a maximum of 2.91% U-235 by weight).
The total weight of each fuel assembly is 1,451 lbs.
Table 1.1-1 summarizes the characteristics of the fuel roos with respect to dimensions, materials, quantities, and otner pertinent parameters.;
1.2 Storage Conditions The new fuel storage racks consist of vertical cells grouped in parallel rows to form structural units that are anchorea to the -floor of the new fuel storage area.
The new fuel will oe stored dry in these racks which are designeo to provide storage for at least 73 fuel asseuulies (one-third of 4 core).
i
, f 0.98 or less for cry Tne arrangment results in a ketf storage of fuel with the highest anticipated enrichment assuuing optimua moderation.
The new fuel storage racks are designed to protect the stored assemblics against possible impact loading due to handling of neighuoring assemblies and to prevent insertion of assemblies into spaces other than the prescribeo locations.
Structural deformations are limited and centerline-to-centerline spacing is maintained to preclude tue possibility of criticality under all anticipated loading conditions, including the design basis earthquake (uuE).
Lateral movement is restricted to waintain safe geometry margins and to preclude the reduction of the space between tue fuel assemoly cavities.
The new fuel racks, except for access platforms, are constructed entirely of stainless steel.
The access plattorms are constructed of galvanized caruon steel and do not come in contact with fuel assemblies.
The new fuel storage facility is part of the fuel-handling building, a seismic Category I structure.
A separate fuel nandling building is provided for each reactor unit.
The new fuel storage facility is located to permit ready access to new fuel assemblies and to facilitate expeditious transfer of the assemolies into the containuent during reactor, refueling operations.
Figures 3, 4, and 5 show the general arrangements and locations of the new fuel storage facilities in the station complex.
The new fuel storage facility is designed in compliance,with ANSI N18.2, Nuclear Safety Criteria for Design of Stationary Pressurized Water Reactor Plants.
Tue normal storage location for new unirradiated fuel is the new fuel storage facility.
tiowever, since the new fuel storage faclLity can accommodate only 73 assemblies, the remainder of the first core,144 assemblies, will be stored dry in the spent fuel storage facility.
The spent fuel storage racks consist of vertical cells grouped to torm structural units.that are anchored to the floor of tue spent fuel pool.
The spent fuel storage racks and pool are designed to provide storage for at least 800 fuel assemulies (three and two-thirds cores).
New fuel assemblies will be stored using every other storage row and 2
column.
The arrangement results in a k of 0.98 or less with the highest anticipated enrichment *Ikssuming an infinite array of fuel storage locations, and flooding with unDorated water.
L__
. The spent fuel storage facility is part of the fuel-handling building, a Seismic Category I structure.
The spent fuel storage facility is designed consistent with ANSI N18.2, Nuclear Safety Criteria for Design of Stationary Pressurized Water Reactor Plants, and Regulatory Guide 1.13, Spent Fuel Storage Facility Design Bases, dated March 10, 1977, as reflected in Part C, Regulatory Position.
The equipment to be used during transfer of new fuel from the shipping containers to the storage racks are the new fuel handling tool, the new fuel handling crane, and the spent fuel handling machine.
The new fuel handling crane is a single girder, underhung bridge crane spanning the new fuel storage area.
The crane is equipped with a mechan-ically operated, interlocking device that allows the bridge to be interlocked with a stationary monorail.
The interlocking device provides for a positive lock between the bridge and monorail and allows for the safe travel of the i
hoist between the bridge and the monorail.
The interlocking device also prevents the hoist from traveling off of either the bridge or monorail when the bridge and monorail are disengaged.
The hoist is an electric hoist and the new fuel handling tool is suspended from the hoist.
The new fuel handling tool (Figure 6) is operated manually for safe transfer of the fuel assemblies.
The spent fuel handling machine (Figure 7) is a traveling bridge and trolley that rides on rails over the spent fuel pool, fuel transfer pool, and cask loading pit.
The spent fuel handling machine hoist assembly contains a grappling device which, when rotated by the actuator mechanism, engages the fuel assembly to be moved.
Once the assembly is grappled, a cable and hoist winch raise the fuel assembly.
Interlocks are installed so that movement of the spent fuel handling machine is not possible when the hoist is withdrawing or inserting an assembly.
Detailed descriptions and scale drawings of the fuel handling areas and associated equipment are given in the San Onofre Nuclear Generating Station Units 2 and 3 Final Safety Analysis Report (FSAR), Section 9.1.
Before-fuel is stored in the fuel-handling building, all construction cranes located close enough to the fuel-handling building will be removed permanently from the area.
As snown in Figures 3 and 4,'the two fuel handling buildings are located on the east side of the containment buildings and are thus isolated from the turbine areas, intake structure, transformers, and diesel generator buildings.
These-areas are likely to contain the majority of personnel equipment activity.
The area directly east of the fuel hancling buildings is a high grade to the switchyard.
- Thus, e
-~.
. tne ouildings are located in a low activity area which will leave little construction activity and discourages the congregation of men and equipment.
The tire protection system in the new fuel area and spent fuel area consists of detection devices, alarms, and suppression systems.
The detection devices, smoke, and fix-temperature-rate-of-rise neat detectors will activate alarms locally and in the control room in case of a fire.
The primary means of suppressing the fire will be through extinguisheds.xtinguishers and portable dry chemical portacle Co e
A more detailed description of the San Unofre duclear Generating Station, Units 2 and 3 FSAR, Section 9 5.1.
When fuel assemblies are stored in the new and spent fuel storage areas, access to the storage area will be restricted to authorized personnel.
The only means of access to the new or spent fuel storage areas will be through doors that are alarmed and locked with keys administered by the Security Supervisor.
Operation of the new fuel handling crane and the spent fuel handling crane will be adminis-tratively controlled oy locking out power to the cranes except when authorized personnel request their use.
1.3 Physical Protection The new fuel storage facility and the spent fuel storage facility are Loth located in the fuel handling building whien is a controlled access area.
A description of the pnysical security program for Gan Onofre Nuclear Generating Station, Units 2 and 3 has been provided to the NRC and has been withneld from public disclosure pursuant to paragraph 2.790(d), 10CFR Part 2, Rule of Practice.
One fuel assemulies furnished for the first core at San Onofre Nuclear Generating Station, Units 2 and 3, contain no waterials enriched in U-235 in greater than 2.91% by weight.
Tne assemblies contain no U-233 nor p'lutonium.
The 2
protective requirements of 10CFR Part 73.47 will apply to the San Onofre nuclear Generating Station, Units 2 and 3, first core new fuel storage.
1.4 Transfer of Special Nuclear Material Transportation of the new fuel assemblies from the fabrication location to the San Onofre Nuclear Generating
~
Station, Units 2 and 3, will be the responsibility of the fuel fabricator, Combustion Engineering, Inc., 1000 Prospect Hill Road, Windsor, Connecticut 06095.
The fuel assemolies will be delivered to the plant site in shipping containers
.n
. i wnica are the property of the fuel fabricator, Comoustion Engineering, Inc.
The shipping container is a steel struc-ture capable of. storing or transporting one or two fuel assemblies.
Combustion nas been licensed by the U.S.
riuclear Regulatory Commission in License SUM-1067 to package and transport fuel assemblies in such shipping containers.
As soon as practical after their arrival, the assemblies will be removed individually froa their shipping containers and placed in the fuel storage racks.
1.5 Financial Protection and Indemnity The proof of financial protection furnished under Section 140.15 of 10CFR Part 140 for San Onofre Unit 1 (DPR-13) also applies to San Cnofre Units 2 and 3.
2.0 HEALTti AND SAFETY 2.1 Radiation Control 1.
The persons responsiole for radiation safety at San Onofre Units 2 and 3 are the Chemical and Radiation Protection Engineer (This position is currently vacant and will ce filled by January 1, 1981.
John P. Albers, the Assistant Radiation Protection Engineer, is 2
currently responsible.), and Stephen P. Corey, the Chemical and itadiation Protectica 'o rmaan.
Tne training and experience of thes e cons are shown in Tables 2.1-1 through 2.1-4.
2.
Mach sealed source will be tested for contamination prior'to initial use or storage excluding 100 uC' or less beta and/or gamma emitting materials and 5 uC or less alpha emitting materials.
Monitoring of each source for removable contamination will occur at six month intervals.
Tne Chemical and Radiation Protection Engineer will directly supervise leak testing of sealed sources.
The sources will be smear tested.
If the test reveals the presence of 0.005 pc or more of removable contara-ination, the source will be withdrawn from use and either decontaminated and repaired, or disposed of in accordance with NRC regulations.
J.
Calibration of most ranges of the gamma and beta-gamma detection instruments is performed inside a shielded ualibrator.
Heutron sources are used to check neutron monitoring instruments.
Additional smaller alpha, usta, and gamma sources can be used as necessary to calibrate or check the lower ranges of the various i
instruments.
Dackground and a check source are counted prior to the use of each instrument to verify that the instrument has not changed significantly.
The instru-ments are calibrated quarterly.
The sources used for cclibration are traceable to the National Bureau of Standards or other standards laboratory.
At least daily prior to use, the instrument response is checked with an internal or external source to verify that the instrument is functioning preperly.
2.2 Nuclear Safety 1.
The nuclear fuel assemblies will ce transferred indi-vidually from tneir shipping containers for storage in the fuel storage racks.
2.
The nuclear safety analysis for storage of fuel in the 2
new fuel and spent fuel storage racks is discussed in Appendix C of this application.
3.
The fuel handling equipment and activities will be limited during receipt of the initial core to that required for new fuel inspection and storage.
The equipment to be used for new fuel transfer from their containers to tne racks are the fuel handling tool, new fuel handling crane, spent fuel handling machine, and such fuel inspection tools as required by procedure.
After arrival of the new fuel shipping containers, the container covers are removed and the fuel assembly strongback raised to the vertical position and locked.
Tne new fuel handling tool, attached to the new fuel handling crane, is then locked to the fuel assembly, the fuel assembly clamping fixtures removed, and the fuel assembly removed from the container.
Next, the protective wrapping is removed and the fuel assembly is visually inspected.
The fuel assembly is then moved over to the new fuel storage racks where it is placed into its designated cavity.
The ftel handling tool is unlocked from the assembly and the operation repeated until the specified number of assemblies are placed in the racks.
The remaining assemblies (144) will be placed in the spent fuel assembly storage racks according to a similar procedure.
In this case, the spent fuel nandling machine is used in place of the new fuel handling crane.
During fuel assembly movement to and from storage, only one assembly will be allowed out of a shipping container or storage location at one time in the f uel storage area.
. 4.
npplicants nave requested an exemption fros. the requirements of Title 10CFR Sect;cn 70.24 as provided in Sousection 70.24(d) previously in tnis application.
2.3 Accident Analysis Tne possibility of a fuel handling accident is remote because of the many administrative controls and physical limitations imposed on tne fuel handling operations.
tiowever, it is postulated that a fuel assembly is dropped breaching the cladding of the fuel.
In the event of such an occurrence, the associated operation would ce halted.
The radiation protection personnel would then evaluate the healtn hazard.
The fuel suppiier, Combustion Engineering, would be notified of the situation and requested to aid tne Plant Staff in evaluating the damage to the affected fuel assemblies.
The possibility of a criticality accident is considered remote due to tne design of the fuei-handling and storage equipment ano the administrative controls.
Tne possibility of fuel damage due to fire in the fuel storage area is considered reuote due to tne limited supply of coccusticle uatarials and lack of ignition source.
'~
tesign casis fuel handling accidents are discussed in San Onofre Nuclear Generating Station Units 2 and 3 FSAR Section 15.7.3.4.
3.0 OYhER MATERIALS REQUIRING NRC LICENSE 1.
Other special nuclear material for which a license is requested consists of uranium-235 and plutonium-238 in the following forms and quantities, a)
Uranium-235 Form Amount Capsule Type Amount / Chamber 934 U-235 35 gm Fission chambers 0.85 gm l
1 of U235*
manufactured ny of U Reuter-Stokes Model No.
RS-C3-2540-102 (24 chambers, 12 per unit)
- 35 gu of U-235 authorized by Amendment 1 to Special Nuclear 2
naterial License No. SNM-1844 (NRC letter to SCE dated January 23, 1980).
c
. The fission chambers will De used in the ex-core detector system for San Cnofre Units 2 and 3.
b)
Plutonium-238 Gource Form Amount Capsule Type Strength 4 douoly 80 curies Monsanto 4.4 x 107 encapsulated (20 curies / source Recearch Corp.
neutrons Pu-Be sources 1.15 gm P'.-238 Model number per second per source) will be supplied
+10%
by October, 1979, 4 months prior to delivery Two sources will be supplied per unit to be used as startup sources.
A complete description oJ the source assembly is contained in CE Crawing No. E-STD-165-220, Rev. Cl, attached to this application.
c)
Plutonium-238 Form Amount Capsule Type 1 doubly 20 curies Monsanto encapsulated Research Pu-Ee source Corp. Model No. 2727B The source will be contained in the J. L. Shepherd Model 149 neutron calibration facility.
The source is fixed to the end of a shielded operating rod which is remotely moved by means of an operating handle-cable assemoly.
The source position is indicated by lights ouilt into the control box.
The dimensions of the calibrator are 33 inches in diameter and 36 inches in height.
The external radiation level is less than 5 mrem /hr at one foot from any surf ace with source in "off" position.
A complete description of the control assembly, source assemoly, and container is shown in J.
L. Shepherd Drawing-Nos. A-0149-3, A-0149-6, and A-0149-7 attached in this application.
2.
Storage Conditions Tne material described above will be stored at San Onofre Unit 1 (DPR-13) until the health physics area at Units 2 and 3 is complete.
The radiation e
E.
. monitoring system, healtu physics and laboratory equipment, and radioactive source materials safety at San Onofre Unit 1 are described in the San Cnofre Unit 1 Final Safety Analysis Report (FSAR) Sections 5.7, 5.8 and 5.9, respectively.
These materials will be under the jurisdiction of the Radiation Protection Group.
Individual storage conditions for the above material is as follows:
a)
The fission chahtbers will be stored in locked cabinets in the health physics area until installation.
b)
The neutron startup sources will be shipped. at the time of fuel shipment.
They will ce stored in their shipping containers in the fuel storage area.
c)
The 20 curie Pu-Be calibration source is contained in the J. L. Shepherd Model 149 calibration f acility which will be stored ir4 the health physics area.
4 9
1
m--_.-_m.________
. "*aule 1.1-1 nechanical Design Parameters t'uel itods fuel naterial UO sintered 2
Pellet diaueter, in.
.325 Pellet length, in.
.390 Pellet density, g/cm3 10.38 Pellet theoretical density, g/cm3 10.9e vellet density (% theoretical) 94.75 tack height cansity, g/cm3 10.061 Clad htaterial 2ircaloy - 4 Clad OD, in.
0.382 2
Clad.ID, in.
0.332 Clad tnickness, in.
0.025 Diaretral gap, in.
0.007 a
Active length, in.
150 Picnum. length, in.
10.0
.Puci Assemuly led array, square 16 x 16 nod positions 236 e
hoc pitch,.in.
0.506 Weigut 1451
- .ipacer grids
'12 Outside uimensions Fuel rod to fuel rod, in..
7.972 x 7.972
.Nuuber~per core 217 e
'k
lable 2.1-1 1 RAINING John P. Albers l2 On 1he Fornel
_1ype of Training Where Trained Duration Job Course 1.
Principles and Practices a.
San Diego State University of Radiation Protection M.S. Degree Radiological Health Physics 2 years X
h b.
Ar00nne National Laboratory: University of Chicago Graduate Student Research Participation 3 months X
X Program: 1LD studies c.
Rockwell International liealth Physics 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> X
d.
Oak Ridge National Laboratory Emergency liandling of Radiation Accidents 40 hotns X
2 e.
Los Alamos Scientific Laboratory Respiratory Protection 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> X
f.
San Diego Chapter Health Physics Society: llealth Physics Certifiction Course 17 weeks X
9 Rockwell International Reactor Operations 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> X
h.
Pacific Gas and Electric Conpany Dept. OT Engineerirv) Rescatch 6 nonths X
1.
San Onofre Nuclear Generating Station 3 years X
2.
Radioactivity Measurement Same as above Standardization una Monitoring Techniques and Inst ruments
Page 2 of 2 Table 2.1-1 lype of Training Where Trained 3.
Mathematics and Calculations Same as above basic to the use and nesasurement 2
of radioactivity 4.
biological ef fects of radiation Sanc as atiove o.
s
(
Table 2.1-2 EXPERIEbCE WITH RADIATION John P. Albers 1.
Isotope - Cs - 137 Maximum Amount - 130 Ci Experience at San Onofre Nuclear Generating Station Unit 1 Duration - 3 years Type of Use - Calibration 2.
Isotcpe - Ra - 226 Maximum Amount - 50 nCi Experience at San Onofre Nuclear Generation Station Unit 1 2
Duration - 3 years Type or Use - Calibration 3.
Material - Mixec Fussion Procucts anc Activatec Corrosien Products Maximum Amount 150 Ci Experience at San Onofre Nuclear Generating Station Unit 1 Duration - 3 years Type of Use - Solic waste Shipments 4.
Material - Cs-137 Maximum Amcunt - 5 mci Experience at Pacific Gas & Electric Ccmpany/ Department of Engineering Research Duration - 6 months b
n s
Table 2.1-3 TRAINING Stephen P. Corey l2 On Tte Formal Type of Training Where Trained Duration Job Course 1.
Principles and Practices a.
Rockwell International Energy of Radiation Protection Systems Group 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> X
b.
Southern California Edison Division Laboratory 6 months X
c.
San Onofre Nuclear Generating Station 5 years X
2 2.
Radioactivity Measurement Same as above Standardization and Monitoring Techniques and Instruments 3.
Mathematics and Calculations San as above basic to the use and measurement of radioactivity 4.
Biological Effects of Radiation Same as above
Table 2.1-4 EXPERIEtCE WITH RADIATIUN Stephen P. Corey
.l.
Isotope - Cs - 137 Maximum Amount - 130 Ci Experience at San Onofre Nuclear Generating Station Unit 1 Duration - 3 years Type of Use - Calibration 2.
Isotope - Ra - 226 2
Maximum Amount - 50 cCi Experience at San Coofre Nuclear Generating Station Unit 1 Duration - 3 years Type of Use - Calibraticn 3.
Material - Mixed Fissica Procucts Maxirrum Amcunt - 120-150 Ci Experience at San Crofre Nuclear Generating Station Unit 1 Curation - 3 years.
. Type of Use - Spent Resin Shipments e
a 4
+1.
Appendix A The names of SCE's Principal officers, all of whom are citi ens of the Unitea States, are as follows:
14ame Position Williant R. Gould Chairman of the Board IIowaro P.
Allen President 11. Fred Christie Executive Vice President and Chief Financial Officer Davic J.
Fogarty Senior Vice President A.
Arenal Vice President G. J.
Bjorklund Vice President RoDert Dietch Vice President
,^
C.
E.
!!athaway Vica President Joe T.
12ead, Jr.
Vice President P.
L. clartin Vice President A.
L. Maxwell Vice President and Comptroller Edward A. Myers, Jr.
Vice President Michael L. Noel Vice President and Treasurer L. Y.
Papay Vice President William H.
Seaman Vice President lucert L. Umbaugh Vice President Vice President D. bunte John R.
Dury General Counsel ilonor Muller Secretary The accress of all the foregoing principal officers of SCE is:
2244 Walnut Grove Avenue l2 Post Office Box 800 Rosemead, California 91770 O
1
.g A-1
Appendix B i
The names of SDG&E's principal officers, all of wnom are citizens of the United States, are as follows:
llame Position Robert E.
Morris President and Chief Executive Officer Tnomas A.
Page Executive Vice President and Chief Operating Officer Gorcon Pearce Vice President and General Counsel J.
itocert belt Vice President Gary D.
Cotton Vice President Alton 'i. Davis Vice President 2
Frank W.
DeVore Vice President David W. Gilman Vice President John E. Itamrick Vice President James J. fiolley Vice President Wiliiam J.
Karnes Secretary Richard Korpan Vice President and Treasurer italph L. Meyer Vice President a
tiobert E.
Parsley Controller R.-Denis Richter Vice President Ronala W. Watkins Vice President Jack E. Thomas Vice President The address of all the foregoing principal of ficers of SCG&E is:
101 Ash Street San Diego, California 92101 9
i B-1 v.
2_----
Appendix C New Fuel Storage Safety Evaluation 1.
New Fuel Storage Racks A multiplication factor of less than 0.93 is.aaintained in the new f uel storage racks under the following conditions:
A.
The fuel rack is infinite in lateral extent.
Vertical cuckling properties are taken into account by repre-senting the fuel at its nominal active length, and 2
placing concrete slabs above and below the rack to provide reflection due to the floor and ceiling.
B.
Water vapor within the rack can assume any density up to 1.0 gm/cm3; taus the entire range of moderation is taken into account.
C.
The rack is fully loaded with 3.7 w/o Combustion Engineering 16 x 16 fuel (the most reactive fuel available).
D.
The temperature is 680F.
C.
No ournacle poison rods or CEA's are present.
F.
Structural support memoers are neglected for conservatism.
The computer codes employed in the criticality analysis of the new fuel storage racks are as follows:
A.
The KENO-IV Code KENO-IV is a three dimens1;nal, multi-group honte Carlo criticality coce which solves the Boltzmann transport values.
KENO-IV contains its equation to determine keff own 16-group Hansen Roach cross section library.
G.
The HAMMER Code HAMMER is a multi-group integral transport theory code which is used to calculate lattice cell cross sections values.
This code has been extensively bench-and k "kgainst D O and light water moderated lattices markeb 2
with good results.
To check the accuracy of KENO, fuel pin k values were determined using both KENO-IV and HAMMEknknd then compared to assure their agreement to within 1%.
Thus HAMMER was used only to check accuracy.
C-1 t.
~
r Parametric variations affecting nuclear characteristics c:
the racks were studied.
These variations result from events shich aay be categorized as normal and acnormal.
!:ornal variations include variation of H,0 densities, fuel eccentrically positioned within a' storage cell, fuel enrichment variation, storage cell pitch variation, and the cumulative effect of all of tne above, the worst case normal configuration.
Abnormal variations include effects of fuel nandling incidents, large moderator density variations, dropped or compacted fuel, and cell displacement due to seismic events.
The abnormal variation resulting in the highest increase in tne magnitude of k gg is chosen to represent the worst case e
aonormal configuration.
A margin of error resulting from calculational uncertainty is added to the numerical results.
itesults Tne k,, values determined for the new fuel storage racks 9
aay ce'sumaarized as follows:
K of the new fuel storage rack dry at 0.55 efgeBor at nominal dimensions K,ff of the new fuel storage rack including 0.72 2
etfects of normal variations and calcula-tional uncertainty O.81 Final k,gg of the new fuel storage rack inclucing normal variations and calcula-tional uncertainty in worst cast acnormal configuration II.
Soent Fuel Storage Racks A aultiplification factor less than 0.98 is maintained in tne spent fuel storage racks for new fuel assemblies stored dry under the following conditions:
A.
Every other storage row and column in the spent fuel
_ storage rack is left vacant (1/4 loading of tne storage rack).
B.
The fuel rack is infinite in lateral extent.
Vertical buckling properties are taken into account by repre-senting the fuel at its nominal active length, and placing concrete slabs above and below the rack to provide refl,ection due to-the floor and ceiling.
C-2
9 C.
Water vapor within the rack can assume any density up to 1.0 gm/cm3; thus, the entire range of moderation is taken into account.
D.
Yne rack is 1/4 loaded (see A.
above) with 3.7 w/o Comoustion Engineering 16 x 16 fuel (the most reactive tuel available).
C.
The temperature is 68oF.
F.
No burnable poison rods or CEA's are present.
G.
Structural support memoers are neglected for conservatism.
The computer code employed in the criticality analysis of new fuel stored dry in the spent fuel storage racks is as follows:
2 The KENO-IV Code KENO-IV is a three dimensional, multi-group Monte Carlo criticality code which solves the Boltzmann transport values.
KEMO-IV contains its equation to determine keff own 16-group Hansen Roach cross section library.
The most significant abnormal configuration parameter affecting fuel in dry storage is the moderator density variation which could occur if the storage area were flooded or, in the case of fire, filled with foam or steam.
Tne entire range of water densities from 1.0 x 10-6 gms/cm3 to 1.0 gms/cm3 was considered by performing multiple calculations at different water densities for eacn storage pattern under consideration.
Other normal design and fabrication variations, such as pitch, eccentricity of fuel, etc., are insignificantly small
( A k < 0. 001) for fuel in dry storage and need not be considered.
Other abnormal vccurrences such as fuel drop and improper positioning of fuel result in substantially smaller keff values than those obtained from the moderator density variations, ano therefore, can be ignored.
O C-3
1
- r nesults The pattern in wnien the rack is loaded to one-quarter capacity results in a :aaxiraum k,, value of 0.87 at a water e
2 censity of 1.0 gms/cu3.
"Au tnis'ilready conservative k,,,
value,:a
'x gt = 0.01 margin of uncertainty can be acded'Eo e
arrive at a final value of 0.b8 for tne maxiaura keff.
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)e NSTF Physical Inventorv Record Item Control Area Three Only (Suberitical Reactor)
Date:
Inventoried by:
- Piece count on Fuel Slugs _=
Nu:nber of Pu-Be Sources in tank =
9 Me 4
M.
+
oe O
99 9
Reported on By:
a4 * '
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