ML19352A868
| ML19352A868 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, 07002901, 07002940, 07002882  |
| Issue date: | 05/21/1981 |
| From: | Crow W, Stevenson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19352A858 | List: |
| References | |
| NUDOCS 8106020247 | |
| Download: ML19352A868 (6) | |
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SAFETY EVALUATION REPORT SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY APPLICATION DOCKETED BY NRC ON JULY 31, 19~/8, AND THE SUPPLEMENTS THERET0 DATED DECEMBER 13, 1978, OCTOBER 27, 1980, AND JANUARY 5, 1981 FOR A STORAGE LICENSE FOR FUEL AND ACCESSORIES FOR THE SAN ON0FRE NUCLEAR GENERATING STATION, UNITS 2 and 3-00CKETS 70-2882, 70-2901 AND 70-2940 Southern California Edison Company and San Diego Gas and Electric Company (the applicants) request licenses to receive 4260 kilograms of U-235 as uranium enriched up t.o 2.91% in the U-235 isotope contained in reactor fuel assemblies, 35 grams of U-235 contained in fission chambers, 100 curies of Pu-238 and associated isotopes contained in encapsulated neutron startup and calibration
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sources, and two, one-curie encapsulated AmBe sources for use in bcron measuring devices.
NRC Materials License No. SNM-1844 was issued to the applicants on January 2, 1979 to allow them to receive approximately 20 grams of U-235 in fission chanbers and amended January 28, 1980 to increase the allowed possession limit to 35 grams U-235 in fission chambers, as requested by the applicants on December 10, 1979.
License No. SNM-1844 was further amended on January 13, 1981 to authorize possession and use of two Amte sources in devices to measure the boron concentration in the primary coolant.
License No. SNM-1844 is being superseded by issuance of new licenses for Units 2 and 3 (SNM-1879 and SNM-1852, respectively) which themselves will be terminated upon issuance of operatirg
. licenses for the units.
Each reactor-specific license will cover the fuel for only that reactor (2130 kilograms U-235) but will cover all of the sources and fission chambers now covered by SNM-1844, since the licensees need that flexibility in their storage and use.
The neutron sources and fission chambers are to be stored at the San Onofre facility under the jurisdiction of the Radiation Protection Group.
The fission chambers will be stored in locked cabinets in the health physics area.
The neutron startup sources will be stored in their shipping containers, and the neutron calibration sources will be stored in the calibration facility in the health physics area.
The AmBe sources for the boron measuring devices will be stored in their shipping containers until installation.
The standard license condition regarding leak testing of sealed sources will be made a part of each license.
The fuel assemblies which t%e applicants wish to receive contain uranium enriched in the U-235 isotope.
Nominal enrichments are 1.87, 2.38, and 2.88%
Because of measurements and enrichment variations usually encountered, it is proposed that a maximum U-235 enrichment of 2.95% be authorized.
The fuel, which will be used in pressurized water reactors, is to be supplied by l
Combustion Engineering, Inc.
The 4260 kilograms (2130 kilograms for each l
unit) of U-235 is contained in 434 fuel assemblies, an average of 9.8 kilog:ams per assembly.
00 02 0 Q
2 The fuel assemblies will be stored in their shipping containers, in the new fuel storage racks, and in the spent fuel storage racks.
The new fuel storage facility is part of the fuel-handling building, a Seismic Category I structure.
A separate fuel handling building is provided for each reactor unit.
The spent fuel storage facility is also a part of the fuel handling building.
Structural deformations are limited and center-to-center spacing of assemblies is maintained under all anticipated loading conditions, including the design basis earthquake.
The new fuel will be stored dry in both the new fuel racks and in the spent fuel storage pool.
The applicants provided nuclear criticality safety analyses to demonstrate the subcriticality of the storage arrangements without water or with water at a range of densities in the arrays.
The safety of both the new storage and spent fuel storage racks was independently verified.
(See attached memorandum dated March 15, 1979, from C. Marotta to J. Delaney.
Although Marotta's memorandum does not address the condition of low density interspersed moderator in the spent fuel pool, the applicants' calculations for this condition are supported by the calculations reported in Nuclear Technology, May 1980, pages 251-260.)
In addition, it has been determined that slightly more than two fuel assemblies are required in order to attain criticality.
Accordingly, the licenses will be conditioned to restrict the fuel that can be out of approved shipping containers or storage locations to one assembly.
It is the Staff's opinion under these conditions that the applicants have
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established teasonable and, sat _isfactory preca_utions to. avoid. accidental criti-cality.
The applicants' industrial security program has been reviewed and it is the Staff's opinion that the program is satisfactory.
The applicants have also described the basic aspects of the radiation safety control program, including a description of the training and experience of personnel responsible for administering the program.
The Staff has concluded that the applicants' radiation safety program and personnel are adequate to allow them to reasonably carry out the activities for which a license is recuested.
The applicants have requested, pursuant to 10 CFR 70.24(d), an exemption from the provisions of 10 CFR 70.24.
Based on the applicant's demonstration of subcriticality under normal and accident conditions, good cause exists for exemption from the requirements of 10 CFR 70.24.
Because of the inherent features associated with the storage and inspection of enirradiated fuel containing uranium enriched to less than 5% in the U-235 isotope, the staff determines that granting such an exemption will not endanger life or property i
or the common defense and security, and is in the public interest.
This exemption is authorized pursuant to 10 CFR 70.14.
The NRR Project Manager, Mr. H. Rood, and the Resident Inspector, Mr. R. J. Pate, have stated that they have no. objection to issuance of the licenses.
3 CONCLUSION Based on the facts summarized in the foregoing paragraphs, the Staff believes that the proposed activities can be performed without undue risk to the health and safety of the public.
It has been determined by the Staff ti,at the applicant fulfills the requirements of 10 CFR 70.23(a).
Further, the issuance of this license is not a major Federal action significantly affecting the quality of the human environment and thus, pursuant to 10 CFR Sl.5(d)(4), no' environmental impact statement, negative declaration, or environmental appraisal need be prepared.
RECOMMENDATION The Staff recommends approval of the application and the exemption of the licensees from the requirements of 10 CFR 70.24.
Is*
R. L. Stevenson l
Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety Approved By: ff4. h /h W. T. Crok, Section Leader F
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LICENSE CONDITION FOR LEAK TFSTING SEALED BYPRODUCT MATERIAL SOURCES
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A.
Each source shall be tested for leakage at intervals not to exceed six (6) months.
In the absence of a certificate from a transferor indicating that a test has been made within six (6) months prior to the transfer, the swaled source shall not be put into use until tested.
B.
The test shall be capable of detecting the presence of 0.005 micro-
", curie of contamination on the test sample. The test sample shall
'be taken from the at :rce or from appropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored.
Records of leak test results shall be kept in
.-. units of microcuries and maintained for inspection by the Commission.
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~ P':T C. OIf the test reveals the presence of 0.005 microcurie or more of g,jf fremovable contamination, the licensee shall immediately withdraw
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..:;.the sealed source from use and shall cause it to be decontaminated 4- @y R,
.M['@Wepairsortobedisposedofinaccordancewiththe-Commission
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d repaired by a person appropriately licensed to make such MHgp
' % sourca has leaked, d e licensee shall file a,er=4n4=g that any
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' ' 7 M egula_tions. Within five (5) days after det report wit'h the Wgf3'55-
!?-) Director, Division of Fuel Cycle and Material Safety, U.S.- Nuclear M.~.C G. ~w.
W egulatory Commission, Washington, D.C.
20555, describing the 7"
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-nource, the test results. the extent of contamination, the apparent Z'u 9]%rsuspectedcauseofsourcefailure,andthecorrectiveaction
a,";;.'
.'-taken. A copy of the report shall be sent to the Director of the
? nearest NRC Inspection and Enforcement Office listed in Appendix D
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E [of Title 10 Code of Federal Regulations, Part 20.
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- e D.' $7he periodic leak test required by this condition does not spely to
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. sealed sources that are stored and not being used. The sources fi
.;.; excepted from this test shall be tested for leakage prior to any
-.use or transfer to another person unless they have been leak tested within six (6) monthe prior to the date of use or transfer.
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_ LICENSE CONDITION FOR LEAK TESTING SEALED PLUTONIUM SOURCES i
A.. Each plutonium sourc'e shal1 be tested for leakage at intervals not
.to exceed six.(6) months.
In the absence of a certificate from a transferor indicating that.a test has been made within six (6)-
months prior to the transfer, the sealed source shall not be put into use until tested.
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B.,,The test shall be capable of detecting the presence of 0.005 micro-curies of alpha contamination on the test sample.
The test sample shall be taken from, the source or from appropriate accessible i
surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored.
Records of leak test results s
shall be.kept in units of microcuries and maintained for inspection by the Comission.
C.
If.the. test reveals the presence of 0.005 microcurie or more of remov'able alpha contamination, the licensee shall immediately with-draw the sealed source from use and shall cause it to be decontami-nated and repaired by a person appropriately licensed to make such repairs or-to be disposed of in accordance with.the Commission regula-tions.
Within five (5) days after determining that any source has le.aked, the licensee shall file a report with the Division of Fuel Cycle and Material Safety, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, describing the source, the test results, the extent of contamination, the appar,ent or suspected cause of source failure, and the corrective actien taken.
A copy of the report shall be sent to the Director of the nearest NRC Inspection and
. Enforcement Office 1.isted in Appendix D of Title 10, Code of Federal Regulations, Part 20.
D.
The periodic 1cak test required by this condition does not apply to sealed sources that are stored and not being used.
The sources excepted from this. test shall be tested for leakage prior to any use or vansfer to another person unless they have been leak tested within six (6) months prior to the date of use or transfer.
U.S. Nuclear Regulatory Comm..'ssion Divirion of Fuel Cycle and Material Safety' Washington, D.C.
20555 l
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g UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
p WASHINGTON, D. C. 20555 *
+o 70-2940 70-2910 Docket No. 50-206 AMENDMENT TO INDEMNITY AGREEMENT NO. B-31 NIENDMENT NO. 14 MAY 21181 Effective
, Indemnity Agreement No. B-31, between Southern California Edison Company and San Diego Gas and Electric Company, and the Atomic Energy Comission, dated June 3,1966, as amended, is hereby further amended as follows:
Item 3 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 3 License number or numbers SNM-962 (From 12:01 a.m., June 3,1966 to 12 midnight, March 26, 1967, inclusive)
DPR~13 (From 12:01 a.m., March 27,1967)
SNM-1879 (From 12:01 a.m.,
MAY
- SNM-1852 (From 12:01 a.m:,
211981
)
)
MAY 211981 F0 THE UNITEDJIATES !<
R REGULATORY COMMISSION ero zman, As tant rector State and License elations Office of State Programs Accepted
, 1981 By SOUTHERN CALIFORNIA EDIS0N COMPANY Accepted
, 1981 By SAN DIEGO GAS AND ELECTRIC COMPANY
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,7,s
- UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
/
70-2940 70-2910 Docket No. 50-206 l
AMENDfiENT TO INDEMNITY AGREEMENT NO. B-31 AMENDMENT NO.14 Effective N Y 2 1 1981
, Indemnity Agreement No. B-31, between Southern California Edison Company and San Diego Gas and Electric Company, and the Atomic Energy Commission, dated June 3, 1966, as amended, is hereby further amended as follows:
Item 3 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 3 License number or numbers SNM-962 (From 12:01 a.m., June 3,1966 to 12 midnight, March 26, 1967, inclusive) i DPR-13 (From 12:01 a.m., March 27,1967)
}
(From 12:01 a.m.,
)
SNti-1879 (From 12:01 a.m., MY 21188I
)
SNM-1852 E Y 2 1 198I i
I F
THE UNITED _SIATES N LEAR REGULATORY COMMISSION t
istant Director State and Licen e Relations Office of State Programs Accepted
, 1981 4
By SOUTHERN CALIFORNIA EDISON COMPANY Accepted
, 1981 By l
SAN DIEGO GAS AND ELECTRIC COMPANY
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ka te?
UNITED STATES o,
NUCLEAR REGULATORY COMMLsslON WASHINGTON, D. C. 20555 s-70-2940 70-2910 Docket No.
50-206 AMENDMENT TO INDEMNITY AGREEMENT NO. B-31 AMENDMENT NO. 14 Effective Indemnity Agreement No. B-31, between Southern California Edison Company and San Diego Gas and Electric Company, and the Atomic Energy Commission, dated June 3, 1966, as amended, is hereby further amended as follows:
Item 3 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 3 License number or numbers SNM-962 (From 12:01 a.m., June 3, 1966 to 12 midnight, March 26, 1967, inclusive)
DPR-13 (From 12:01 a.m., March 27,1967)
SNM-1079 (From 12:01 a.m.,
gay 2 1 1961
)
SNM-1852 (From 12:01 a.m.,
)
MAY 211081 FOR HE UNITE p a % NU R REGULATORY COMMISSION
'J o, um s Sa zman, Assi ant Di ector State and Licensee lations Office c State Programs Accepted 1981 By SOUTHERN CALIFORNIA EDISON COMPANY Accepted
, 1981 By SAN DIEGO GAS AND ELECTRIC COMPANY e
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