ML13303A502
| ML13303A502 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/04/1981 |
| From: | Chandler L NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Hand C, Johnson E, Kelley J Atomic Safety and Licensing Board Panel |
| References | |
| ISSUANCES-OL, NUDOCS 8106050506 | |
| Download: ML13303A502 (16) | |
Text
J UN-0 4 198 1 June 4, 1981oro James L. Kelley, Esq., Chairman,DrCaeH.anJ, V
O Administrative Judge Amnsrtv ug Atomic Safety and Licensing Board coBdg aieLbrtr U.S. Nuclear Regulatory Commission Uiest~fClfri Washington, D. C. 20555 P. 0. Box 247 Bodega Bay, California 94923 Mrs. Elizabeth B. Johnson, Administrative Judge Oak Ridge National Laboratory P. 0. Box X, Building 3500 Oak Ridge, Tennessee 37830 In the Matter of SOUTHERN CALIFORNIA EDISON COMPANY, ET AL.
(San Onofre Nuclear Gener t'g Station, Unit'sand 3)
Docket Nos. 0-361 L and 50-362 OL
Dear Members of the Board:
.By letter dated March 6, 1979 I informed you that the Staff was reviewing the application of Southern California Edison CompanyI et al.
for the issuance of special nuclear materials licenses in connection with
.San Onofre Units 2 and 3. In subsequent letters, I advised you of the issuance of Special Nuclear Materials License, No. SNM-1844, and of amend ments thereto.
This is to inform you that, on May 21, 1981, the Staff issued Special Nuclear Materials Licenses Nos. SNM-1879 and SNM-1852. Special Nuclear Materials License No. SNM-1844, as amended, is superseded b~y issuance of these licenses. A copy of the relevant correspondence is enclosed.
Sincerely, Lawrence J. Chandler Deputy Assistant Chief Hearing Counsel
Enclosure:
As stated See cc's next -page OFFICEO SURNAMEOL BATE 41 NRc-osins FOM31 1/8)NcM0240 OFFICIAL RECORD COPY
- USGPO: 1980-329-824
cc w/enclosures Janice E. Kerr, Esq.
David R. Pigott, Esq.
Alan R. Watts, Esq.
Richard J. Wharton, Esq.
Mrs. Lyn Harris Hicks Charles R. Kocher, Esq.
David W. Gilman Atomic Safety and Licensing Board Charles McClung, Jr., Esq.
Atomic Safety and Licensing Appeal Board Phyllis M. Gallagher, Esq.
Secretary A. S. Carstens Distribution:
Document Mgt. Br.
Shapar/Engelhardt Christenbury/Scinto Rutberg Vogler Hoefling Chandler Chandl er/Chron FF (2)
F:Miraglia H. Rood OFFICEO SURNAME DATE NRC FORM 318 10/80 NRCM 0240 OFFICIAL RECORD COPY
- USGPO: 1980-329-824
MAY 2 1 1981 FCUF:RLS 70-2882 70-2901 70-2940 Southern California Edison Company ATTN:
Mr. R. Dietch, Vice President Nuclear Engineering and Operations
'P.O. Box.800 2244 Walnut Grove Avenue
-Rosemead, California 91770 Gentlemen:
Enclosed are NRC Materials License No.
SNM-1879 and SNM-1852 that authorize the receipt, possession, inspection, and storage of fuel and accessories for eventual use in the San Onofre Nuclear Generating Station, Units 2 and 3, respectively. The possession limits in these licenses include the nuclear materials formerly licensed under NRC Materials License No. SNM-1844, which is therefore superseded.
In addition, the licenses authorize the packaging of fuel assemblies for delivery to a carrier. This latter authority enables you to return fuel assemblies to their shipping containers if there is a need to transfer the assemblies to another location, e.g., return to the manufacturer. The delivery of the assemblies to a carrier must be in accordance with 10 CFR Part 71, "Packaging of Radioactive Material for Transport and Transportation of Radioactive Material Under Certain Conditions," copy enclosed. In this regard, your attention is directed to §71.12(b) of Part 71 that provides a general license under specified conditions for the use of certain shipping packages that have been authorized by the NRC for use by another licensee.
Also enclosed are three copies of Amendment No. 14 to Indemnity Agreement No. B-31 for your review, acceptance, and the return of one signed copy.
The Nuclear Regulatory Commission (Commission) uses an electronic data processing system to record the location by licensee, of special nuclear material.
This system uses a three-letter Reporting Identification Symbol to identify licensees who submit material transfer reports and periodic material status reports in accordance with §§70.53 and 70.54 of the Commission's Regulations, 10 CFR Part 70. For this purpose, you have been assigned the following Reporting Identification Symbols:
XRF and XUR for Units 2 and 3, respectively. :These symbols are to be used in completing the transaction reports and periodic material status reports and should be used in any other correspondehce with the NRC relative to such reports. You should also note the requirements of §70.51(b), (c), and (d) regarding records, material control and accounting procedures, and physical inventories. Your cooperation will be appreciated.
.%..0.
r.
Southern California Edison Company 2
MAY 2 1 98 Your application for licenses Irequested an exemption from the provisions of 10 CFR 70.24. Such an exemption would relieve you from the requirement of having a criticality alarm syst.-
Because of the inherent features associated with the storage an dinspection of unirradiated fuel, the NRC staff has determined that you have shown good cause for being granted the exemption and that granting such an exemption will not endanger life or property or the common defense and security and.is otherwise in the public interest.
The license conditions were discussed with and agreed to by Mr. T. Mercurio, representing Southern California Edison Company and San Diego Gas and Electric Company, and Mr. R. Stevenson of my staff.
Sincerely, original Signed by.
R. G. Page, Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosures:
- 1.
NRC Materials License No
-SNM1879
- 2.
NRC Materials License No. SM 1852
- 3.
Safety Evaluation Report
- 4.
- 5.
Amendment No. 12 to Indemnity Agreement No. B-31 (3 copies)
U. S. NUCLEAR REGULATORY COMMISSION Page 1 of 2
Pages MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 438). 'and Title 10, Code of Federal Regulations, Chapter 1, Parts 30, 31, 32, 33, 34, 35, 36, 40 and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s); and to import such byproduct and source material. This license shall be deemed to conttin the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee
- 1. Southern California Edison Cacpany San Diego Gas and Electric Campany
- 3. License number S -189
- 2.
Post Office Box 800 2244 Walnut Grove Avenue Poseneal California 91770
- 4. Expiration date Decmbr 31, 1982 or Docket or
- 5.
70-2940 Reference No.
- 6. Byproduct, source, and/or
- 7. Chemical and/or physical
- 8. Maximum amount that licensee special nuclear material form may possess at any one time under this license A.
aranium enriched A.
Contained in fission A.
Thirty-five (35) grans "in the U-235 isotope chambers of U-235 at any enrichment Uraninm enriced Contained in reactor E.
2130 kilograms of in the U-235 isotope fuel asseblies U-235 at an enrich aent not to exceed 2.95%
C.
Pu-238 and C.
Contained in doubly C.
100 curies associated isotopes encapsulated neutran sources D.
Americiav. 241 D.
Contained in doubly D.
2 curies encapsulated neutron sources
- 9.
Authorized use:
For use in accoroance with the statenents, representations and conditions specified in the licensee's application:
docketed by NRC on July 31, 1978, the suppleents thereto dated December 13, 1978, October 27, 1980, and January 5, 1981.
CODITIGE
- 10. 'Authorized Place of Use: The licensee's San Cnofre Nuclear Generating Station, U nit 2, as described in the aforesaid applicationi.
unon conversion of Construction Permit No. CPPR-97 to an operating license, hiebever is Parlier.
11h
'O 02,
Fo.m NRC-374A U. S. NUCLEAR REGULATORY COMMISSION Page 2 of 2 Pages MATERIALS LICENSE Supplementary Sheet License Number Docket or 70-2!4t Reference No.70_294_
- 11.
'lbe licensee shall canply with the attached 'License Cordition For Leak
.rstire Sealed Plutonium Sources" anc 'License Corition For Leak Testimr Sealed Byoroduct Material Sources".
- 12.
As a condition of this license, no more than one (1) fuel assmtly may be out of aproved shippim Containers or storage racks at any one ture.
- 13.
'The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials helC Tner this license.
- 14.
Procedures for smear tests and contamination control of the new fuel will be ceveloped and approved before fuel receipt.
If visual inspection of the fuel made on receipt indicates a possible contamination problen, sear tests will be rade and contamination control procedures initiated.
oU For the U. S. Nuclear Regulatory Commission MAY 2 1 1by Division of Fuel Cycle and Material Safety Washington. D.C. 20555
FnnNAC*7' U. S. NUCLEAR REGULATORY COMMISSION Page 1 of Pages MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Itle 10, Code of Federal Regulations, Chapter 1, Parts 30, 31, 32, 33, 34, 35, 36, 40 and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s); and to import such byproduct and source material. This license shall be deemed to contain the conditions specified in Section 183 of the Atonfic Energy Act of 1954, as amended, and is subject to all applicable rules, regula.
tions and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specifiea below.
Licensee 1.Southern California Edison Carpany San Diego Gas and Electric Cocaany nuber SW-1852 1~)S5~ad. California 917703.
Exiratns datberDcrbr31 92o 2 Post Office Box 800
'2244 Walnut Grove Avenue Biosenead,.California 91770
- 4. Expiration date December 311, 1982 cr*
Docket or 70-2901 5_ Reference No.
- 6. Byproduct, source, and/or
- 7. Chemical and/or physical
- 8. Maximum amount that licensee special nuclear material form may possess at any one time under this license A.
Uraniun enriched A.
Contained in fissin A.
Thirty-five (35) grams in the 0-235 isotope chanbers of U-235 at any enr ichnent B.
Uranim enriched B.
Contained in reactor B.
2130 kilograms of in the D-235 isotope fuel assblies -
U-235 at an enrich mnt not to exceed 2.95%
C.
Pu-238 and C.
Contained in doubly C.
100 curies associated isotopes encansulated neutron sources D..
Awericium 241 D.
Contained in doubly D.
2 curies encapsulated neutron sources
- 9.
Authorized use:
For use in accordance with the statenents, representations and conditions specified in the licensee's aplication docketed by ?tIC on July 31, 1978. the supplement thereto dated Decerber 13, 1978, October 27, 1980, and January 5, 1961.
CChiDITICS
- 10.
Authorized Place of Use: The licensee's San Onofre Nuclear Generating Station, Unit 3, as described in the aforesaid application.
uon conversion of Construction Permit No. CPPR-98 to an operatirr license, hichever is earlier.
7o 4
Z2*
"04U NRC-374A S. NUCLEAR REGULATORY COMMISSION Page 2 of 2 Pages MATERIALS LICENSE Suppleinentairy Sheet Ucense Number 85-1852 Docket or Reference No.__7_-_01 (contined~
- 11.
he licensee shall cmaply with the attached "License Corndition For Leak
'Oasting Sealee Plutonium Sources and "License Condition For Leak Testinm Sealed Eyoroduct M1aterial Sources".
- 12.
As. a condition of this license, no nore than one (1) fuel assembly rey be out of approved shipping containers or storawe racks at any one tire.
- 13.
Iflhe licensee is bereby exacted from the provisions of 10 CFR 70.24 insofar as this section arplies to materials held under this license.
- 14.
Procedures for smear tests and contamination control of the new fuel will be developed and approved before fuel receipt.
If visual inspectnr of the fuel eane on recePvt indicates a possible contamination problem, srear tests will be made and contarination control prced-ures initiated.
For the U. S. Nuclear Regulatory Commission MAY 2 10I1 Date by Division of Fuel Cycle and Material Safety Washington, D.C. 20555 I
.0 g
SAFETY EVALUATION REPORT SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY APPLICATION DOCKETED BY NRC ON JULY 31, 1978, AND THE SUPPLEMENTS THERETO DATED DECEMBER 13, 1978, OCTOBER 27, 1980, AND JANUARY 5, 1981 FOR A STORAGE LICENSE FOR FUEL AND ACCESSORIES FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 and 3 DOCKETS 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 to 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 sources, and two, one-curie encapsulated AmBe sources for use in boron 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 chambers 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 AmBe sources in devices to measure the boron concentration in the primary coolant. License No. SNM-1844 is being superseded bty issuance of--newilicenses for Units 2 and 3 (SNM-1879 and SNM-1852, respectively) which themselves will be terminated upon issuance of operating 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 the applicants wish to receive contain uranium enriched in the U-235 isotope. Nominal enrichments are 1.87, 2.38, and 2.88%
U-235. 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 Combustion Engineering, Inc.
The 4260 kilograms (2130 kilograms.for each unit) of U-235 is contained in 434 fuel assemblies, an average of 9.8 kilograms per assembly.
-L.
4 e
- 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 buildin?
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 storageracks was independently verified. (See attached memorandum dated March 15, 197 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 n order to attain criticality. Accordingly, the licenses will be conditione 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 established reasonable and satisfactory precautions to avoid accidental criti cality.
The applicants' industrial securi ty program has been reviewed and it is the Staff's opinion that the progiAis satisfactory.
The applicants have also descr bed the basic aspects of the radiation safety control program, including ad 'ription of the training and experience of personnel responsible for admin stering the program. The Staff has concluded that the applicants' radiationgifety program and personnel are adequate to allow them to reasonably carry out the activities for which a license is requested.
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 an'd 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 unirradiated 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 or the common defense and securt and is in the public interest. This exempti.on is authorized pursuan to 10 CFR 70.14.
The NRR Project Manager, Mr. H kbod, 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 that 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 51.5(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.
R. L. Stevenson Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety Approved By: O4.
W. T. Cro(, Section Leader
LICENSE CONDITION FOR LEAK TESTING SEALED BYPRODUCT MATERIAL SOURCES 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 sealed 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 source 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.
C.,7If the test reveals the presence of 0.005 microcurie or more of removable contamination, the licensee shall immediately withdraw
-the sealed source from use and shall cause it to be decontaminated
.d repaired by a person appropriately licensed to make such
-'"repairs or to be disposed of in accordance with the Commission egulations.
JWithin five (5) days after determining that any source has leaked, the licensee shall file a report with the 7Director, 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 apparent
--or suspected cause of source failure, and the corrective action
-taken.
A copy of the report shall be sent to the Director of the nearest NRC Inspection and Enforcement Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.
D.
The periodic leak 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 transfer to another person unless they have been leak tested
-within six (6) months prior to the date of use or transfer.
LICENSE CONDITION FOR LEAK-TESTING SEALED PLUTONIUM SOURCES A."I. Each plutonium 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 sealed source shall not be put into use until tested.
B. Tetest shall be capable of detecting the presence of 0.005 micr-o curies of alpha contamination on the test sample.
The test sample shall be taken from. the source 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 'ommlissi on.
C. if.the.-test reveals the presence of 0.005 microcurie or more of removable alpha contamination, the licensee shall immiediately 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 Commuiission regula tions.
Within five (5) days after 'determining that any source has leaked, the licensee shall file a report with the Division of Fuel.
Cycle and Material Safety, U.S.
Nuclear Regulatory-Commission, Was hi ngton, -D.
C. 2O55J-describing the source, the test results, the extent "of contamination, the appar ent or suspected cause of source failure, and the corrective action taken.
A copy of the report shall be sent to the Director of the nearest NRC Inspection and Enforcement Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.
D. The periodic leak 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 transfer to another person unless they have been leak tested within six (6) months prior to the date ofl use or transfer.
U.S. Nuclear Regulatory Conriission Division of Fuel Cycle and Material Safety" Washington, D.C.
20555
- UNITED STATES.
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 70-2940 70-2910 Docket No. 50-206 AMENDMENT TO INDEMNITY AGREEMENTNO. B-31 AMENDMENT NO. 14 MAY 2 11%
1 1
Effective
, Indemnity Agreement No. B-31, betwedn 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-1879 (From 12:01 a.m.,
MAY 21191
)
SNM-1852 (From 12:01 a.m.,
MY 2 1 m98 FOR 7HE UNITED N
R REGULATORY COMMISSION Sa zman, Assi ant Di ector State and Licensee lations Office of State Programs Accepted
.1981 By SOUTHERN CALIFORNIA EDISON COMPANY Accepted 1981 By SAN DIEGO GAS AND ELECTRIC COMPANY
REG o1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 70-2940 70-2910 Docket No. 50-206 AMENDMENT TO INDEMNITY AGREEMENT NO.
B-31 AMENDMENT NO. 14 Effective M1Indemnity Agreement No. B-31, between Southern California Edison Company and San Diego Gas and Electric Company, W '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-1879 (From 12:01 a.m.,
MAY 2 11981
)
SNM-1852 (From 12:01 a.m;,
)
MAY 2118 FO THE UNITED SN R REGULATORY COMMISSION Lero ~lfzman
, As.
tant rector State and License elations Office of State Programs Accepted 1981 By SOUTHERN CALIFORNIA EDISON COMPANY Accepted
, 1981 BySAN_________S__ND_______________
S AN DIEGO GAS AND ELECTRIC COMPANY
_,UNITED STATES NUCLEARREGULATORY COMMISSION WASHINGTON, D. C. 20555 70-2940 70-2910 Docket No. 50-206 AMENDMENT TO INDEMNITY AGREEMENT NO. B-31 AMENDMENT NO. 14 Effective MAY 2 1 1 ndemnity Agreement No. B-31, between Southern California Edison Copanfy and San Diego Gas and Electric Company, and the Atomic Energy Commission;:dated June 3, 1966, as amended, is hereby further amended as fo1 Item 3 of the Attachment to th demnity agreement is deleted in its entirety and the following sub tjtuted therefor Item 3 License number or nubers 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.,
ggy 2)11981 SNM-1852
- (From 12:01 a.m.,
)
FQ THE UNITED TES N LEAR REGULATORY COMMISSION me Sal zman, istant D tector.
State and Licen e Relatio s Office of State Programs Accepted 1981 By SOUTHERN CALIFORNIA EDISON COMPANY Accepted_1981 By SAN DIEGO GAS AND ELECTRIC COMPANY