ML20027C858
| ML20027C858 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/29/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027C857 | List: |
| References | |
| TAC-43460, NUDOCS 8210270317 | |
| Download: ML20027C858 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 g se /
SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The filing (which is being handled by the Comission as an application) by Sacramento Municipal Utility District (the licensee), dated April 3,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in confomity with the_ provisions of the Act, and theYu'les and regulations of the Comnission;
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I C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8210270317 820929
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PDR ADOCK 05000312 P
. 2.
Accordingly, Facility Operating License No. DPR-54 is hereby amended as indicated below:
A.
Add paragraph 2.C.(10) to read as follows:
2.C.(10) IAEA Safeguards The licensee shall implement Codes 2. through 7. of " Facility Attachment No. 3, dated April 16, 1982", to the U. S./IAEA Safeguards Agreement transmitted to the licensee via NRC letter dated August 6, 1982.
For purposes of this license condition, the Facility Attach-ment shall be interpreted as follows:
Facility Attachment Code 2.2 The types of modifications with respect to which informa-tion is required, under 10 CFR 75.11, to be submitted in advance are those items stated in Code 2.2.
e "Any change in the rated thermal output for continuous operations" means:
Any change that exceeds the rated thermal output for continuous operation as described in Paragraph 14 of the Design Information Questionnaire (DIQ) dated April 3,1981 or as modified in accordance with 10 CFR 75.ll(c).
e "Any change in the access routes to the reactor area" means:
Any new entrance / exits involving SNM fuel routes or any deletion or modification of existing entrances / exits involving SNM fuel or new openings other than those shown in paragraph 10 (Attachment 10-2) and paragraph 56 (Attach-ment 56.2) of the DIQ dated April 3,1981 or as modified in accordance with 10 CFR 75.11(c).
e "Any change in the design of the reactor fuel" means:
Any change in the design of the reactor fuel other than the specifications stated in paragraphs 24 (Attachment 24-1),
25, 26 (Attachments 26-1 and 26-2) and 27 of the DIQ dated April 3,1981 or as modified in accordance with 10 CFR 75.ll(c).
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. e "Any change in the nominal fuel enrichments of the fuel exceeding 3.5 w/o" means:
Any change in the fuel enrichment from that listed in paragraph 23 of the DIQ dated April 3,1981, or as modified in accordance with 10 CFR 75.11(c), that would exceed 3.5 weight percent U-235.
e "Any change of the refueling equipment or methods" means:
Any introduction of new, additional or modified equipment other than that described in paragraph 41 (Attachments 41-1, 41-2, 41-3, 41-4, and 10-4) of the DIQ dated April 3, 1981 or as modified in accordance with 10 CFR 75.ll(c).
e " Introduction of new loop heat removal equipment which will be required to increase the nominal rated core thermal power level" means:
Any introduction of new, modified or additional loop heat removal equipment which would permit increases in the core thermal output from paragraph 14 of the DIQ dated April 3, 1981 or as modified in accordance with 10 CFR 75.ll(c).
e "The installation of any fuel assembly, decladding or dissolution equipment" means:
The introduction of equipment necessary to extrdct special nuclear material from the fuel rods.
Facility Attachment Codes 3.1.3 and 5.1.2 e Procedures, as referred to in 10 CFR 75.21 ' include, among other things, the provisions for item counting and verification set out in Codes 3.1.3 and 5.1.2.
" Item counting and verification" means:
The continuation of the licensee's current physical inventory taking and material control and accounting procedures employed to verify the existence and/or location of SNM fuel assemblies as described in Attachment 55-5 of the DIQ dated April 3, 1981, or as modified in accordance with 10 CFR 75.11(c).
(Similar inventory data for required material control and accounting reports not generated as a result of a physical inventory, may be obtained from the licensee's records.)
. Facility Attachment Code 6.2 e " Concise Notes" means those reports that are required to be submitted pursuant to 10 CFR 75.34 and 75.35 on DOE /NRC F6rm 740M and prepared in accordance with printed instruc-tions for completing the form.
Facility Attachment Code 7.
o " Inspection" means:
Inspection or inspections as described in 10 CFR 75.42 and as conducted by duly authorized representatives (Inspectors) of the IAEA.
Facility Attachment Code 7.3 t
e Code 7.3 shall not be interpreted as requiring a minimum actual inspection effort or any obligation on the part of the licensee to assure that any such minimum actual inspection effort is applied.
"15-20 man-days per year if one refueling occurs" means the anticipated IAEA effort under ordinary circumstances.
Facility Attachment Codes 7.4.2 and 7.4.3 e " Verification of the inventory, e.g., by item counting and identification" means:
The IAEA inspection effort may include the verification of all, or any portion of, the licensee's SNM inventory (fuel assemblies in the core are subject to verification only during refueling and not at any other time).
l The IAEA's inventory verification procedures may include confirmation of the stated location and serial numbers of l
fuel assemblies using procedures that are practical and that are within both the IAEA's and the licensee's technical capabilities.
Facility Attachment Code 7.5 The Agency (IAEA) is normally permitted to routinely use portable equipment for their independent material verifications. However, notwithstanding incorporation of Facility Attachment Code 7.5 in this license, the installation of fixed equipment pursuant to said Code 7.5 is not required except in accordance with such additional conditions as may subsequently be added to this license.
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. Facility Attachment Code 7.9.1
" Office space for the Agency's inspectors" means:
e Simple, non-dedicated of fice space.
o " Power supply for the Agency's instruments" means:
Power supply for the Agency's portable measuring instru-ments.
Pursuant to the provisions of 10 CFR 75.41, the Commission will inform the Sacramento Municipal Utility District, in writing, when its installation is no longer subject to Article 39(b) of the principal text of the U. S./IAEA Safeguards Agreement. The IAEA Safeguards License Conditions incorporating Code 7 of the Facility Attachment as part of NRC License No. DPR-54 will be terminated as of the date of such notice from the Commission. However, since the IAEA may elect to maintain the licensee's installation under Article 2(a) of the Protocol, provisions equivalent to Codes 2 through 6 of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeguards License Conditions to NRC License No. DPR-54 will remain in effect until the Commission notifies the Sacramento Municipal Utility District otherwise.
If this option is not selected by the IAEA, the Commission will then notify the Sacramento Municipal Utility District that all License Conditions pertaining to the U. S./IAEA Safeguards Agreement are terminated.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR R GULATORY COMMISSION
. U./
Jo 1 F. Stolz, Chie 0
rating Reactors Branch #4 Division of Licensing l
Date of Issuance:
September 29, 1982 l
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