ML19319E290
| ML19319E290 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/27/1978 |
| From: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| To: | OFFICE OF THE FEDERAL REGISTER |
| References | |
| NUDOCS 8004040562 | |
| Download: ML19319E290 (1) | |
Text
pa de roQ UNITED STATES :
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July 27, 1978
'CFFicE OF THE ~
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SECRETARY
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Director
-Office of the Federal Register:
National Archives and Records Service
' Washington, D. C.
20403
Dear Sir:
. Enclosed for publication in the Federal Register are an original and two' certified copies of a document entitled:
'::Y:
SACRAMENTO MUNICKPAL UTILITY DISTRICT g:;
Docket No. 50-312 j
J ORDER FOR MODIFICATION OF LICF'!SE 1
1 Publication of the above document at the earliest possible dar.e would b
.l be appreciated.
This material is to be charged to requisition number D-149.
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Sincerely, Samuel J. Chilk Secretary of the Commission
Enclosures:
Original and 2 certified copies bec: LRecoran.Fn"414 mErnnch Office of-Public Affairs yk['
Executive Legal Director
-Offic'e of' Congressional Affairs Office of the General Counsel
-SECY - C&R Branch'
- 800404o % 7 e
7590-01'
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UNITED STATES OF AMERICA l
NUCLEAR REGULATORY COMMISSION j
e In the Matter of-l SACPAMENTO MUNICIPAL UTILITY DISTRICT
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Docket No. 50-312 Rancho Seco Nuclear Generatiiig Station j
ORDER FOR MODIFICATION OF LICENSE I.
-The Sacramento Municipal Utility District (the licensee), is the holder of Facility Operating License No. DPR-54 which authorizes the operation of the nuclear power reactor known as Rancho Seco Nuclear Generating Station (the facility) at steady state reactor power levels not in excess 1
of 2772 megawatts thermal (rated power). The facility consists of'a j
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Babcock and Wilcox Company (B&W) designed pressurized water reactor (PWR) locat'ed at the licensee's site in Sacramento Countj, C11ifornia.
II.
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In accordance with the requirements of the Comission's Emergency Core
- Cooling System (ECCS) Acceptance Criteria,10 CFR 50.46, the licensee submitted on July 8,1975, an ECCS evaluation for the facility. The ECCS performance submitted by the licensee was based upon an ECCS Evaluation Model developed by B&W, the designer of the Nuclear Steam Supply System for this facility. The B&W ECCS Evaluation Model had been previously DOCUMENT DUPLICA'I 3 eviously Entire document prsystem 4
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into entered
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