ML19317G671
| ML19317G671 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/16/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8003250725 | |
| Download: ML19317G671 (3) | |
Text
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Docket No. 50-312 JUN 1 8 EM Mr. E. K. Davis, General Counsel Sacramento Municipal Utility District 6201 S Street, P. O. Box 15830 Sacramento, California 95813
Dear Mr. Davis:
We find that we necd additional information to complete our review of your application for an operating license for the Rancho Seco Nuclear Generating Station. The specific information required is described in the enclosure and has been categorized into groups which generally correspond to appli-cable section headings in the Final Safety Analysis Report.
We have not completed our review of the subject eattere covered in this t
requeet for additional infornation. At a later date we vill request
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additional information, if necessary, on these subject matters and others not addressed herein.
In order to maintain our licensing review schedule ve will need a completely I-adequate response by July 19, 1972. Please inform us within 7 days af ter k
receipt of this letter of your confirmation of the schedule or the date you will be able to meet.
If you cannot meet our specified date or if your reply is not fully responsive to our requests it is highly likely that the overall schedule for completing the licensing review for this project will have to be extended. Since reassignment of the staff's efforts will require completion of the new assignment prior to returning to this project, the extent of extension will most like.ly be greater than the extent of delay in your response.
Please contact us if you have any questions regarding the enclosed requests.
Sincerely, R. C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing
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David S. Y,aplan, Secretary and Attorney 6201 S Street P. O. Box 15839 Sacramento, California 95813 DISTRIBITTION AEC PDR Local PDR Docket RP Reading PWR-4 Reading S. Hanauer R. S. Boyd R. C. DeYoung D. Skovholt P. Schroeder R. Maccary D. Knuth R. Tedesco H. Denton PWR Branch Chiefs R. W. Klecker OGC RO (3)
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REQUEST FOR ADDITIONAL INFORMATION SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 2.0 SITE 2.11 Specify the zone number in addition to the information you provided in response to question 2.6.
3.0 REACTOR 3.6 Jiscuss the quality assurance programs and quality control checks that are designed to assure. the mechanical integrity of your fuel over its anticipated lifetime including any design review effort.
review and audit of quality assurance measures and your planned inspections of the fuel upon delivery.
Indicate how your fuel design and manufacture will minimize possible failures from clad hydriding and UO2 - clad interaction.
6.0 ENCINEERED SAFETY FEATURES 6.9 Specify the expected dose rate at the decay heat removal pump suction lines during the post accident recirculation mode. Discuss the precautions taken to minimize radiation exposure to personnel during sampling and ph adjustment of the post accident cooling solution in containment.
9.0 AUXILIARY SYSTEMS 9.16 The spent fuel scorage facility ventilation system is a Class II (seismic) system. Discuss the radiological consequences of failure of' this system during a Design Basis Earthnuake coincident with
- cpglug of a fuel element durina refueling. Specify the release of radioactivity to the site boundary. Discuss the design changes you would make if the dose at the site houndary exceeds one percent of the limits specified in 10 CFR 100 which you have established
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in the FSAR as a criterion for requiring a Class 1 (seismic) design.
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