ML19319E084
| ML19319E084 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/04/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8003310594 | |
| Download: ML19319E084 (6) | |
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Docket No. $0-312 MG M
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Mr. E. E. Davis, Geneml Counsel Sae mmento MLmicipal Utility District 6201 S Stmet, P. O. Box 15830 Bacramento, California 95813
Dear Mr. Davis:
We find that we need additional infomation to co::plete our mview of your application for an operating license for the Rancho Seco Nucimer Genenting Station. 'the specific infomation required is described in s.
the enclosure and has been estegorized into groups which generally correspond to applicable section headings in the Final Safety Analysis Report.
We have not completed our review of the subject ratters covend in this request for additional information. At a later data ve vill request additional infor ation, if necessary, on these subject matters and others not addressed herein.
In order to maintain our licensing review schedule we vill need a com-plately adequate msponse by August 26, 1972. Please inform us within seven days after receipt of this letter of your confirmation of the g
sehedule or the date you will be able to meet. If you estuwt meet our specified date or if your uply is nut fully mopensive to our requests it is highly likely that the overall sehedule for completing the licensing review for t' is project will bave to be extended. Since reassignment of the staff's efforts vill requin completion of the new assignment prior to a turning to this project, the extent of extension vill most likely be greater than the extent of delay in your msponse.
Please contact us if you have any questious Mgarding the enclosed reg'.msts.
Eineerely, Origfael Signed by L 8. heYeong R. C. DeYoung, Assistant Director for Pmesurized Water Beactors Directorate of Licensing Boeleeure: See attaehed l
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Enclosure:
Request for Additional Infor,ation ces Davis S. Kaplan 5scretary and Attoeney 6G01 S Street P. o. Box 15839 n g' Seersmento, California 95813 DISTRIBUTION:
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REQUEST FOR ADDITIONAL INFORMATION SACRAbw MUNICIPAL UTILITY DISTRICT
_ RANCHO SECO N'JCLEAR POWER FIANT E0CKET NO. 50-312 90 DESIGN BASES - STRUC'IURES AND EQUIPMENT 5.78 For penetration numbers omitted from FSAR h ble 5 2-2 and Figure 5 2-9, such as the transfer canal tube, discuss the function and isolation capability of the penetrations.
6.0 ENGINEERED SAFETY FEATURES 6.10 Under post-DPA conditions, the reactor buildin6 emergency sump may contain debris that could be dmwn into the systems taking suction from the sump unless preventive measures are taken; therefore, describe the protective screen assembly that vill be used to prevent debris, capable of clogging the reactor building spmy system nozzles, from entering the su=p suction piping.
Provide assurance that the failure of a portion of the screen assembly will not negate the effectiveness of the entire assembly.
Specify the screening surface area that will be available. Pro-vide drawings showing the physical arrangement of the assembly within the sump.
6.11 Two of the emergency cooling units are equipped with activated charcoal filters for air cleanup and removal of fission products.
Specify the type of activated charcoal used. Also, calculate the expected charcoal filter temperature, assuming 50% release of iodine from the core and only one of the uni:s is operative.
Further, calculate the expected charcoal filter temperature assuming subsequent inoperability of the unit. Discuss the design provisions to prevent iodine desorption or charcoal ignition.
6.12 Discuss the design bases for the emergency cooling unit housing and describe the pressure relief dampers. Provide an analysis of damper performance under design basis accident conditions showing that they are capable of preventing possible damage to the housings due to a sudden pressure change.
6.13 With regard to the emergency upper dome air circulators, provide the following information:
6.13 1 Discuss the design provisions that assure the ductwork vill remain intact in the event of a design basis accident.
~2-6.14 Under post-DPA conditions, it is important that the nactor building atmosphere be thoroughly mixed to prevent hydrogen pocketing and assure the effectiveness of the containment heat removal systems; therefore, provide the following 'nforation:
6.14.1 Discuss the capability of the reactor building emergency cooling system and the emergency upper dome air circulators to thoroughly mix the building atmosphere, including the air within building compartments, considering that the air flow ductwork of the normal ventilation system will not be used.
6.14.2 To what extent must the emergency upper dome air circulators be relied on to aid in mixing the reactor building atmosphere?
6.14.3 Provide the results of tests which have been performed or describe the nature of tests that will be performed to verify the capability of the emergency cooling system and emergency upper dome air circulators to thoroughly mix the reactor building atmosphere.
3-70 INSTRUMENTATION AND CONTROL SYSTEMS 7 33 Gection 6.2.2.1.2 of the FSAR describes the procedure for transferring the spray cystem pump suction from the bomted water storage tank (NST) to the reactor building emergency cump. Provide a malfunction analysis of the monitoring instrumentation and. control circuitry to assure that no single electrical fault will pmvent the tmnsfer to the reciret.'.stion mode.
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14.0 SAFETY ANALYSIS 14.11 Provide the containment response analyses for the spectrum of reactor inlet pipe breaks. Include the effect of steam generator stored energy on the containment response.
14.12 For the purpose of performing an independent assessment of the reactor building pressum response under IOCA conditions, provide the following information:
14.12.1 P* ovide a curve of fan cooler performance showir.g energy removal rate as a function of containment atmosphere temperature.
14.12.2 For each of the mactor inlet and outlet pipe breaks analyzed
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(FSAR Table 14.4-6 and Request 14.11), provide a table of fluid mass flow rate (1b/hr) and internal energy (Etu/lb) as a function of time (hr) for the initial blowdown period of the accident.
14.12 3 For each outlet pipe break analyzed above, provide tables of energy release rate (Btu /lb)/hr), internal energy (Btu [1b), and the fluid mass flow rate (lb as a function of time (hr) following the completion of blowdown for post-blowdown energy cources, such as boil-off of the reflooding water and core decay heat.
14.12.4 for reactor inlet pipe bmaks, provide the information requested in questions 14. 2.2 and 14.2 3, above, but include the stored energy in the steam generators.
14.12 5 Specify the assumed efficiency of the spray droplets in cooling the reactor building atmosphere.
14.12.6 Gpecify the assumed air tempemture outside the mactor building nnd the minimum mactor building operating temperatures.
14C HYDROGEN PURGING 14C.1 Provide the following information with respect to the hydrogen monitoring equipment:
14C.1.1 Clarify how the reactor building radiation monitoring system can be used to monitor the hydroge t concentration in the building (refer to FS4R Appendix 14C, Section 140.6.2.