ML19320A266
| ML19320A266 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/31/1972 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004210554 | |
| Download: ML19320A266 (2) | |
Text
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AEC 1 RRMaccary Local PDR DKnuth Docket HDenton RP Reading PWR Branch Chiefs PWR-4 Reading RWKlecker SHHanauer OGC RSBoyd R0 (3)
RCDeYoung RMBernero Docket No. 50-313 DSkovholt EGoulbourne 007 3 I s73 FSchroeder JShapaker RTedesco Mr. J. D. Phillipe j
Vice President & Chief Eng4w Arkansas Power sad Light Company l
Sixth sad Fine Streets Fine Bluff, Arkansas 71601
Dear Mr. Phillips:
Onthebasisofouresse1NingreviewoftheFinsiSafetyAnalysisReport for the Arkansas Bealear One - Unit No. 1, we find that we need additional information to complate our evaluation. The specific information required is listed in the emelesere.
In order to maintain our lisensing review =ahad=1e we will need a completely adequate response by November 30, 1972. Please inform us within seven (7) j days after receipt of this letter of your confirmation of the schedule or i
the date you will be able to aset. If you cannot meet our specified date j
or if your reply is not fully responsive to our requests it is highly likely that the overall schedule for souplating the licensing review for this project will have to be extended. Since reassignment of the staff's efforts t
will require completion of the new assignment prior to returning to this project, the extent of extension will most Ithaly be greater than the extent of delay in your response.
~ Sincerely, j
Odstaat staned D'F Albert schweneer A. Schwencer, Chief Pressurised Water Reactors Branch No. 4 Directorate of Licensing
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4 REQUEST FOR ADDITIONAL INFORMATION ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT 1 DOCYET NO. 50-313 6.19 Your response to our Request for Information No. 6.11 does
'not present sufficient information for us to complete our analysis. Provide the following information regarding the generation of hydrogen following a design basis loss-of-coolant accident, based on the guidelines of Safety Guide 7, " Control of Combustible Gas Concentrations in Containment Following a Loss-Of-Coolant Accident":
- 6.19.1 Graphically show the integrated energy released' as a func-tion of time in the core and sump solution for radiolytic decomposition of "ater.
6.19.2 Discuss the assumptions made in calculating the energy released in the core and sump solution for radiolytic decomposition of water.
6.19.3 With-respect to the zine base paint used in the reactor.
building, specify the commercial names of the primer and topcoat paint, the mass of zine involved, and the assumed corrosion rate.
6.19.4 Specify the coni.
- tration of hydrogen assumed in the primary coolant.
4 6.19.5 Graphically show the integrated hydrogen production within the reactor building as a function of time for each of the potential sourt 9 of hydrogen.-
14.10 Provide the' following information regarding containment response to loss-of-coolant accidents. All assumptions used-in the analyses should be explained. Assumptions
.should be conservative with respect to the calculation of containment pressures.
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