NUREG-0023, Forwards Auxiliary & Power Conversion Sys Branch Sser (NUREG-0023) Re PSAR Through Amend 33.Fire Protection Sys Design & Criteria Acceptable.Open Item Resolved: Difference between revisions

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#REDIRECT [[NUREG-0023, Forwards Hydrologic Engineering Evaluation Re Dewatering Sys Design Bases.Evaluation Performed to Comply W/Staff Requirements Outlined in Ser,Section 2.4.4 (NUREG-0023) & Stated in Conditions of CP]]
| number = ML20210S830
| issue date = 04/08/1976
| title = Forwards Auxiliary & Power Conversion Sys Branch Sser (NUREG-0023) Re PSAR Through Amend 33.Fire Protection Sys Design & Criteria Acceptable.Open Item Resolved
| author name = Tedesco R
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name = Deyoung R
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000508, 05000509
| license number =
| contact person =
| case reference number = CON-WNP-1643, RTR-NUREG-0023, RTR-NUREG-23
| document report number = NUDOCS 8605290434
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| page count = 2
}}
 
=Text=
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bociet File eVR S Mb NRR Retsding PS Re3 diag APCSB Reading Docket Nas. M,5h-j 50-50S R. C. Leloung, Assistant Director for Li,t t kater Beactors PM h
SAFETT ETALUATION REPORT CUFPLLMfLT 40. 1 Plant Namo! kPP3e. Nuclear Prciect No. 3 and No. 5 T.icensing Stage: CI Dceket Dunberr: 1TV 50-508; STN Sn-509 Responsible Branch:
L'eT. 3 Project Manacar: A. Soutnie i
Requested Cwpletion Date: April 9, 1976 Thr enclose.4 6upplement to the 1:PPS3 Units 3 and 5 Csfety Ev'alu.stica P.coort 04CREG-0023), issued Yebtuary 13,197619dattro the scetion of the Auxilinty and Tower Ccmversio;i Sprena tranch based on noy ar;end:; eats, up tc and including Atends-nt 32.
'The appiteant has pubritted infornatien for the fire prottetibn systec in response to our previous concerns. Wa acw ct.nclude that the k'?PSS Units 3 end 5 firre protection systen desirn criteria and bases are accepts. Sic.
Ue find this open iter: now rer.olved. As a result of investigatlons presently being conducted by the staf f on fire protection systtes a furth r requirements may be ir posed to further ir:rrove the capabilf tv of the fire protection systems to prevent unacceptabic damage t! wit rust result from a fire 1.e. fore plant operation.
OHginnt sirned ty-Rotett L. Teduco Robert L. Tedesco, Assistant Director for Plant Systems Division of Systems Safety Fncloourc As Stated cc: See Page 2 8605290434 760408 PDR ADOCK 05000508 E
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