View source for RBG-20968, Forwards Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage, Completing Util Response to Criteria 2 of SER Confirmatory Item 50 Re NUREG-0737, Item II.B.3

{{Adams
| number = ML20117P102
| issue date = 05/13/1985
| title = Forwards Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage, Completing Util Response to Criteria 2 of SER Confirmatory Item 50 Re NUREG-0737, Item II.B.3
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000458
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM
| document report number = RBG-20968, NUDOCS 8505200398
| package number = ML20117P105
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
}}

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       ,.x A GULF STATES                          UTELITIES ^ COMPANY RIVER BEND STATION     POST OFHCE BOX 220 -    ST. FRANCISVILLE. LOUISIANA 70775 AREA CODE SO4 -    635-6094      346-8661 May 13, 1985 RBG-20968 File Nos. G9.5, G9.19.2, 234.600 Mr.' Harold R. Denton, Director Office of Nuclear Reactor Regulation ^
U. S. Nuclear Regulatory Commission Washington, D. C. 20555

==Dear Mr. Denton:==

River Bend Station - Unit 1 Docket No. 50-458' he enclosed information suppleme'nts-Gulf States Utilities Company's (GSU) January 2,.1985 submittal to your-office concerning Safety Evaluation Report f(SER)' Confirmatory Item No. (50). Specifically, Criteria-2 and 10 regarding the NUREG-0737 'DfI Action Plan Item II.B.3 required further clarification from the Nuclecr Regulatory Commission's Chemical Engineering Branch (CHEB) : reviewer, -Mr. Paul Wu.
L Enclosed is a revised River Bend Stetion (RBS) degraded core damage estimation' procedure (COP-1050) which is based on the BWR Owners Group Generic Core Damage Estimation Procedure' (General Electric' Company NEDO-22215,
             " Procedures for the Letermination of the Extent of _ Core Damage Under Accident Conditions"). This is consistent with Licensing Review Group -II issue 3-CHEB and completes GSU's response'to Critorion 2.
The post accident sampling system'-(PASS) operators will be provided with-refresher training-annually in post-accident sampling, analysis and transport. This completes GSU's response to Criteria 10.
Sincerely, I
h J.Manager-Engineering, E. Booker Nuclear Fuels G Licensing River Bend Nuclear Group
;            Enclosure                                                                                              h00 0
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