View source for RBG-26763, Forwards Proposed Draft Outline for Hydrogen Control Rept, in Response to NRC 870909 Request.Util Revising Schedule for Submittal of plant-specific Hydrogen Control Analysis to 6 Months Following Issuance of SER on Topical Rept HGN-112

{{Adams
| number = ML20235U750
| issue date = 10/08/1987
| title = Forwards Proposed Draft Outline for Hydrogen Control Rept, in Response to NRC 870909 Request.Util Revising Schedule for Submittal of plant-specific Hydrogen Control Analysis to 6 Months Following Issuance of SER on Topical Rept HGN-112
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-26763, NUDOCS 8710140235
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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GULF STATES                             UTILITIES COMPANY RIVER BEND STATION     POST OFFIC4 BOX 220 '   ST. FRANCISVILLE. LOUISIANA 70715 AREA CODE 604     635 60944      346 8651 October 8, 1987 I
RBG- 26763                              -
File Nos. G9.5, G9.23 l
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:                                                                                                      I River Bend Station                   ' Unit 1 Docket No. 50-458 On March 31,            1987,      in a letter from Gulf States Utilities Company (GSU) to the Nuclear Regulatory Commission '(NRC),                                       GSU proposed to submit the fin'al hydrogen control analysis for River Bend Station (RBS) by September, 1987. Subsequent to this Ic*ter. GSU received a letter from the RBS HRC Project Manager dated September 9, 3" t.M ch provided guidance on an acceptable scope and schedule for submittal of the RBS final hydrogen control analysis. Based on this letter, GSU is revining the schedule for submittal of the plant specific hydrogen control analysis required by'10CFR50.44 to six months following the issuance of the generic hydrogen control safety evaluation report (SFR) on Topical Report HGN-112. The RBS hydrogen control report will take into consideration generic                             SER         recommendations          regarding information to be included in the final plant specific report.
As required by 10CFR50.44, the scope of the RBS analysis will provide an evaluation of the consequences of hydrogen released from a degraded core accident. This evaluation will include the recovery period, use postulated accidents accepted by the NRC staff, support the design of the      hydrogen         control system, show that containment structural j       integrity is maintained, and demonstrate survivability of systems and components necessary to establish and maintain safe shutdown and containment integrity. The letter from the RBS NRC Project Manager also requested that a proposed outline be provided for the RBE hydrogen control report. A proposed draft outline for this report is attached.        This draft working outline may undergo some refinement as the report is developed but should serve to identify the major topics to be discussed in the RBS hydrogen control report.                                              Each topic identified in the outline will be addressed in sufficient detail to 0140235 871008                                                                                               [O p   ADOCK 05000458 PDR                                                                                         II

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demonstrate compliance with~the. hydrogen control rule requirements and
: to provide a. basis'for issuance of a plant specific.SER. Generic HCOG submittals will be endorsed for situations where         the.. generic work       ]
;                       ' supports or is applicable to RBS.                                                   i l
                                      >                             Sincerely,
                                                                       ,  f.            h                  .l J. E. Booker.
Manager-River Bend Oversight River Bend Nuclear Group-               j
                                          'b l
JEB/E     /    /4AM/ch-Attachment cc:     U.S. Nuclear Regulatory Commission Re'gion IV 611 Ryan Plaza Drive, Suite 1000-Arlington, TX'76011
                              'NRC Resident Inspector
                               ' Post Office Box 1051
                               'St. Francisv111e, LA 70775
    ;i,                                                                                                     !
:1 Propored Draft Outline for River Bend Str. tion Hydrogen Control Report I. EXECCTTIVE SlMRRY                                           '
II. INTRODUCTION
: 1. RBS Preliminary Analysis
: 2. HCOG Program Plan III. HYDROGEN IGNITION SYSTEM DESIGN
: 1. Separation Criteria
: 2. Power Supply Requirements
: 3. Qualification Testing
: 4. Actuation Criteria IV. DEGRADED CORE ACCIDENT HYDROGEN GE2ERATION
: 1. Code Selection
: 2. Accident scenarios
: 3. Mechanistic Release Histories
: 4. Non-mechanistic Release History V. HYDROGEN CCNSUSTION TESTING
: 1. 1/4 Scale Test Program                               .-
: 2. Other Test Programs VI. PRDRRY CONTAINMENT STRUCTURAL INTEGRITY
: 1. Drywell A. Pressure Capacity Analysis B. Predicted Hydrogen Burn Pressure - Analysis
: 2. Containment A. Ultimate Capacity Analysis B. Predicted Hydrogen Burn Pressure - Analysis C. Measured HydruJen Burn Pressure - Testing VII. PRIMARY CONTAINMENT EQUIPMENT SURVIVABILITY
: 1. Drywell A. Thermal Environment Definition - Analysis B. Equipnent List Definition
* C. Heating-6 Analysis Results
: 2. Containment A. Thermal Environment Definition - Analysis B. Thermal Environment Definition - Testing C. Equipnent List Definition D. Heating-6 Analysis Results VIII. HYDROGEN CONTROL DERGENCY OPERATING PROCEDURE                     ;
1 IX. CONCLUSION
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