RBG-21454, Forwards Revised Drywell Break Base Case Analysis. Peak Containment Pressure Calculated for Revised CLASIX-3 Drywell Break Analysis During Hydrogen Release Was 12.7 Psig & Occurred in Wetwell Vol
| ML20129F091 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/05/1985 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20129F093 | List: |
| References | |
| RBG-21454, NUDOCS 8507170219 | |
| Download: ML20129F091 (2) | |
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b GULF STATES UTILITIES COMPANY July 5, 1985 RDG 21454 File No. G9.5 Mr. H. R. Denton Office of Nuclear Regulation U. S. Nuclear Regulatory Ccmnission Washington, D.C. 20555
Dear Mr. Denton:
River Bend Station - Unit 1 Docket No. 50-458 As requested by the NBC Staff, Gulf States Utilities Cmpany (GSU) has revised the CIASIX-3 drywell break analysis previously sutraitted on June 7,
1985.
Enclosed.is a copy of GSU's report entitled " Revised.
Drywell Break Base Case Analysis".
The peak containment pressure calculated for the revised drywell break analysis during hydrogen release was 12.7 psig and occurred in the wetwell volume. 'Ihis result, when compared with the RBS ultimate pressure retaining capability of 56 psig (GSU letter frm J. E. Booker to R. L. Tedesco dated June 22, 1983) demonstrates that hydrogen burns do not threaten the RBS contalment structural integrity.
The revised CIASIX-3 analysis used hydrogen source terms a 75% clad representative of severe accident conditions equivalent to equivalent metal-water reaction.
As a result, the containment tenperatures and pressures pralicted by this analysis are conservative.
Gulf States Utilities is participating in the Hydrogen Control Owners Group (HCOG) testing and analysis program to further address hydrogen burn phenmenon. Results fr m this progr m will be evaluated for applicability to the River Bend Station and if necessary incorporated into GSU's final analysis as noted in our letter of June 26, 1985.
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8507170219 850705
, j'gy PDR ADOCK 05000458 A
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'Ihe subnittal of this reanalysis provides additional information f
regarding the drywell break analysis as requested by the NIC Staff.
l Very Truly Yours,
- f. G A, J. E. Booker Manager -
Engineering, Idcensing &
Nuclear Fuels River Bend Nuclear Group kak JEB/WJR/ES Attachment NDC i
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