ML20215D085
| ML20215D085 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 10/01/1986 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | Frank Akstulewicz, Jaffe D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215D088 | List: |
| References | |
| NUDOCS 8610100647 | |
| Download: ML20215D085 (2) | |
Text
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MEMORANDUM FOR:
~
F. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate, PWR-B D. Jaffe, Project Manager PWR Project Directorate #8, PWR-B FROM:
Charles E. Rossi, Assistant Director Division of PWR Licensing-A
SUBJECT:
SER FOR TOPICAL REPORT NUSCO 140-2, "NUSCO T/H MODEL QUALIFICATION, VOLUME II (VIPRE-01)"
Plant Names:
Haddam Neck Plant Millstone Nuclear Pcwer Station Unit No. 2 Docket Nos.:
50-213, 50-336 i
Licensing Stage:
OR I
Responsible Directorate: ISA Project Directorate, PWR-B PWR Project Directorate #8, PWR-B Review Branch:
Reactor Systems Branch, PWR-A Review Status:
Complete The Reactor Systems Branch of the Division of PWR Licensing-A has prepared the enclosed safety evaluation report on Topical Report NUSCo 140-2, "NUSCo Thermal Hydraulic Model Qualification Volume II, (VIPRE)". We have found that the topical report is acceptable f m referencing for Haddam Neck licensing calculations of core thermal hydraulics using VIPRE-01. We also require that the licensee perform an analysis to ensure that the DNBR limit of 1.3 for the W-3 critical heat flux cor-relation used.in VIPRE-01 provides a 95/95 limit for DNB.
Since Millstone Unit 2 has different fuel design, a separate study is necessary to establish the fuel-dependent inputs and to demonstrate the appropriateness of the DNBR limit for any CHF correlation to be used with the VIPRE-01 code.
Our SALP input is also attached as Enclosure 2.
._@81D51 signed by l
Charles E. Rossi, Assistant Director Division of PWR Licensing-A
Enclosures:
,, DISTRIBUTION:,
As stated
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a MEMORANDUM FOR:
F. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate, PWR-B D. Jaffe, Project Manager PWR Project Directorate #8, PWR-B FROM:
Charles E. Rossi, Assistant Director Division of PWR Licensing-A
SUBJECT:
SER FOR TOPICAL REPORT NUSCO 140-2, "NUSCO T/H MODEL QUALIFICATION, VOLUME II (VIPRE-01)"
Plant Names:
Haddam Neck Plant Millstone Nuclear Power Station Unit No. 2 Docket Nos.:
50-213, 50-336
/.
Licensing Stage:
/
Responsible Branches:
ISA Project Directorate, PWR-B
/
PWR Project Directorate #8, PWR-B Review Branch:
Reactor Systems Branch, PWR-A Review Status:
Complete The Reactor Systems Branch of the Division of PWR Licensing-A has prepared the Hydraulic Model Qualification Volume II, (VIPRE)"[t NUSCO 140-2, "NUSCo Thermal enclosed safety evaluation report on Topical Repor We have found that the topical report is acceptable for referencing for HaddamAleck licensing calculations of core thermal hydraulics using VIPRE-01. We also require that the licensee perfonn an analysis to ensure that the DNBR limit of 1.3 for the W-3 critical heat flux cor-
. relation used in VIPRE-01 provides a 95/9!Vlimit for DNB.
Since Millstone Unit 2 has different fpel design, a separate study is necessary to establish the fuel-dependent inpu ( and to demonstrate the appropriateness of the DNBR limit for any CHF corre) tion to be used with the VIPRE-01 code.
Our SALP input is also attached as Enclosure 2.
Charles E. Rossi, Assistant Director Division of PWR Licensing-A
Enclosures:
Di5rR r S vT od FM As stated cc:
T. Novak H. Berkow 9MS D. Crutchffeld A. Thadani R
L FM 1
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C. Thomat D. Jaffe A
F d-h W. Minne'rs C. Grimes s,' " 5 0FLA AF W.Hoffes
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