ML20246B112
| ML20246B112 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/30/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20246B114 | List: |
| References | |
| TXX-89441, NUDOCS 8907070203 | |
| Download: ML20246B112 (2) | |
Text
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4 Log # TXX-89441 c
File # 10010
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915 nlELECTRIC June 30, 1989 Wlulman J. Cabia.Jr.
Executwe Vwe Presudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555 j
SUBJECT:
COMANCHE PEAF '5?ErH ELECTRIC STATION (CPSES)
DOCKET NOS. EO v4! AND 50-446 1
SUBMITTAL OF hru-01 CORE THERMAL-HYDRAULIC ANALYSIS j
HETHODS TOPICAL REPORT RXE-89-002 REF:
1.
Letter from W. J. Cahill, (TV Electric) to USNRC, TXX-89047, dated January 31, 1989 2.
Letter from C. E. Rossi (NRC) to J. A. Blaisdell (UGRA),
" Acceptance for Referencing of Licensing Topical Report, EPRI NP-2511-CCH, 'VIPRE-01: A Thermal Hydraulic Analysis Code for Reactor Cores: Volumes 1, 2, 3 and 4,*" dated May 1, 1986.
3.
NRC Generic Letter 83-11, February 8,1983.
Gentlemen:
TU Electric has developed the capability to perform core thermal-hydraulic analyses using the VIPRE-01 computer code.
The VIPRE-01 analysis capability represents one component of the complete TU Electric reload analysis program described in Reference 1.
TU Electric intends to use this capability to perform Departure from Nucleate Boiling (DNB) Calculations for core safety limit evaluations, setpoint analyses, and safety analyses for normal operation and plant transients.
The VIPRE-01 code has been approved previously by the NRC (Reference 2) for PWR licensing applications.
The enclosed two copies of TU Electric Topical Report No. RXE-89-002 are submitted to satisfy the VIPRE-01 model documentation and user qualification requirements stated in References 2 and 3.
Your timely review of this topical report is appreciated.
J11 8907070203 890630 h
DR ADOCK 0500 5
40 Nonh Olke Street LB 81 Dallas, Texas 75201
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t TXX-89441 June 30, 1989 Page 2 of 2 If you have any questions on this material, please contact Steve Maier or Ray Ashley of my staff.
Sincerely, William J.
hill. Jr.
RLA/dde Enclosures (2)
I c - Mr. R. D. Martin. Region IV j
Resident Inspectors, CPSES (3)
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File # 10010
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r 915 nlELECTRIC June 30, 1989 Wause J. Cabal. Jr.
Decunve nce Prendent U. S. Nuclear Regulatory Commission Attn: Docunent Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUBMITTAL OF VIPRE-01 CORE THERMAL-HYDRAULIC ANALYSIS METHODS TOPICAL REPORT RXE-89-002 REF:
1.
Letter from W. J. Cahill (TV Electric) to USNRC, TXX-89047, dated January 31, 1989 2.
Letter from C. E. Rossi (NRC) to J. A. Blaisdell (UGRA),
" Acceptance for Referencing of Licensing Topical Report, EPRI NP-2511-CCM, 'VIPRE-01:
A Thermal Hydraulic Analysis Code for Reactor Cores; Volumes 1, 2, 3 and 4,'" dated May 1, 1986.
3.
NRC Generic Letter 83-11. February 8, 1983.
Gentlemen:
TV Electric has developed the capability to perform core thermal-hydraulic analyses using the VIPRE-01 computer code. The VIPRE-01 analysis capability represents one component of the complete TU Electric reload analysis program described in Reference 1.
TU Electric intends to use this capability to perform Departure from Nucleate Boiling (DNB) Calculations for core safety limit evaluations, setpoint analyses, and safety analyses for normal operation and plant transients.
l The VIPRE-01 code has been approved previously by the NRC (Reference 2) for PWR licensing applications.
The enclosed two copies of TV Electric Topical Report No. RXE-89-002 are submitted to satisfy the VIPRE-01 model documentation and user qualification requirements stated in References 2 and 3.
Your timely review of this topical report is appreciated.
O I
i p1 G907070203 890630 ADOCK0500yf5 PDR mm ouve street La si canas, reus mot J
p 1,*
3 l
i TXX 89441 June 30, 1989 Page 2 of 2 l
If you have any questions on this material, please contact Steve Maier or Ray Ashley of my staff.
i t-Sincerely, u
t-I William J.
hill, Jr.
RLA/dde Enclosures (2) c - Mr.. R. D. Martin, Region IV i
Resident Inspectors, CPSES (3)
I J
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