ML20010F852
| ML20010F852 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 09/08/1981 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NO-81-1460, NUDOCS 8109110457 | |
| Download: ML20010F852 (3) | |
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1 Carolina Power & Light Company September 8, 1981 l
FILE: NG-3514 (B)
Serial No.: NO-81-1460 j
NF-1070 i
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l Office of Nuclear Reactor Regulation g%g ' ]\\
ATTENTION:
Mr. T. A. Ippolito, Chief j
Operating Reactors Branch No. 2
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United States Nuclear Regulatory Commission C
Chq j1 Washington, DC 20555
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'I i,:J BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2
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DOCKET NOS 50-325 AND 50-324 4
LICENSE NOS. DPR-71 AND DPR-62 l
RELOAD ANALYSES
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Dear Mr. Ippolito:
Summary I
t Carolina Pc eer & Light Company (CP&L) is beginning a program in which we plan to perform our.own reload analyses for the Brunswick
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Steam Electric Plant, Unit Nos. I and 2.
i The first step in performing reload analyses will be for CP&L' i
to assume the primary burden in performing the steady-state analyses for the Brunswick Plant beginning in mid-1983. Therefore, in the second quarter of 1982, we will submit for your review topical reports detailing our steady-state methodology in the thermal-hydraulics and neutronics areas. This submittal will be followed in mid-1983 and.1984 with additional topical reports to address CP&L's methodology L
in process computer core monitoring and transient analyses.
Introduction CP&L ' plans to establish the capability to perform reload design analyses for the Brunswick Plant. This is being done for several reasons:
1.
Enable faster responses to anomalous operating situations.
2.
-Increase flexibility in operations planning.
3.
Maintain. a high level of in-house knowledge of reactor jj
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core behavior.
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S 411 Fayetteville Street
- P. O. Bnx 1551
- Raleigh, H. v. 27602
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8109110457 810908 PDR ADOCK 05000324 r
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Increase flexibility in fuel procurement.
5.
Realize financial benefits through fuel contracts.
In order to achieve this analysis capability, CP&L has been engaged in the development and testing of appropriate BWR steady-state and transient models for the past several years.
The primary computer programs to be used for neutronics analyses are the RECORD and PRESTO-B codes which are proprietary to Scandpower, Inc., and are a part of their fuel management system.
Extensive benchmarking of these codes against Brunswick Plant data has been conducted. These studies have shown that the Scandpower neutronics codes are appropriate for the intended task and that CP&L has the required expertise in conducting the desired analyses. Therefore, we plan to submit appropriate reports to you for licensing approval.
Schedule To initiate this process, we will submit our steady-state BWR methodology for your review because this serves as the foundation or initial state for cycle management, process computer, and transient analyses.
CP&L plans to submit this topical report in the second quarter of 1982.
It will contain a neutronics package (based on the Scandpower RECORD and PREST 0-B codes), a thermal-hydraulics package (tentatively based on the EPRI FIBWR code), and Brunswick specific benchmarking information.
For your reference, Scandpower, Inc., is planning to submit topical reports on the RECORD and PRESTO-B codes to NRC in the first quarter of 1982.
These codes will form the basis of our neutronics submittal and would therefore require review and approval by NRC.
The Scandpower, Inc., topical reports will demonstrate and describe the code capabilities, their verification, and the corresponding methodology, while the CP&L topical reports will describe the specific application of these codes to the Brunswick Plant in all nominal operating conditions.
We plan to follow this steady-state submittal with topical reports on our process computer methodology and transient methodology.
These submittals are planned for 1983 and 1984, respectively.
Conclusion CP&L believes that developing the capability to perform reload analyses in-house is an important goal to achieve.
The first step is to submit the steady-state methodology in the second quarter of 1982 for your review. We would request NRC t o complete the review / approval process by early 1983 so that CP&L could apply these methods to the mid-1983 reload analyses.
l l
l l We would welcome the opportunity to meet with your staff to discuss the modeling techniques and other details regarding our plans.
Please cal? us if you would like to set up a meeting or if you have any questions concerning this information.
Yours very truly,
-ff WWM ty E. E. Utley -
Executive Vice President Power Supply and Engineering & Construction EEU:la cc:
Mr. J. Van Vliet d
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