ML19341B781
| ML19341B781 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/24/1981 |
| From: | Groce R Maine Yankee |
| To: | Carter J Office of Nuclear Reactor Regulation |
| References | |
| FMY-81-21, NUDOCS 8102270555 | |
| Download: ML19341B781 (4) | |
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February 24, 1981 3
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Units:: States' Nuclear Regulatory Commission Wash 1P.gton,'D. C.
20555 Attention:
Office of Nuclear Reactor Regulation Division of Systems Integration Reactor Systems Branch Mr. James Carter MAIL STOP P1130
Subject:
Maine Yankee RETRAN Input Deck
References:
1.
License No. DPR-36 (Docket No. 50-309) 2.
MYAPC letter to USNRC (WMY 80-165), dated December 23, 1980.
3 MYAPC letter to USNRC (WMY 80-67), " Revised Steam Line Break Analysis". dated April 17, 1980.
4.
YAEC 1104, " Maine Yankee Plant Accident Analysis Model Using FLASH-4, W. J. Szyeczak, dated November 1976.
5 MYAFC letter to USNRC (WMY 79-143), YAEC-1202, Maine Yankee Cycle 5 Core Performance Analysis, dated December 5,1979
Dear Sir:
Per discussions with members of your staff, we are submitting one copy of the input deck for the Maine Yankee RETRAN steam line break model.
This model will be used in the benchmark analysis discussed in Reference 2.
The attached Figures present nodal diagrams of the model as currently configured.
The primary system representation in this model contains a minor modification of the Maine Yankee RELAP-4Di model nodalization used in the Cycle 5 small break LOCA analysis (reference 5).
The feedtrain nodalization, with the exception of the explicit representation of each feedtrain p;mp is similar to the nodalization used in the Cycle 5 FLASH steam line break model, References 3 and 4.
The steam line nodalization is more detailed than the Cycle 5 FLASH representation. Minor modifications may be made to the model during the benchmarking process.
Any changes will be fully documented in the benchmark report and final model description to follow in early March.
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United States Nuclear Regulatory Commission Page Two Fe bruary 13. 1981 Additional changes to the att ached model will be required to represent the turbine driven feedwater pump, turbine drive, ar.d associated control systems.
These will require only minor changes to the physical characteristics of pump volume 209, and additional control block representations of the turbine torque balance and control logic; which will be documented in the Cycle 6 reload analysis report to be submitted in mid April.
Should you desire additional information regarding the enclosed deck, please contact Mr. Phil Guimond at X2123 Respectfully, MAINE YANKEE ATOMIC PO'n'ER COMPANY wb/
Robert H. Groce Senior Engineer - Licensing PJG/smh Enclosure
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