ML20153F009

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Requests Approval to Use MINI-CECOR/BASSS for in-core Monitoring of Limiting Conditions for Operation on Peak Linear Heat Rate & Departure from Nucleate Boiling
ML20153F009
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/18/1986
From: Andrews R
OMAHA PUBLIC POWER DISTRICT
To: Thadani A
Office of Nuclear Reactor Regulation
References
LIC-86-057, LIC-86-57, TAC-59869, TS-FC-86-86, NUDOCS 8602250238
Download: ML20153F009 (2)


Text

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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102-2247 402/536-4000 February 18, 1986 TS-FC-86-86 LIC-86-057 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 l

References:

(1) Docket No. 50-285 (2) Letter NRC (E. J. But-her) to 0 PPD (R. L. Andrews) dated August 26, 1985.

(3) OPPD Application, dated September 3, 1985.

(4) Letter OPPD (R. L. Andrews) to NRC (E. J. Butcher), dated October 4, 1985 (LIC-85-436).

Dear Mr. Thadani:

MINI-CECOR Validation The Omaha Public Power District's Cycle 10 reload submittal to the NRC on September 3,1985 contained a section on the use of the MINI-CECOR/BASSS pro-gram to monitor Limiting Conditions for operation on peak linear heat rate and departure from nucleate boiling. The approval of the use of this soft-ware for incore LC0 monitoring was made contingent on the validation by Com-bustion Engineering that the CECOR version on the OPPD plant computer and the version licensed for use on the CE mainframe computer yield identical results for a variety of cases. The purpose of the validation was to provide assur-ance that the MINI-CECOR software loaded on the District's plant computer works properly and that the physics uncertainties associated with the use of the mainframe version of CECOR are applicable to the mini-computer version.

MINI-CECOR is a mini-computer version of Combustion Engineering's CECOR code.

It uses the same algorithms as the mainframe version but has a reduced level of editing options to enable it to fit on a mini-computer.

I To enable the code to fit on the Fort Calhoun computer, Combustion Engineer-ing started with a'2.0 Mod 5 version of CECOR and performed the following:

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J Mr.-Ashok C. Thadani LIC-86-057 Page Two

1. Removed the capability of writing the PDQ 221 file.
2. Removed the capability of writing the COLSS file.
3. Removed the capability of writing the TOUCHY file.
4. Removed the capability of reading the BULL file.
5. Added the BASSS calculation.
6. Changed the temporary coefficient file format to direct access.
7. Provided for a single set of CECOR files for all cases.
8. Resized common blocks to reflect the small Fort Calhoun core (relative j to other CE designed cores that are larger).

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After CE personnel completed this work, the code was loaded on the Fort Cal-houn computer by Combustion Engineering. At this time CE performed a seven-teen case validation check to confirm that the version OPPD would use would a yield identical results relative to the version executed (;n the CE main-i frame. On January 28, 1986, Combustion Engineering notifiad OPPD that all of the work on the MINI-CECOR version was complete and, that both CECOR versions had calculated identical results for all seventeen ca~ses. These recorded calculations have been documented through the Combustion Engineering quality i

assurance program.

Based on the validation effort recently completed by Combustion Engineering, the District believes that MINI-CECOR/BASSS can now be declared operational. I Your approval is hereby requested so that MINI-CECOR/BASSS may be used for incore monitoring of the Limiting Conditions for Operation on peak linear 1

heat rate and departure from nucleate boiling.

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R. L. Andrews Division Manager Nuclear Production RLA/JDK/rh cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, DC 20036 Mr. E. G. Tourigny, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector I

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