ML20012F077

From kanterella
Jump to navigation Jump to search
Provides Annual Rept to Update Changes & Errors in Loca/Eccs Codes & Methods Utilized by C-E for Evaluation of Facility. During 1989,COMPREC-II Computer Code Modified to Remove Low Amplitude Flow Oscillations
ML20012F077
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/30/1990
From: Gates W
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0265, LIC-90-265, NUDOCS 9004090455
Download: ML20012F077 (2)


Text

. .

o w Omaha PubHC Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 March 30, 1990 LIC-90 0265

@s.

.' U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mai' Station PI-137 Washington, DC 20555

References:

1. Docket No. 50-285
2. CENPD 134P, "COMPERC-II A Program for Emergency Refill-Reflood of the Core", August 1974
3. CENPD-134P, Supplement 1, "COMPI:RC-II, A Program for l Emergency Refill-Reflood of the Core (Modifications)",

February 1975 l

4. CENPD-134P, Su piement 2, "COMPERC-II, A Program for Emergency Refi 1-Reflood of the Core" June 1985 l
5. Letter from OPPD (K. J. Morris to NRC (Document Control Desk) dated October 16, 1989 ( 1C-89-952) l Gentlemen:

SUBJECT:

Annual Report on loss of Coolant Accident (LOCA)/ Emergency Core Cooling System (ECCS) Models As required by 10CFR50.46(a)(3)(ii), Omaha Public Power District (0 PPD) is providing this annual report to update changes or errors in the LOCA/ECCS codes and methods utilized by Combustion Engineering (CE) for the evaluation of the Fort Calhoun Station (FCS) Unit No.1. There were no errors identified during this CE evaluation.

During 1989 the COMPERC-II computer code (References 2, 3 and 4) was modified l to more realistically model safety injection (SI) spillage during a large break LOCA event. This modification also removed low-amplitude flow oscillations introduced by the discontinuity of the fixed head in the old model. i There was no significant change in the Peak Clad Temperature (PCT) resulting from the revised model. The two possible effects of the modification of the SI l model include reflood rate and two-phase level which have been evaluated by CE I and have been determined to have no impact on the PCT. The cumulative change l l in PCT for large break LOCA, including that from the previous annual i notification (Reference 5 , is a reduction of less than l'F in the PCT. There i have been no changes in t e small break LOCA results or model to date.

p$409040090033oADOCK 05000293 1 PitC l e 5124 Emploumen in i opportunitu

[N!

ll0

i ..

! i

,, ., 5 U. S. Nuclear Regulatory Commission j

LIC 90 0265 ,

Page 2 '

l Since no significant changes, as defined by 10CFR50.46, were implemented in 1989 for Fort Calhoun LOCA analyses, no action beyond the submittal of this  ;

report is required.

If you should have any questions, please contact me.

Sincerely, i sv..D. k W. G. Gates Division Manager '

Nuclear Operations WGG/pje c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV A. Bournia, NRC Project Manager i P. H. Harrell, NRC Senior Resident Inspector ,

i l

l v.

l l

1 i

l '.

l- ,

l i