ML20082H393: Difference between revisions
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55'ENTERGY | 55'ENTERGY f527"'""'""*' | ||
Kilk;na.LA 70066 Tet 504 739 6774 | Kilk;na.LA 70066 Tet 504 739 6774 | ||
) | |||
R. F. Burski amu | R. F. Burski amu Nucksar Safety YtArfc4 3 W3F1-95-0061 A4.0b PR April 12, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 | ||
Nucksar Safety | |||
YtArfc4 3 W3F1-95-0061 A4.0b PR April 12, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
| Line 30: | Line 27: | ||
This submittal is being made in accordance with 10CFR50.46 in that errors were found and corrected in 1994 in the ABB Combustion Engineering evaluation models used for Emergency Core Cooling System (ECCS) analyses. | This submittal is being made in accordance with 10CFR50.46 in that errors were found and corrected in 1994 in the ABB Combustion Engineering evaluation models used for Emergency Core Cooling System (ECCS) analyses. | ||
One error was in the PARCH peak cladding temperature-(PCT) code used for small break Loss-of-Coolant Accident (LOCA) analysis and two errors were in the PARCH steam cooling heat transfer coefficient code used for large break LOCA analysis. | One error was in the PARCH peak cladding temperature-(PCT) code used for small break Loss-of-Coolant Accident (LOCA) analysis and two errors were in the PARCH steam cooling heat transfer coefficient code used for large break LOCA analysis. | ||
Correction of the errors in PARCH had no effect on the PCT for the large break LOCA. The sum of the absolute magnitude of the temperature changes for the large break LOCA from all reports to date continues to be less than l'F. No change occurred in the PCT due to correction of the error in PARCH | Correction of the errors in PARCH had no effect on the PCT for the large break LOCA. | ||
for the small break LOCA. | The sum of the absolute magnitude of the temperature changes for the large break LOCA from all reports to date continues to be less than l'F. | ||
No change occurred in the PCT due to correction of the error in PARCH for the small break LOCA. | |||
A copy of CENPD-279, Supplement 6 (dated February,1995), entitled " Annual Report on CE ECCS Codes and Methods for 10CFR50.46," is attached, which addresses the year 1994 errors and corrections that are identified above. | A copy of CENPD-279, Supplement 6 (dated February,1995), entitled " Annual Report on CE ECCS Codes and Methods for 10CFR50.46," is attached, which addresses the year 1994 errors and corrections that are identified above. | ||
17(' 61 G | 0 17(' 61 G g | ||
DR..ADOCK 0500 | 950417o123 950412 DR..ADOCK 0500 2 | ||
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If you'should have any questions regarding this submittal, please contact | .- Annual Report on CE-ECCS' Codes' and' Methods for-10CFR50'.46 W3F1-95-0061 | ||
Roy Prados at_(504) 739-6632. | 'Page 2 fis 1: April 12, 1995 If you'should have any questions regarding this submittal, please contact Roy Prados at_(504) 739-6632. | ||
- i f Very truly yours,~. | |||
j | |||
Director | -i R.F. Burski J | ||
Director Nuclear Safety RFB/RWP/ssf. | |||
Attachment | Attachment i | ||
(w/ Attachment) cc: | i (w/ Attachment) cc: | ||
C.P. Patel,.NRC-NRR R.B. McGehee | L.J. Callan, NRC Region ~IV C.P. Patel,.NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office f | ||
N.S. Reynolds NRC Resident Inspectors Office f | |||
h i | h i | ||
h t | h t | ||
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i w, | i w, | ||
.}} | |||
Latest revision as of 07:04, 14 December 2024
| ML20082H393 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/12/1995 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20082H394 | List: |
| References | |
| W3F1-95-0061, W3F1-95-61, NUDOCS 9504170123 | |
| Download: ML20082H393 (2) | |
Text
,
55'ENTERGY f527"'""'""*'
Kilk;na.LA 70066 Tet 504 739 6774
)
R. F. Burski amu Nucksar Safety YtArfc4 3 W3F1-95-0061 A4.0b PR April 12, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Annual Report on CE ECCS Codes and Methods for 10CFR50.46 Gentlemen:
This submittal is being made in accordance with 10CFR50.46 in that errors were found and corrected in 1994 in the ABB Combustion Engineering evaluation models used for Emergency Core Cooling System (ECCS) analyses.
One error was in the PARCH peak cladding temperature-(PCT) code used for small break Loss-of-Coolant Accident (LOCA) analysis and two errors were in the PARCH steam cooling heat transfer coefficient code used for large break LOCA analysis.
Correction of the errors in PARCH had no effect on the PCT for the large break LOCA.
The sum of the absolute magnitude of the temperature changes for the large break LOCA from all reports to date continues to be less than l'F.
No change occurred in the PCT due to correction of the error in PARCH for the small break LOCA.
A copy of CENPD-279, Supplement 6 (dated February,1995), entitled " Annual Report on CE ECCS Codes and Methods for 10CFR50.46," is attached, which addresses the year 1994 errors and corrections that are identified above.
0 17(' 61 G g
950417o123 950412 DR..ADOCK 0500 2
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y,?
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- ,. x.
- )
5
.- Annual Report on CE-ECCS' Codes' and' Methods for-10CFR50'.46 W3F1-95-0061
'Page 2 fis 1: April 12, 1995 If you'should have any questions regarding this submittal, please contact Roy Prados at_(504) 739-6632.
- i f Very truly yours,~.
j
-i R.F. Burski J
Director Nuclear Safety RFB/RWP/ssf.
Attachment i
i (w/ Attachment) cc:
L.J. Callan, NRC Region ~IV C.P. Patel,.NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office f
h i
h t
/
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i w,
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