ML18102A288
| ML18102A288 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/02/1996 |
| From: | Dawn Powell Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96227, NUDOCS 9608080251 | |
| Download: ML18102A288 (3) | |
Text
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e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit t\\UG 0 2 1996 LR-N96227 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
PEAK FUEL CLAD TEMPERATURE CHANGES SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.46(a) (3) (ii),
Public Service Electric and Gas Company (PSE&G) hereby reports changes of greater than fifty degrees F absolute magnitude to the calculated Peak Clad Temperature (PCT) for the Salem Unit Nos. 1 and 2 Small Break Loss of Coolant Accident (LOCA) analyses.
These changes reflect the correction of three errors contained in codes used to support LOCA analyses.
These errors were identified to PSE&G by Westinghouse Electric Corporation in th~ir letters PSE-96-209 and PSE-96-243.
The errors had negligible impact upon the Large Break LOCA analyses PCT results.
While the absolute magnitude of the allocation of margin for these errors is 68 degrees F, the net impact on the Small Break LOCA analyses is to reduce PCT from the last reported value of 1660 degrees F to 1652 degrees F.
The attachment describes the basis for each allocation of margin and the cumulative impact on the Small Break LOCA analyses is shown in Table 1.
If there are any questions regarding this transmittal, please contact us.
Attachment 9608080251 PDR ADOCK p
(~~~~ ---
960802 05000272 PDR The power is in your hands.
Sincerely, D. R. Powell Manager -
Licensing and Regulation 95-2168 REV. 6/94
Document Control Desk LR-N96227 AUG 0 21996 Attachment Errors Resulting in Reduction of Peak Clad Temperature for Small Break LOCA.
There are three errors that have occurred since the last annual report.
The first of these is identified as NOTRUMP Enthalpy Error.
The error resulted from an error in an equation used in the NOTRUMP code.
Specifically, the error in the equation was a partial derivative that had been taken with respect to an energy term rather than a mass term.
The allocation made to address this correction resulted in an increase of Small Break LOCA PCT of 20 degrees F.
The second error is identified as SBLOCTA Fuel Rod Initialization Error.
This resulted from an error in a code used for Small Break LOCA.
The error discovered in the SBLOCTA code related to adjustments that are made during the fuel rod initialization process.
Specifically, a power correction that was intended to compensate for pellet diameter adjustments was incorrect.
- Other, unrelated changes were also made to the fuel rod creep and strain model to correct errors that might occur during certain transient conditions.
Since these changes were small and somewhat related, they were evaluated as a single issue.
The allocation made to address their correction resulted in an increase in Small Break PCT of 10 degrees F.
The third error is identified as Loop Seal Elevation Error.
This was an error in the relative elevation of the crossover leg in the evaluation model codes.
For the Large Break LOCA, the correction is estimated to have a negligible effect.
However, for the Small Break LOCA PCT, a reduction of 38 degrees F occurred.
Table 1 -
Summary of Error and Net Change Direction and Absolute Error Source Magnitude Magnitude NOT RUMP Specific
+20 degrees F 20 Enthalpy Error SBLOCTA Fuel Rod
+10 degrees F 10 Initialization Error Loop Seal Elevation
-38 degrees F 38 Error Net Change I Total
-8 degrees F 68 Absolute Magnitude
Document Control Desk LR-N96227
- C Mr. Hubert J. Miller, Administrator -
Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 AUG 0 2 1996 Mr. L. N. Olshan, Licensing Project Manager -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall USNRC Senior Resident Inspector X24 Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625