ML042740504
| ML042740504 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/16/2004 |
| From: | Perino C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N04-0413 | |
| Download: ML042740504 (2) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 1 6 2004
§ PSEG LR-N04-0413 NuclearLLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 LCR S03-05, IMPLEMENTATION OF ALTERNATE SOURCE TERM SALEM GENERATING STATION, UNITS I AND 2 FACILITY OPERATING LICENSE DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Re: TRANSMITTAL OF PSEG CALCULATIONS On April 26, 2004, PSEG Nuclear, LLC (PSEG) submitted a request for revision of Appendix A of the Technical Specifications for the Salem Nuclear Generating Station, Units 1 and 2 implementing the guidelines provided by Regulatory Guide 1.183, "Accident Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Stations".
In the submittal, the NRC was informed that PSEG had completed calculations to support the revised dose analysis and that the calculations are available for the staff s review upon request. During the working meeting held on September 9, 2004 at the NRC headquarters, NRC staff requested copies of the applicable calculations in order to complete their review of our submittal.
The following calculations are included for NRC staff review:
- 1. S-C-ZZ-MDC-1 945, Post LOCA EAB, LPZ and CR Doses - Alternative Source Term (AST), Rev. OIR1
- 2. S-C-ZZ-MDC-1948, EAB, LPZ and CR Doses, Rod Ejection Accident (REA)-
AST, Rev. OIR2
- 3. S-C-ZZ-MDC-1 949, EAB, LPZ and CR Doses, Steam Generator Tube Rupture (SGTR) Accident-AST, Rev. OIR2
- 4. S-C-ZZ-MDC-1950, EAB, LPZ and CR Doses, Main Steam Line Break (MSLB) Accident-AST, Rev. OIR1
- 6. S-C-ZZ-MDC-1959, CR X/Qs Using ARCON 96 Code-Non-LOCA Releases, Rev. OIR1
- 7. S-C-ZZ-MDC-1987, Input Parameters for Salem AST Dose Calcs, Rev. 1 (Containment Spray Coverage Evaluation) 4 95-2168 REV. 7/99
Document Control Desk SEP 1 6 2004 LR.N04-0413
- 8. S-C-ZZ-MEE-1 805, Waste Gas Decay Tank and Volume Control Tank Rupture Accidents-AST Analysis, Rev. 0 (w/o attachmeints)
Note: This evaluation was completed to facilitate the adoption of AST TEDE terminology only and does not represent any changes to the Salem Units 1 and 2 current design/licensing basis.
Additionally, at NRC staffs request, a CD containing the design inputs and RADTRAD data used to develop our submittal is included with this package.
This submittal does not contain any information considered 'Proprietary" or that should be withheld from public disclosure.
If you have any questions or require additional information, please contact Mr.
Jesus Arias at (856) 339-5245.
Sincerely, Christina Perino Director-Licensing and Nuclear Safety C:
Mr. S. Collins, Administrator-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager - Salem & Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem Units 1 and 2 Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625