LR-N13-0087, Report of Changes, Tests, and Experiments
| ML13113A020 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/19/2013 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LR-N13-0087 | |
| Download: ML13113A020 (3) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 LR-N13-0087 APR 192013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Salem Generating Station, Units 1 and 2 Facility Operating License Nos. DRP-70 and DRP-75 NRC Docket Nos. 50-272 and 50-311 Report of Changes, Tests, and Experiments 1 OCFR50.59(d)(2)
Pursuant to the requirements of 10CFR50.59(d)(2), PSEG Nuclear LLC (PSEG) forwards a summary of changes, tests, and experiments implemented at Salem Units 1 and 2 during the period of January 1, 2011 through December 31,2012.
There are no new commitments in this letter.
If there are any questions, please contact Thomas Cachaza at 856-339"'5038.
Car :.J. Fricker Site Vice President - Salem Attachments ( 1)
Document Control Desk Page 2 LR-N 13-0087 C
W. Dean, Administrator - Region 1 J. Hughey, Licensing Project Manager - Salem USNRC Senior Resident Inspector - Salem P. Mulligan, Manager, IV, Bureau of Nuclear Engineering T. Cachaza, Salem Commitment Coordinator L. Marabella, Corporate Commitment Coordinator
Document Control Desk LR-N13-0087 Summary of Changes, Tests, and Experimsnts Salem Units 1 and 2 Salem Dose Calculations Updated for Increased Control Room Envelope Unfiltered In Leakage (Salem PORC-S2011-020)
Description of Activity:
The proposed activity revised the following calculations that collectively determine Control Room (CR), Exclusion Area Boundary (EAB), Low Population Zone (LPZ), Salem Technical Support Center (TSC) and mission doses following design basis accidents (DBAs) to incorporate changes to plant parameters and dose calculation models. The changes to the calculations include the following:
Increase unfiltered in-leakage rate for the Control Room Envelope (CRE) from 150 CFM to 275 CFM Decrease Engineered Safety Feature (ESF) leakage from 0. 7 GPM to 0.45 GPM Decrease CREACS makeup rate from 2200 CFM to 2100 CFM Addition of a model for the dose contribution due to back leakage to the Refueling Water Storage Tank (RWST) and increasing the RWST back leakage from 100 cc/hr to 50,000 cc/hr Increase the iodine decontamination factor for the intact steam generator leak path (primary to secondary) from 1 to 100 Decrease the time used in the RADTRAD release fraction and timing file for the containment relief line release model from 3.6 E-03 hr to 0.1 E-05 hr to more closely represent an instantaneous release scenario.
Update the RADTRAD computer code from version 3.02 to version 3.03 References to Replacement Steam Generators (RSG) are updated to reflect U/2 Steam Generators The calculations which were revised are:
S-C-ZZ-MDC-1920 - Fuel Handling Accidents Radiological Consequences, Revision 4 S-C-ZZ-MDC-1945 - Post-LOCA EAB, LPZ, & CR Doses - Alternative Source Term (AST),
Revision 0 S-C-ZZ-MDC-1946 - Post-LOCA TSC Doses - Alternative Source Term (AST), Revision 0 S-C-ZZ-MDC-194 7 - Post-LOCA Vital Area Access Area Mission Doses -AST, Revision 0 S-C-ZZ-MDC-1948 - EAB, LPZ, & CR Doses - Rod Ejection Accident (REA) -AST, Revision 1 S-C-ZZ-MDC-1949 - EAB, LPZ, & CR Doses - Steam Generator Tube Rupture (SGTR)
Accident-AST, Revision 1 S-C-ZZ-MDC-1950 - EAB, LPZ, & CR Doses - Main Steam Line Break (MSLB) Accident AST, Revision 1 S-C-ZZ-MDC-1951 - EAB, LPZ, & CR Doses - RCP Locked Rotor Accident (LRA)-AST, Revision 1 S-C-ZZ-MDC-1987 - Input Parameters for Salem AST Dose Cales, Revision 2