BYRON 2004-0069, Addendum to 2003 Annual Radiological Environmental Operating Report
| ML041700061 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/10/2004 |
| From: | Kuczynski S Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2004-0069 | |
| Download: ML041700061 (4) | |
Text
ExekIenm.
Exelon Generation www.exeloncorp.com Nuclear Byron Generating Station 4450 North German Church Road Byron, IL 61010-9794 Tel 815-234-5441 June 10, 2004 LTR:
BYRON 2004-0069 File:
2.12.1523 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Addendum to 2003 Annual Radiological Environmental Operating Report This addendum to the 2003 Annual Radioactive Effluent Release Report dated May 15, 2004 submitted under Byron Letter #2004-0044 is being provided for the following reasons.
- 1. Page eleven of ninety-four - the fourth quarter average release rate for iodine was incorrectly reported as 3.57E-2. The correct value is 3.57E-7.
- 2. Page twenty-four of ninety-four was incorrectly outlined uA" through uG". The outline should start with "C" through "I' as a continuation of page twenty-three of ninety-four.
These corrections have been captured in the Exelon Corporation Corrective Action Program in Condition Report #218097.
If you have any questions regarding this information, please contact W. Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station SEK/ES/tlf/dlcw Attachments: revised pages 11 and 24 of 94 cc:
Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Byron Station
ADDENDUM 2003 Annual Radioactive Effluent Release Report
EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS -
SUMMATION OF ALL RELEASES Byron Unit Two 2003 REPORT FOR 2003 Units Fission and Activation
- 1. Total Release
- 2. Avg. Release Rate Gases Ci uCi/sec QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.47E-01 1.23E-01 1.55E+00 1.94E-01 2.02E+00 1.88E-02 1.57E-02 1.95E-01 2.44E-02 6.41E-02 0.OOE+00 0.OOE+00 0.OOE+00 2.84E-06 2.84E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.57E-07 9.01E-08l Iodine-131
- 1. Total Release Ci
- 2. Avg. Release Rate uCi/sec Particulates Half Life
- 1. Total Release
- 2. Avg. Release Rate
>= 8 days Ci uCi/sec 4.76E-08 8.90E-07 1.56E-06 0.OOE+00 2.50E-06 6.12E-09 1.13E-07 1.96E-07 0.OOE+00 7.92E-08 Tritium
- 1. Total Release Ci 4.97E-01
- 2. Avg. Release Rate uCi/sec 6.39E-02 4.88E-01 2.70E-01 7.12E-01 1.97E+00 6.20E-02 3.40E-02 8.96E-02 6.24E-02 Date/Time: 03/16/2004 12:23 retdas Report Page 11 of 94
BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-4541455 RADIOACTIVE EFFLUENT RELEASE REPORT January, 2003 THROUGH December, 2003 C. Meteorological and environmental impact information is reported in the Station Annual Radiological Environmental Operating Report as required by Technical Specification 5.6.2.
D. No limits were exceeded in liquid hold up tanks as stated in Technical Specification 5.5.12 or in waste gas decay tanks as stated in Technical Specification 5.5.12.
E. There were no irradiated fuel shipments during this period.
F. There were no elevated releases. All releases are considered vent or ground level releases.
G. There were no REMP issues in 2003.
H. Attached are Offsite Dose Calculations for January through December of 2003.
I.
Liquid effluent monitor OPR01J was declared inoperable due to loss of flow alarms when the monitor was aligned to sample from OWX26T during recirculation mode of operation. This occurred on August 8, 2003 and was returned to service on December 12, 2003, exceeding the fourteen day L.C.O. During this 4-month period, an extensive troubleshooting effort took place in an effort to eliminate this problem. The monitor was repaired and returned to service after the sample probe intake holes were enlarged to reduce the restriction to flow through the radiation monitor. During this time all required sampling was performed in accordance with the Technical Requirements Manual LCO action statements. This issue was entered into the Corrective Action Process under condition report 170808.
Report Page 24 of 94