ML041730450
| ML041730450 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/02/2004 |
| From: | Kuczynski S Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BL-03-002, BYRON 2004-0060 | |
| Download: ML041730450 (5) | |
Text
Exekt nSm Exelon Generation Company, LLC www.exeloncorp.com Nuclear Byron Station 4450 North German Church Road Byron, IL 61010-9794 June 2, 2004 LTR:
__File:__1.:10.0101
~_ _
United States Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 60-Day Response to NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity" On August 21, 2003, the NRC issued NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity." This bulletin requires the following information be submitted to the NRC within 60 days after plant restart following the next ifisiectionrof the-iractor pressure vessel lower head penetrations:
"a summary of the inspections performed, the extent of the inspections, the methods used, a description of the as-found condition of the lower head, any findings of relevant indications of through-wall leakage, and a summary of the disposition of any findings of boric acid deposits and any corrective actions taken as a result of indications found."
Pursuant to 10 CFR 50.54, "Conditions of licenses," paragraph (e, Attachment 1 to this letter provides the Byron Station, Unit 2 60-day response. This response is due to the NRC by June 8,2004..
June 2, 2004 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions or desire additional information regarding this letter, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
I declare under penalty of perjury that the foregoing is true and correct.
Respectfully, Executed on 6-2-01 3/>
Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station
Enclosures:
, Byron Station Unit 2 60-Day Response to NRC Bulletin 2003-02 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station
ATTACHMENT 1 Byron Station Unit 2 60-Day Response to NRC Bulletin 2003-02 "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity" Byron Station Unit 2 60-Day Response to NRC Bulletin 2003-02 On August 21, 2003, the NRC issued NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity." This bulletin requires the following information be submitted to the NRC within 60 days of plant restart following the next inspection of the reactor pressure vessel (RPV) lower head penetrations:
Within 60 days of plant restart following the next inspection of the RPV lower head penetrations, the subject PWR addressees should submit to the NRC a summary of the inspections performed, the extent of the inspections, the methods used,-a description-of the-as-found condition of the 'lower head,-any findings of relevant indications of through-wall leakage, and a summary of the disposition of any findings of boric acid deposits and any corrective actions taken as a result of indications found.
Response
Summary of the Inspections Performed, Extent of the Inspections, and Methods Used A remote visual inspection of the Byron Station, Unit 2 RPV bottom mounted instrumentation (BMI) nozzles (58 total) and RPV lower head was performed in Mode 5 descending during Byron Station, Unit 2 refueling outage 11 (i.e., B2R11) in March 2004. The inspection, performed by VT-2 qualified personnel, examined the full circumference around each BMI nozzle on the RPV lower head using multiple passes (i.e., four total) to ensure full coverage with overlap. The inspection was performed in accordance with procedure ER-AP-335-1012, "Visual Examination of PWR Reactor Vessel Head Penetrations." The inspection used remote equipment capable of resolving the appropriate detail (i.e., 1/32" line on an 18% neutral gray card) at two feet. The actual distances viewed were less than two feet which gave extremely close views of the BMI nozzle to RPV lower head interface region, thereby ensuring any boric acid leakage would be easily-identified.
Description of the As-Found Condition, Findings of Relevant Indications, and Summary of the Disposition of any Findings The RPV lower head visual inspection identified no evidence of any boric acid deposits in the BMI nozzle to RPV lower head interface region. Several rust trails (minor surface corrosion) caused by previous refueling outage reactor cavity boot seal leakage were noted. These indications did not impact the performance of the RPV lower head examination and were found to be acceptable as no RPV boric acid leakage was identified and no wastage was observed.
_-2 Page 1 of 2 Corrective Actions Taken There were no corrective actions taken as a result of indications found as no evidence of RPV boric acid leakage was identified.
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