ML051650307
| ML051650307 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/03/2005 |
| From: | Fadel D Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:5054-07, BL-03-002 | |
| Download: ML051650307 (3) | |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place POWER*
BridgmanMI 49106 AEP~com A unit of American Electric Powver June 3, 2005 AEP:NRC:5054-07 10 CFR 50.54 Docket No.
50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD, 20852 Donald C. Cook Nuclear Plant Unit 1 NUCLEAR REGULATORY COMMISSION BULLETIN 2003-02:
LEAKAGE FROM REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS AND REACTOR COOLANT PRESSURE BOUNDARY INTEGRITY - UNIT 1 CYCLE 20 INSPECTION RESULTS
Reference:
Letter from R. P. Powers, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission Document Control Desk, "Nuclear Regulatory Commission Bulletin 2003-02: Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity Thirty-day Response,"
AEP:NRC:3054-14, dated September 17, 2003.
During the Unit 1, Cycle 20 refueling outage that ended April, 26, 2005, Indiana Michigan Power Company (I&M), the licensee for the Donald C. Cook Nuclear Plant, performed a visual inspection of the bottom mounted instrumentation (BMI) nozzle penetrations in accordance with Nuclear Regulatory Commission Bulletin 2003-02, 'leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity." The inspection was completed in accordance with I&M's commitment that was made in the referenced letter.
The inspection was conducted by I&M personnel qualified as American Society of Mechanical Engineers (ASME) Code,Section XI, Level 2 examiners.
A pole-mounted alternating current powered camera was used to perform an ASME Code,Section XI, VT-2 examination to ASME Code,Section XI, VT-3 examination criteria on all 58 Unit 1 reactor pressure vessel (RPV) BMI nozzle penetrations, including 360 degrees around each BMI penetration. No boric acid deposits were found at any RPV BMI nozzle penetration or anywhere on the RPV bottom head surface area.
No boric acid residue sampling or analysis was required or performed. The as-found condition of the Unit 1 RPV bottom head was identical to the as-left condition following the bottom head cleaning performed during the Unit 1 Cycle 19 refueling outage. No indications of through-wall leakage were found during the Unit 1 Cycle 20 RPV BMI inspection. The bottom two sections of
U. S. Nuclear Regulatory Commission Page 2 AEP:NRC:5054-07 insulation were lowered to allow unobstructed access to all penetrations and the membrane areas of the lower reactor vessel. The inspection results were saved to a computer drive as video clips.
This letter contains no new commitments. Should you have any questions, please contact Mr. John A. Zwolinski, Director of Safety Assurance, at (269) 466-2428.
Sincerely, Engineering Vice President RGV/rdw c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP J. T. King, MPSC C. F. Lyon - NRC Washington, DC MDEQ-WHMD/HWRPS NRC Resident Inspector
U. S. Nuclear Regulatory Commission Page 3 AEP:NRC:5054-07 AFFIRMATION 1, Daniel P. Fadel, being duly sworn, state that I am Engineering Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company Engineering Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ____
DAY OF J________
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