ML053130163
| ML053130163 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/28/2005 |
| From: | William Holston Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMPIL 1995, NUREG-0619 | |
| Download: ML053130163 (2) | |
Text
Constellation Energy-P.O. Box 63 Lycoming, NY 13093 Nine Mile Point Nuclear Station October 28, 2005 NMP1L 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Nine Mile Point Unit 1 Docket No. 50-220 Facility Operating License No. DPR-63 NUREG-0619 Inspection Report for Feedwater Nozzle Examinations -2005 Refueling Outage Gentlemen:
The purpose of this letter is to provide the NRC with the results of inspections performed at Nine Mile Point Unit 1 (NMP1) in April 2005 during refueling outage (RFO) eighteen. The Nine Mile Point Nuclear Station, LLC (NMPNS) commitment to NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," requires a report to be submitted discussing inspections of the feedwater nozzles within six months of completing an outage during which an inspection was performed. The examinations identified no recordable indications.
NUREG-0619, Section 4.4.3.1 (2) requests information to be provided for the following topics:
Startup/Shutdown Cvcles:
The feedwater nozzles have experienced 33 startup/shutdown cycles since the last inspection performed and 216 cycles since initial plant operation.
Summarv of Previous Inspections:
Visual examinations were performed previously during the eighth, eleventh, twelfth and fourteenth refueling outages. As previously reported, these examinations also resulted in no reportable indications, except for a crack observed in a nonstructural weld of one end bracket pin during the 1981 RFO eight, which was subsequently repaired.
.x L4
Page 2 NMP1L 1995 Modifications:
NUREG-0619 requests licensees to report any system changes or changes in operating procedures that will affect feedwater flow or temperature and that should be considered in predicting future cracking tendencies based on past history. There have been no such system changes or changes in operating procedures since the last report.
Inspection Summarv/Results:
Visual examinations of the feedwater sparger for NUREG-0619 were performed in accordance with NMPNS procedures. These examinations were performed with a remote underwater television camera system qualified with specific In-Vessel Visual Inspection (IVVI) resolution requirements. These examinations covered the general condition of the feedwater sparger, pipe, sparger welds, nozzle welds, flow holes, end bracket pins, tack welds and end bracket welds.
Additionally, accessible areas of the feedwater nozzle blend radius were examined for general structural condition. These examinations were performed to VT-3 requirements; however, the resolution requirements of VT-1 were adhered to. No recordable indications were identified during performance of these examinations. These inservice examination results have been reviewed and approved by a NMPNS Level III examiner.
Leakage Monitoring:
NMPNS has not installed an on-line bypass leakage monitoring system at NMPl. The thermal sleeve design utilized includes flow baffles that prevent mixing of the hot reactor water and colder feedwater in the nozzle annulus. NUREG-0619, Section 4.3.2.4, specifically excludes NMP1 from this item.
If you have any questions about this submittal, please contact James Hutton, Director Licensing, at (315) 349-1041..
Very truly yours, William C. Holston Manager Engineering Services WCH/RF/sac cc:
Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. L. M. Cline, NRC Senior Resident Inspector Mr. T. G. Colburn, Senior Project Manager, NRR (2 copies)