ML052640170
| ML052640170 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/17/2005 |
| From: | George Wunder NRC/NRR/DLPM/LPD1 |
| To: | Christian D Dominion Nuclear Connecticut |
| Wunder G, NRR/DLPM, 415-1494 | |
| References | |
| TAC MC6714 | |
| Download: ML052640170 (6) | |
Text
October 17, 2005 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, REGARDING MILLSTONE POWER STATION, UNIT NO. 3, STEAM GENERATOR PLUGGING REPORT (TAC NO. MC6714)
Dear Mr. Christian:
By letters dated May 3, 2004, and April 7, 2005, respectively, Dominion Nuclear Connecticut, Inc. submitted the 15-day steam generator (SG) plugging report in accordance with Technical Specification (TS) Sections 4.4.5.5.a and 6.9.2, and the 12-month SG tube inspection report in accordance with TS Sections 4.4.5.5.b and 6.9.2. In order to complete its review of the reports, the Nuclear Regulatory Commission staff requires responses to the attached questions. These questions were forwarded electronically to Mr. Paul Willoughby of your staff on September 20, 2005. Please provide your responses within 60 days of the date of this letter.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: See next page
ML052640170 OFFICE PDI-2/PM PDI-2/LA PDI-2/SC NAME GWunder CRaynor DRoberts DATE 10/17/05 10/14/05 10/17/05
Millstone Power Station, Unit No. 3 cc:
Lillilan M. Cuoco, Esquire Senior Resident Inspector Senior Counsel Millstone Power Station Dominion Resources Services, Inc. c/o U.S. Nuclear Regulatory Commission Rope Ferry Road P. O. Box 513 Waterford, CT 06385 Niantic, CT 06357 Edward L. Wilds, Jr., Ph.D. Mr. G. D. Hicks Director, Division of Radiation Director - Nuclear Station Safety Department of Environmental Protection and Licensing 79 Elm Street Dominion Nuclear Connecticut, Inc.
Hartford, CT 06106-5127 Rope Ferry Road Waterford, CT 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Ms. Nancy Burton 475 Allendale Road 147 Cross Highway King of Prussia, PA 19406 Redding Ridge, CT 00870 First Selectmen Mr. William D. Meinert Town of Waterford Nuclear Engineer 15 Rope Ferry Road Massachusetts Municipal Wholesale Waterford, CT 06385 Electric Company Moody Street Mr. P. J. Parulis P.O. Box 426 Manager - Nuclear Oversight Ludlow, MA 01056 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Mr. J. Alan Price Waterford, CT 06385 Site Vice President Dominion Nuclear Connecticut, Inc.
Mr. W. R. Matthews Rope Ferry Road Senior Vice President - Nuclear Operations Waterford, CT 06385 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Mr. Chris Funderburk Waterford, CT 06385 Director, Nuclear Licensing and Operations Support Mr. John Markowicz Dominion Resources Services, Inc.
Co-Chair 5000 Dominion Boulevard Nuclear Energy Advisory Council Glen Allen, VA 23060-6711 9 Susan Terrace Waterford, CT 06385 Mr. David W. Dodson Licensing Supervisor Mr. Evan W. Woollacott Dominion Nuclear Connecticut, Inc.
Co-Chair Rope Ferry Road Nuclear Energy Advisory Council Waterford, CT 06385 128 Terry's Plain Road Simsbury, CT 06070
Millstone Power Station, Unit No. 3 cc:
Mr. S. E. Scace Assistant to the Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. A. J. Jordan, Jr.
Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT NO. 3 REVIEW OF STEAM GENERATOR INSPECTION REPORTS DOCKET NO. 50-423 By letters dated May 3, 2004, and April 7, 2005, respectively, Dominion Nuclear Connecticut, Inc. submitted the 15-day steam generator (SG) plugging report in accordance with Technical Specification (TS) Sections 4.4.5.5.a and 6.9.2, and the 12-month SG tube inspection report in accordance with TS Sections 4.4.5.5.b and 6.9.2. In order to complete its review of the reports, the Nuclear Regulatory Commission staff requires responses to the following questions.
- 1. On Page 3 of the letter dated April 7, 2005 (12-month report), it is stated that possible loose part signals were identified for two tubes in SG B. No associated tube degradation was reported. Were these loose parts removed from SG B? If not, what hindered the removal of these parts? Discuss any other loose parts that may have been left in service. In addition, provide the results of any evaluations performed to ensure the loose parts left in service will not result in a loss of tube integrity for the period between inspections.
- 2. Page 3 of the 12-month report stated that manufacturing burnish marks (MBM) were reported for SG B (9) and SG D (6). The MBMs were determined not to be service-induced for both SGs. Discuss whether the MBMs were traceable to the baseline inspection to support that they were not service-induced, and if their signals had undergone any changes.
- 3. Due to dents and dings being areas of increased stress, discuss the scope and results of any dent and ding examinations performed during the 9th refueling outage. If no inspections were performed, provide the basis for not performing such inspections.
- 4. On Page 4 of the 12-month report, it is reported that two single volumetric indications (SVI) are due to hand-hole installation during SG fabrication. Discuss which tubes (e.g., Row 27, Column 39) are related to the installed hand-holes, and if the SVIs were traceable to the baseline inspection. In addition, discuss whether the SVI signals had undergone any changes.
- 5. It was stated on Page 5 of the 12-month report that an SVI in Tube Row 1, Column 1 (R1C1) appeared to be a manufacturing defect similar to tubes plugged prior to startup.
Discuss whether previous rotating pancake coil (RPC) exams of Tube R1C1 have been performed. In addition, discuss any changes the SVI may have undergone from any previous exams.
- 6. Page 5 of the 12-month report indicates that five tubes with SVI and/or PLP signals were plugged due to the area not being accessible for visual inspection. Were the five tubes stabilized in case there was a loose part present?
- 7. Discuss whether a visual inspection was performed on Tube R5C1 which contained a SVI with no associated loose part signal (from eddy current). In addition, provide the results of the inspection, if a visual inspection was performed.
- 8. Regarding the staffs review summary of the 8th refueling outage dated April 25, 2004, discuss any other restricted or ovalized tubes that may have been identified (even though not plugged) during this outage.
- 9. Table 1 of the annual report indicates that RPC was performed for 50% of Row 1 and Row 2 U-bends. Please provide the basis for not expanding the scope of the U-bend inspection given that an indication was found in Row 1.
- 10. On Page 4 of the 12-month report, it was indicated that four tubes with indications attributed to Freespan indications, possibly MBMs which could not be confirmed by historical bobbin data were left in service. Please describe these indications in greater detail. If they are not traceable to previous inspections, why were they not considered degraded and plugged?