ML032380406
| ML032380406 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/10/2003 |
| From: | Anthony Mcmurtray NRC/NRR/DLPM/LPD3 |
| To: | Solymossy J Nuclear Management Co |
| References | |
| TAC MC0503 | |
| Download: ML032380406 (5) | |
Text
September 10, 2003 Mr. Joseph M. Solymossy Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MC0503)
Dear Mr. Solymossy:
We would like to arrange a telephone conference with members of your staff to discuss the ongoing results of the steam generator (SG) tube inspections that will be conducted during the upcoming refueling outage (RFO-22) at Prairie Island Nuclear Generating Plant, Unit 2. This telephone conference, which is strictly voluntary on your part, should occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.
Enclosed is a list of discussion points to facilitate this telephone conference.
Inservice inspections of SG tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. In response to a recommendation made in a report by the Nuclear Regulatory Commissions (NRCs) Indian Point 2 Lessons Learned Task Force, the NRC staff plans to document a brief summary of the telephone conference, as well as any material that you may provide in support of the call.
If you have any questions regarding this matter, please contact me at (301) 415-4106.
Sincerely,
/RA/
Anthony C. McMurtray, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-306
Enclosure:
Discussion Points cc w/encl: See next page
ML032380406 OFFICE PDIII-1/PM PDIII-1/LA EMCB/SC PDIII-1/SC NAME AMcMurtray RBouling LLund LRaghavan DATE 09/04/03 09/03/03 09/05/03 09/09/03
Prairie Island Nuclear Generating Plant, Unit 2 cc:
Jonathan Rogoff, Esquire General Counsel Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Manager, Regulatory Affairs Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089 Adonis A. Neblett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, MN 55101-2127 U.S. Nuclear Regulatory Commission Resident Inspectors Office 1719 Wakonade Drive East Welch, MN 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 Tribal Council Prairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089 Nuclear Asset Manager Xcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mano K. Nazar Senior Vice President Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 August 2003
ENCLOSURE STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 DOCKET NO. 50-306 The following discussion points have been prepared to facilitate an upcoming telephone conference between the Nuclear Regulatory Commission (NRC) and the Nuclear Management Company, LLC (the licensee), to discuss the ongoing results of the steam generator (SG) tube inspections that will be conducted during the upcoming refueling outage (RFO-22) at the Prairie Island Nuclear Generating Plant, Unit 2. This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the SG inspection activities have been completed.
1.
Discuss whether any primary-to-secondary leakage existed in Unit 2 prior to shutdown.
2.
Discuss the results of secondary-side pressure tests.
3.
For each SG, provide a general description of areas examined, including the expansion criteria utilized and the type of probe used in each area. Also, be prepared to discuss your inspection of the tube within the tubesheet, particularly the portion of the tube below the expansion/transition region.
4.
Discuss any exceptions taken to the industry guidelines.
5.
Provide a summary of the number of indications identified to-date of each degradation mode and steam generator tube location (i.e., tube support plate, top-of-tubesheet, etc.).
Also provide information such as voltages and estimated depths and lengths of the most significant indications.
6.
Describe repair/plugging plans for the SG tubes that meet the repair/plugging criteria.
7.
Discuss the previous history of SG tube inspection results, including any "look backs" performed. Specifically for significant indications or indications where look backs are used in support of dispositioning (i.e., manufacturing burnish marks).
8.
Discuss, in general, new inspection findings (i.e., degradation mode or location of degradation new to this unit).
9.
Discuss the following regarding loose parts:
what inspections are performed to detect loose parts a description of any loose parts detected and their location within the SG if the loose parts were removed from the SG indications of tube damage associated with the loose parts the source or nature of the loose parts, if known
- 10. Discuss your use or reliance on inspection probes (eddy current or ultrasonic) other than bobbin and typical rotating probes, if applicable.
- 11. Describe in-situ pressure test plans and results, if applicable and available, including tube selection criteria.
- 12. Describe tube pull plans and preliminary results, if applicable and available, including tube selection criteria.
- 13. Discuss the assessment of tube integrity for the previous operating cycle (i.e., condition monitoring).
- 14. Discuss the assessment of tube integrity for the next operating cycle (i.e., operational assessment).
- 15. Provide the schedule for steam generator-related activities during the remainder of the current outage.