ML020380518

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Upcoming Steam Generator Tube Inservice Inspection
ML020380518
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 02/12/2002
From: Kim T
NRC/NRR/DLPM/LPD3
To: Nazar M
Nuclear Management Co
Kim, TJ, NRR/DLPM/LPD III-1, 415-1392
References
Download: ML020380518 (5)


Text

February 12, 2002 Mr. Mano Nazar 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

Dear Mr. Nazar:

A telephone conference has been arranged with members of your staff to discuss the results of the steam generator (SG) tube inspections that have been conducted during the current refueling outage (RFO-21) at Prairie Island Nuclear Generating Plant, Unit 2. This telephone conference will 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 have provided in support of the call.

If you have any questions regarding this matter, please contact me at (301) 415-1392.

Sincerely,

/RA/

Tae Kim, 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

ML020380518

Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:

J. E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.

Washington, DC 20037 Site Licensing Manager 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 Inspector's 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 Mr. Stephen Bloom, 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 Mr. Roy A. Anderson Executive Vice President and Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Xcel Energy, Inc.

414 Nicollet Mall Minneapolis, MN 55401

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 results of the steam generator (SG) tube inspections conducted during the current refueling outage (RFO-21) at 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 hydrostatic tests.

3.

For each SG, provide a general description of areas examined, including the expansion criteria utilized and type of probe used in each area.

4.

For analyzed eddy current results, describe bobbin indications (those not examined with rotating pancake coil (RPC)) and RPC/Plus Point/Cecco indications. Include the following information in the discussion: location, number, degradation mode, disposition, and voltages/depths/lengths of significant indications.

5.

Describe repair/plugging plans for the SG tubes that meet the repair/plugging criteria.

6.

Discuss the previous history of SG tube inspection results, including any "look backs" performed.

7.

Discuss, in general, the new inspection findings.

8.

Describe in-situ pressure test plans and results (if applicable and available), including tube selection criteria.

9.

Describe tube pull plans and preliminary results (if applicable and available); include tube selection criteria.

10. Discuss the assessment of tube integrity for the previous operating cycle.
11. Discuss the assessment of tube integrity for next operating cycle.
12. Provide the schedule for SG-related activities during the remainder of the current outage.

ENCLOSURE

13. Discuss what steps have been taken, or will be taken, in response to the lessons learned from the Indian Point Unit 2 tube failure. In addition, please be prepared to discuss the following:

a) the actions that are taken in response to identifying a new degradation mechanism, b) the actions taken to ensure that data noise levels are acceptable, and c) data quality issues and the need for criteria to address data quality.

It is the NRC staffs expectation that any significant results or relevant trends discussed during the telephone conference, as well as any materials provided by your staff during the telephone conference regarding the SG tube results, will be included in one of the special reports required by the Prairie Island Technical Specifications.