ML063120515

Telephone Conference to Discuss the Results of the Steam Generator Inspection During Upcoming Refueling Outage

ML063120515
Person / Time
Site:	Prairie Island
Issue date:	11/16/2006
From:	Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1
To:	Thomas J. Palmisano Nuclear Management Co
M. Chawla LPL3-1
References
TAC MD3441
Download: ML063120515 (5)

Text

November 16, 2006 Mr. Thomas J. Palmisano 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 - TELEPHONE CONFERENCE TO DISCUSS THE RESULTS OF THE STEAM GENERATOR INSPECTION DURING UPCOMING UNIT 2 REFUELING OUTAGE (TAC NUMBER MD3441)

Dear Mr. Palmisano:

The Nuclear Regulatory Commission (NRC) staff would like to discuss results of the steam generator (SG) tube inspections to be conducted during the upcoming Prairie Island Nuclear Generating Plant, Unit 2 refueling outage. Please review the enclosed discussion points, which have been prepared to facilitate the phone conference with your representatives. We would like to schedule this phone call towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.

If you have any questions regarding this response, please contact me.

Sincerely,

/RA/

Mahesh Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-306

Enclosure:

As stated cc: see next page

ML063120515 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA BC:AFPB NRR/LPL3-1/BC NAME MChawla:ca THarris Paul Klein LRaghavan DATE 11/ 9/06 11/9/06 11/15/06 11/16/06

STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION NUCLEAR MANAGEMENT COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 DOCKET NO. 50-306 The following discussion points have been prepared to facilitate the phone conference arranged with the Nuclear Management Company licensee to discuss the results of the steam generator (SG) tube inspections to be conducted during the upcoming Prairie Island Nuclear Generating Plant, Unit 2 refueling outage. This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.

The staff plans to document a brief summary of the conference call as well as any material that is provided in support of the call.

1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.

2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.

3. Discuss any exceptions taken to the industry guidelines.

4. For each SG, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100 percent of dents/dings greater than 5 volts and a 20 percent sample between two and five volts),

and the expansion criteria.

5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date of each degradation mode (e.g.,

number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).

6. Describe repair/plugging plans.

7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

8. Provide the schedule for steam generator-related activities during the remainder of the current outage.

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 the results of any secondary side inspections.

11. Discuss any unexpected or unusual results.

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

Jonathan Rogoff, Esquire Tribal Council Vice President, Counsel & Secretary Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.

Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 Michael B. Sellman Manager - Environmental Protection Division President and Chief Executive Officer Minnesota Attorney Generals Office Nuclear Management Company, LLC 445 Minnesota St., Suite 900 700 First Street St. Paul, MN 55101-2127 Hudson, MI 54016 U.S. Nuclear Regulatory Commission Craig G. Anderson Resident Inspector's Office Senior Vice President, Group Operations 1719 Wakonade Drive East Nuclear Management Company, LLC Welch, MN 55089-9642 700 First Street Hudson, WI 54016 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 November 2005