ML030350082

(BVPS-1) - Upcoming Steam Generator Tube Inservice Inspection

ML030350082
Person / Time
Site:	Beaver Valley
Issue date:	02/04/2003
From:	Dan Collins NRC/NRR/DLPM/LPD1
To:	Bezilla M FirstEnergy Nuclear Operating Co
Collins D S, NRR/DLPM, 415-1427
References
TAC MB7271
Download: ML030350082 (6)

Text

February 4, 2003 Mr. Mark B. Bezilla Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1) - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MB7271)

Dear Mr. Bezilla:

Inservice inspections (ISI) of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant technical specifications (TSs), reporting requirements range from submitting a special report, within 15 days following completion of each ISI of SG tubes, that identifies the number of tubes plugged and/or repaired; to submitting a special report, within 12 months following completion of the inspection, that provides complete results of the SG tube ISI. The special report containing the complete results shall include the following:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged and/or repaired.

The Nuclear Regulatory Commission (NRC) staff requests a phone conference with members of your staff to discuss the results of the SG tube inspections to be conducted during the upcoming BVPS-1 refueling outage (1R15). The phone call would occur after the majority of the tubes have been inspected, but before the SG inspection activities are completed.

Enclosed is a list of discussion points to facilitate this phone conference.

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

M. Bezilla Please contact me if you have any questions or suggestions regarding this issue. Thank you for your support in this area.

Sincerely,

/RA/

Daniel S. Collins, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334

Enclosure:

List of Discussion Points cc w/encl: See next page

M. Bezilla Please contact me if you have any questions or suggestions regarding this issue. Thank you for your support in this area.

Sincerely,

/RA/

Daniel S. Collins, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334

Enclosure:

List of Discussion Points cc w/encl: See next page DISTRIBUTION:

PUBLIC PDI-1 R/F DKern, R-I JRogge, R-I OGC ACRS ALLund BPlatchek, R-I KKarwoski CKhan RLaufer RHaag DCollins MOBrien CLauron C:\ORPCheckout\FileNET\ML030350082.wpd Accession No: ML030350082 *see previous concurrence OFFICE PDI-1/PM PDI-2/LA EMCB/SC PDI-1/SC NAME DCollins SLittle for MOBrien ALLund* RLaufer DATE 1/30/03 1/31/03 01-21-03 1/31/03 OFFICIAL RECORD COPY

Beaver Valley Power Station, Units 1 and 2 Mary OReilly, Attorney FirstEnergy Nuclear Operating Company FirstEnergy Corporation 76 South Main Street Akron, OH 44308 Rich Janati, Chief Division of Nuclear Safety FirstEnergy Nuclear Operating Company Bureau of Radiation Protection Regulatory Affairs/Performance Deparment of Environmental Protection Improvement Rachel Carson State Office Building Larry R. Freeland, Manager P.O. Box 8469 Beaver Valley Power Station Harrisburg, PA 17105-8469 Post Office Box 4, BV-A Shippingport, PA 15077 Mayor of the Borough of Shippingport Commissioner James R. Lewis P O Box 3 West Virginia Division of Labor Shippingport, PA 15077 749-B, Building No. 6 Capitol Complex Regional Administrator, Region I Charleston, WV 25305 U.S. Nuclear Regulatory Commission 475 Allendale Road Director, Utilities Department King of Prussia, PA 19406 Public Utilities Commission 180 East Broad Street Resident Inspector Columbus, OH 43266-0573 U.S. Nuclear Regulatory Commission Post Office Box 298 Director, Pennsylvania Emergency Shippingport, PA 15077 Management Agency 2605 Interstate Dr. FirstEnergy Nuclear Operating Company Harrisburg, PA 17110-9364 Beaver Valley Power Station ATTN: M. P. Pearson, Director Ohio EPA-DERR Services and Projects (BV-IPAB)

ATTN: Zack A. Clayton Post Office Box 4 Post Office Box 1049 Shippingport, PA 15077 Columbus, OH 43266-0149 FirstEnergy Nuclear Operating Company Dr. Judith Johnsrud Beaver Valley Power Station National Energy Committee Mr. B. F. Sepelak Sierra Club Post Office Box 4, BV-A 433 Orlando Avenue Shippingport, PA 15077 State College, PA 16803 J. H. Lash, Plant Manager (BV-IPAB)

FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077

STEAM GENERATOR (SG) TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1)

DOCKET NO. 50-334 The following discussion points have been prepared to facilitate the phone conference arranged with the FirstEnergy Nuclear Operating Company (FENOC) to discuss the results of the SG tube inspections to be conducted during the spring 2003 upcoming BVPS-1 refueling outage (1R15). This phone call will be scheduled to occur toward the end of the planned SG tube inspections, but before the unit exits its refueling outage.

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

1. Discuss whether any primary-to-secondary leakage existed in this unit prior to shutdown. Include values of any calculated leakage and trends relative to previous outages.

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 type of probe used in each area. Also, please 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 SG tube location (e.g., 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 (e.g., manufacturing burnish marks).

8. Discuss, in general, new inspection findings (e.g., degradation mode or location of degradation new to this unit).

Enclosure

9. If steam generators contain Alloy 600 thermally treated tubing, discuss actions taken (if any) based on Seabrooks recent findings. Information regarding Seabrooks recent findings may be found in Nuclear Regulatory Commission letters dated July 2, September 20, and November 26, 2002 (ADAMS Accession numbers ML021800003, ML022590328, and ML023300041, respectively).

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 SG-related activities during the remainder of the current outage.