Information Notice 2005-09, Official Exhibit - ENT000527-00-BD01 - NRC Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to Tubesheet Welds (Apr. 7, 2005)
| ML12340A713 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/07/2005 |
| From: | Hilland P Division of Inspection and Regional Support |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 23330, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML12340A713 (7) | |
United States Nuclear Regulatory Commission Official Hearing Exhibit
Entergy Nuclear Operations, Inc.
In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01 ENT000527 Docket #: 05000247 l 05000286 Submitted: August 20, 2012 Exhibit #: ENT000527-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:
Rejected: Stricken:
Other:
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 7, 2005 NRC INFORMATION NOTICE 2005-09: INDICATIONS IN THERMALLY TREATED ALLOY
600 STEAM GENERATOR TUBES AND TUBE-
TO-TUBESHEET WELDS
ADDRESSEES
All holders of operating licenses for pressurized-water reactors (PWRs), except those who have
permanently ceased operations and have certified that fuel has been permanently removed
from the reactor vessel.
PURPOSE
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees about recent operating experience with degradation in steam generator tubes and
tube-to-tubesheet welds. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action or written response is required.
DESCRIPTION OF CIRCUMSTANCES
Catawba Nuclear Station, Unit 2, has four Westinghouse Model D5 recirculating steam
generators. Each steam generator has approximately 4,600 tubes fabricated from thermally
treated Alloy 600 (Figure 1). During fabrication of the steam generators, a portion of the U-
shaped tubes are inserted into a thick plate called a tubesheet. The tubesheet is approximately
21 inches thick and has two holes for each tube (one hole on the hot-leg side of the steam
generator and one hole on the cold-leg side). The lower end of the tubes were tack-expanded
into the tubesheet for approximately 0.70 inch (Figure 2). This tack expansion is performed to
facilitate welding of the tube to the primary side of the tubesheet. In the case of Catawba
Unit 2, this region is frequently referred to as the tack roll region since the tack expansion was
accomplished by mechanically rolling the tube into the tubesheet. The tack expansion forms a
temporary expansion transition (i.e., a roll transition in the case of Catawba). Following
welding, the tubes were hydraulically expanded for the full depth of the tubesheet. The
transition from the expanded portion of tube within the tubesheet to the unexpanded portion of
the tube at the top of the tubesheet is referred to as the expansion transition region of the tube.
In 2004, at Catawba Unit 2, Duke Energy (the licensee) conducted steam generator tube
inspections. At the time of the inspections, Catawba Unit 2 had operated for approximately
14.7 effective full-power years and the licensee had never identified any cracklike indications in
the steam generator tubes or welds.
As part of the inspection, the licensee planned to use a rotating probe to inspect approximately
25 percent of the tubes in each of the steam generators from 2 inches above the top of the
tubesheet to 9 inches below the top of the tubesheet. During the rotating probe examinations in
the tubesheet region in steam generator B, the licensee found three discrete circumferential
indications in an overexpanded region of one tube. Overexpanded regions such as this are
sometimes called bulges or tubesheet anomalies. These terms are used to distinguish
overexpanded regions of the tubes from regions that have been expanded above the top of the
tubesheet, which may also be referred to as overexpansions. The indications were located
approximately 7 inches below the top of the hot-leg tubesheet. The indications began from the
inside diameter of the tubes and are approximately 30 degrees in circumferential extent. The
overexpanded region extended for approximately 6 inches and the diameter was estimated to
be approximately 0.003 inch greater than the diameter observed in the remainder of the
expanded region. Overexpansions in the tubesheet region are a result of expanding the tube
into a region of the tubesheet which is not perfectly round. This out-of-round condition is the
result of anomalies introduced into the tubesheet during the drilling process (e.g., when the drill
bit wanders). As a result of identifying these circumferential indications, the licensee increased
the scope of the rotating probe examinations in the tubesheet region to include all tubes in all
four steam generators with overexpanded regions in the hot leg. The licensee inspected these
tubes from 2 inches above the top of the tubesheet to the tube end. A total of 1344 tubes in the
hot-leg tubesheet region of all four steam generators have overexpanded regions.
During these additional rotating probe examinations, no additional indications were found in the
overexpanded (bulged) regions; however, several indications were found at the tube ends
(tube-to-tubesheet weld) and one indication was found in the tack expansion region. At the
tube ends, the licensee identified approximately 12 indications in steam generators A, B, and D.
These indications were in the tube-to-tubesheet weld and were not visible during visual
inspections of the weld. The indication in the tack expansion (the region of the tube expanded
into the tubesheet to facilitate welding) was approximately 0.70 inch above the tube-to- tubesheet weld and was circumferentially oriented. It was estimated to be 330 degrees in
circumferential extent and 100 percent through-wall.
Based on these results, the licensee expanded the scope of the rotating probe examinations in
the tack expansion region to include 100 percent of the tubes in steam generator B and 20
percent of the tubes in steam generators A, C, and D. These tubes were inspected from the
tube end to approximately 2 inches above the tube end (which bounds the locations where the
tube end indications were identified).
In steam generator B, 9 tubes were found to have indications in the tack roll region. These
indications were circumferentially oriented and consisted of either single or multiple cracks. No
indications were found in the tack roll region in steam generators A, C, or D. In the tube-to- tubesheet weld region, 188 tubes in steam generator B, 1 tube in steam generator A, and
7 tubes in steam generator D contained indications in the tube-to-tubesheet weld. No
indications were found in the tube-to-tubesheet weld region in steam generator C. Six tubes in
steam generator B were identified with tube end (i.e., tube-to-tubesheet weld) indications that
extended into the tube material. The indications in these tubes were axially and
circumferentially oriented and consisted of either single or multiple cracks. The licensee plugged the tube with the circumferential indications in the overexpanded region
and the tubes with indications in the tack roll region. In addition, the licensee plugged the six
tubes with indications in the weld region that extended into the tube material.
BACKGROUND
In the U.S., only a few cracks (or cracklike indications) have been detected in steam generator
tubes fabricated from thermally treated Alloy 600. Prior to 2004, most (if not all) of these
indications occurred at two plants and were attributed to nonoptimal tube processing. These
cracklike indications occurred in the region of the tube where it passes through the tube support
plates. Additional information concerning this type of cracking is given in NRC Information
Notice 2002-21, Supplement 1, Axial Outside-Diameter Cracking Affecting Thermally Treated
Alloy 600 Steam Generator Tubing.
DISCUSSION
The findings at Catawba Unit 2 are noteworthy because they indicate that degradation can
potentially be occurring at various locations within the tubesheet region of thermally treated
Alloy 600 tubes. The findings are also noteworthy because potential cracklike indications were
first found in manufacturing anomalies (e.g., bulges or tubesheet anomalies) rather than at
other tube locations such as the expansion transition or U-bend region. Historically, rotating
probe inspections have focused on the expansion transition region on the hot-leg side and the
U-bend region of tubes with short-bend radii. Inspections focused on these areas due to the
high operating temperature and residual stress in these regions. The recent experience at
Catawba shows the importance of monitoring all tube locations (such as bulges, dents, dings, and other anomalies from the manufacture of the steam generators) with techniques capable of
finding potential forms of degradation that may be occurring at these locations (refer to Generic
Letter 2004-001, Requirements for Steam Generator Tube Inspections). The Catawba
experience also highlights the need to inspect all regions with high residual stress. Such
inspections will provide added assurance that any degradation at these locations will be
promptly detected.
The inspection of the tube-to-tubesheet weld and the repair of any indications detected in these
welds are not governed by the surveillance requirements in the Catawba Unit 2 technical
specifications. However, indications in the parent tube adjacent to the tube-to-tubesheet weld
are governed by the plant technical specifications. Since the weld is designed at many plants
to serve as part of the reactor coolant pressure boundary (i.e., it is a structural weld), the
findings at Catawba illustrate the importance of inspecting the parent tube adjacent to the weld
and the weld itself for degradation. Evaluating the results of these inspections is important for
verifying the weld and the parent tube will continue to satisfy its design basis. Alternatively, redefining the reactor coolant pressure boundary using a different method of evaluation for the
tube-to-tubesheet joint may demonstrate that degradation in this region is not safety significant.
Recent steam generator tube leaks at several plants with thermally treated Alloy 600 or Alloy
690 tubing (H.B. Robinson, Palo Verde, Shearon Harris) also show the need for thorough inspections and robust inservice inspection programs regardless of the tube material or steam
generator history. Information Notices 2004-17, Loose Part Detection and Computerized Eddy
Current Data Analysis in Steam Generators, and 2004-16, Tube Leakage Due to a Fabrication
Flaw in a Replacement Steam Generator, provide additional details on some of these leakage
events. Although corrosion-related degradation in plants with thermally treated tubing has been
minimal, the recent operating experience at plants with thermally treated steam generator tubes
indicates that damage by loose parts or damage incurred during manufacture of steam
generator tubes can result in primary-to-secondary system leakage. This experience also
shows the importance of being alert to all potential tube degradation mechanisms and to
aggressively examine eddy current inspection signals that may be associated with tube
degradation.
CONTACT
S
This information notice requires no specific action or written response. Please direct any
questions about this matter to the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
/RA/
Patrick L. Hiland, Chief
Reactor Operations Branch
Division of Inspection Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
Kenneth J. Karwoski, NRR
301-415-2752 E-mail: kjk1@nrc.gov
Attachments: 1. PWR Recirculating Steam Generator Figure 1
2. Tube Installed in the Tubesheet Figure 2 Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
OFFICE OES:IROB:DIPM TECH EDITOR EMCB:DE SC:EMCB:DE C:EMCB:DE
NAME OTabatabai PKleene KKarwoski ALLund WHBateman
DATE 04/05/2005 02/23/2005 03/07/2005 03/16/2005 03/17/2005 OFFICE D:DE OES:IROB:DIPM C:IROB:DIPM
NAME MMayfield/CG for/ EJBenner PLHiland
DATE 03/23/2005 04/06/2005 04/07/2005
IN 2005-09 Attachment 1 Steam outtet
Steam
separators
Feedwate r inlet
U-bend portion
of tube
Downcomer annulus
Tube bundle
Tube supports
Tube sheet
Primary inlet Primary outlet
(Hot Leg) (Cold Leg)
PWR Recirculating Steam Generator
Figure 1
IN 2005-09 Attachment 2 I Tube Installed in the Tubesheet I
I Tube I I Expansion Transition I
ITop of Tubesheet I
ITubesheet I
I Not to Scale
Figure 2