ML110460487
| ML110460487 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Perry, Oyster Creek, Grand Gulf, Cooper, Pilgrim, River Bend, Vermont Yankee, Duane Arnold, Clinton, Quad Cities, FitzPatrick |
| Issue date: | 02/15/2011 |
| From: | Porter D GE-Hitachi Nuclear Energy Americas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| MFN 11-023 | |
| Download: ML110460487 (11) | |
Text
GE Hitachi Nuclear Energy February 15, 2011 MFN 11-023 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Part 21 Reportable Condition Notification:
Design Life of D and S Lattice Marathon Control Blades GE Hitachi Nuclear Energy (GEH) has completed its evaluation of the cracking of Marathon Control Rod Blades (CRB) at an international BWR/6. This issue was initially reported on October 20, 2010 as GEH letter MFN 10-327 (Reference 1). Additional information was provided on December 1, 2010 as GEH letter MFN 10-351 (Reference 2).
GEH has determined that the design life, of D and S lattice Marathon Control Blades may be less than previously stated. The design life if not revised, could result in significant control blade cracking and could, if not corrected, create a Substantial Safety Hazard and is considered a reportable condition under 10CFR Part 21.21(d). Marathon C lattice Control Blades are not affected by this condition. The information contained in this document informs the NRC of the conclusions and recommendations derived from GEHs investigation of this issue.
Please contact me if there are any questions on this information.
If you have any questions, please call me at (910) 819-4491.
Sincerely, Dale E. Porter Safety Evaluation Program Manager GE-Hitachi Nuclear Energy Americas LLC Dale E. Porter GE-Hitachi Nuclear Energy Americas LLC Safety Evaluation Program Manager 3901 Castle Hayne Rd.,
Wilmington, NC 28401 USA T 910 819-4491 Dale.Porter@GE.Com
MFN 11-023 Page 2 of 2
References:
- 1. Letter from Dale E. Porter (GEH) to Document Control Desk (US NRC),
Subject:
Part 21 60-Day Interim Report Notification: Crack Indications in Marathon Control Rod Blades, October 20, 2010, MFN 10-327.
- 2. Letter from Dale E. Porter (GEH) to Document Control Desk (US NRC),
Subject:
Update to MFN 10-327: Crack Indications in Marathon Control Rod Blades, December 1, 2010, MFN 10-351.
Attachments:
- 1. GEH Evaluation
- 2. Notification Information Required by 21.21(d)(4)
- 3. US Plants Potentially Affected cc:
S. S. Philpott, USNRC S. J. Pannier, USNRC O. Tabatabai-Yazdi, USNRC J. F. Harrison, GEH J. G. Head, GEH P. L. Campbell, GEH Washington A. A. Lingenfelter, GNF PRC File DRF Section No. 0000-0129-4275
MFN 11-023 Page 1 of 2
- Description of Evaluation
=
Background===
GE Hitachi Nuclear Energy (GEH) manufactures Marathon Control Rod Blades (CRB) for D lattice, BWR/2-4 plants, S lattice, BWR/6 plants, and C lattice, BWR/4-5 plants, as well as for other reactor vendor plants with similar configurations. GEH maintains a continuous surveillance program to monitor Marathon CRB performance in the BWR fleet as required by the NRC Safety Evaluation NEDE-31758P-A. This surveillance program primarily consists of visual inspections of highly irradiated near End-of-Life Marathon CRBs. The most recent update report for the Marathon surveillance program was issued to the BWR fleet in May 2010 (Report # 0000-0071-8269-R2). Since that update was issued GEH has completed the planned visual inspection of four discharged CRBs at an international BWR/6, identified as Plant O in the surveillance report. The visual inspection of these assemblies has revealed cracks on all four CRBs. Some of the cracks were larger than those previously observed and reported in the surveillance report. The cracks were more numerous and occur at locations of lower reported local B10 depletion than previously documented.
Investigation The investigation into the cause of CRB tube cracking has been completed. The investigation has identified an additional cause for concern associated with cracking of high depletion Marathon Control Rod Blades used in D and S lattice type BWR plants.
A rapid thermal transient, with cold-water injection resulting from actuation of the Automatic Depressurization System specific to Plant O has been determined to be a significant contributor to the extent of cracking seen on the Marathon Control Blades. The extent of cracking seen on Marathon CRBs at Plant O has been determined to not represent a condition anticipated to occur at other plants with Marathon CRBs unless a similar or more severe thermal transient should occur. The cause of cracking of CRB tubes is Irradiation Assisted Stress Corrosion Cracking (IASCC). The IASCC results from susceptible material from irradiation, aggressive environment from oxidizing BWR water and excessive tensile stress caused from B4C swelling.
MFN 11-023 Page 2 of 2 As a result of this investigation GEH recommends a Marathon lifetime reduction as follows.
The recommended Marathon CRB lifetime reduction imposes a 60% local B10 depletion limit, or 54% for D lattice 1/4 segment and 55% for S lattice 1/4 segment lifetime limit.
Some D & S lattice Marathon CRBs manufactured after 2006 have an improved square geometry and their lifetime is greater than stated above. Lifetimes of these specific blades will be updated and maintained in GEH Marathon CRB lifetime document. GEH will update and maintain the GEH BWR Control Rod Lifetime document NEDE-30931-12-P, Table 3-3 with revised End-of-Life 1/4 Segment and 4 Segment Average B10 depletions for all applicable control blades.
These revised lifetime depletion limits are higher than those previously communicated that were bounding values for planning purposes. The values stated above are based on the final evaluation of all technical data.
The new lifetime limits will substantially reduce the likelihood of CRB operation with excessive cracking and will assure the CRBs will perform their required safety functions.
ABWR and ESBWR Design Certification Documentation Applicability The issues described above have been reviewed for applicability to documentation associated with 10CFR 52 and it has been determined that there is no affect on the technical information contained in either the ABWR certified design or the ESBWR design in certification.
MFN 11-023 Page 1 of 6 (i)
Name and address of the individual or individuals informing the Commission.
Dale E. Porter GE Hitachi Nuclear Energy Safety Evaluation Program Manager 3901 Castle Hayne Road, Wilmington, NC 28401 (ii)
Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
The basic component that contains a defect is Marathon Control Rod Blades for D and S lattice plants. The following part numbers identify these CRBs:
PLANT TYPE PROJECT/PLANT QTY SHIP YEAR Part Number#
S CLINTON 13 2002 107E1425G001 S
CLINTON 4
2002 107E1425G001 S
CLINTON 12 2004 107E1425G001 S
CLINTON 12 2005 107E1425G001 S
CLINTON 4
2007 105E3995G001 S
GRAND GULF 8
2007 105E3995G001 S
GRAND GULF 12 2008 105E3995G001 S
GRAND GULF 11 2010 105E3995G001 S
PERRY 4
1992 107E6101G001 S
PERRY 9
1993 107E6121G001 S
PERRY 5
1999 107E1425G001 S
PERRY 6
2001 107E1425G001 S
PERRY 25 2003 107E1425G001 S
PERRY 10 2005 107E1425G001 S
PERRY 10 2005 107E1425G001 S
PERRY 10 2006 107E1425G001 S
PERRY 15 2008 105E3995G001 S
RIVER BEND 9
2001 107E1425G001 S
RIVER BEND 2
2004 107E1425G001 S
RIVER BEND 9
2007 105E3995G001 S
RIVER BEND 5
2007 105E3995G001 S
RIVERBEND 9
2009 105E3995G001
MFN 11-023 Page 2 of 6 PLANT TYPE PROJECT/PLANT QTY SHIP YEAR Part Number#
S RIVERBEND 11 2010 105E3995G001 D
BROWNS FERRY 27 2002 107E1421G001 D
BROWNS FERRY 5
2002 107E1421G001 D
BROWNS FERRY 8
1998 107E1421G001 D
BROWNS FERRY 9
1998 107E1421G001 D
BROWNS FERRY 29 1999 107E1421G001 D
BROWNS FERRY 8
1998 107E1421G001 D
COOPER 25 1991 103E1697G007 D
COOPER 12 1995 107E6120G002 D
COOPER 6
2003 107E1421G001 D
COOPER 6
2004 107E1421G001 D
COOPER 4
2006 105E3991G001 D
COOPER 6
2008 105E3991G001 D
COOPER 12 2009 105E3991G001 D
COOPER 18 2009 105E3991G001 D
DRESDEN 4
2001 107E1421G001 D
DRESDEN 18 2002 107E1421G001 D
DRESDEN 18 2003 107E1421G001 D
DRESDEN 10 2004 107E1421G001 D
DRESDEN 1
2005 107E1421G001 D
DRESDEN 9
2007 107E1421G001 D
DRESDEN 10 2010 105E3991G003 D
DRESDEN 9
2009 105E3991G003 D
DUANE ARNOLD 10 2005 107E1421G001 D
DUANE ARNOLD 1
2009 105E3991G003 D
FITZPATRICK 4
1991 103E1697G008 D
FITZPATRICK 15 1996 107E6120G006 D
FITZPATRICK 14 1998 107E1421G002 D
FITZPATRICK 8
2008 105E3991G003 D
FITZPATRICK 8
2010 105E3991G003 D
FITZPATRICK 5
2000 107E1421G002 D
FITZPATRICK 6
2002 107E1421G002 D
FITZPATRICK 4
2002 107E1421G002 D
FITZPATRICK 8
2004 107E1421G002 D
HATCH 5
2004 107E1421G004 D
MONTICELLO 8
2003 107E1421G003 D
MONTICELLO 12 2005 107E1421G003
MFN 11-023 Page 3 of 6 PLANT TYPE PROJECT/PLANT QTY SHIP YEAR Part Number#
D MONTICELLO 16 2006 105E3991G002 D
MONTICELLO 12 2009 105E3991G002 D
OYSTER CREEK 1
1988 103E1076G009 D
OYSTER CREEK 4
1990 103E1076G010 D
OYSTER CREEK 12 1994 107E6120G004 D
OYSTER CREEK 1
2000 107E1421G001 D
OYSTER CREEK 12 2004 107E1421G001 D
OYSTER CREEK 10 2006 107E1421G001 D
OYSTER CREEK 2
2006 107E1421G001 D
PEACH BOTTOM 13 2000 107E1421G001 D
PEACH BOTTOM 9
2001 107E1421G001 D
PEACH BOTTOM 7
2002 107E1421G001 D
PEACH BOTTOM 11 2003 107E1421G001 D
PEACH BOTTOM 9
2004 107E1421G001 D
PEACH BOTTOM 4
2005 107E1421G001 D
PEACH BOTTOM 2
2007 107E1421G001 D
PEACH BOTTOM 4
1992 107E6035G002 D
PEACH BOTTOM 18 1998 107E1421G001 D
PEACH BOTTOM 24 1999 107E1421G001 D
PEACH BOTTOM 2
2008 105E3991G003 D
PEACH BOTTOM 2
2010 105E3991G003 D
PEACH BOTTOM 5
1995 107E6120G002 D
PEACH BOTTOM 12 1997 107E1421G001 D
PILGRIM 3
2003 107E1421G003 D
PILGRIM 10 2004 107E1421G003 D
PILGRIM 8
2009 105E3991G002 D
QUAD CITIES 2
2000 107E1421G001 D
QUAD CITIES 8
2002 107E1421G001 D
QUAD CITIES 10 2002 107E1421G001 D
QUAD CITIES 18 2004 107E1421G001 D
QUAD CITIES 13 2005 107E1421G001 D
QUAD CITIES 1
2006 107E1421G001 D
QUAD CITIES 4
2007 105E3991G003 D
QUAD CITIES 13 2007 105E3991G003 D
QUAD CITIES 14 2007 107E1421G001 D
QUAD CITIES 7
2009 105E3991G003 D
QUAD CITIES 10 2010 105E3991G003
MFN 11-023 Page 4 of 6 PLANT TYPE PROJECT/PLANT QTY SHIP YEAR Part Number#
D VERMONT YANKEE 8
1990 103E1076G012 D
VERMONT YANKEE 4
1991 103E1697G007 D
VERMONT YANKEE 4
1993 107E6120G002 D
VERMONT YANKEE 6
1994 107E6120G002 D
VERMONT YANKEE 4
1996 107E6120G002 D
VERMONT YANKEE 4
1997 107E1421G001 D
VERMONT YANKEE 1
1999 107E1421G001 D
VERMONT YANKEE 4
2001 107E1421G001 D
VERMONT YANKEE 8
2004 107E1421G002 D
VERMONT YANKEE 4
2008 105E3991G003 (iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
GE Hitachi Nuclear Energy (iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
GE Hitachi Nuclear Energy Marathon Control Rod Blades have the potential to develop significant cracks on the absorber tubes that contain boron carbide capsules.
Significant cracking of the absorber tubes could result in loss of boron carbide that could affect Control Blade Reactivity Worth Requirements.
(v)
The date on which the information of such defect or failure to comply was obtained.
A Potential Reportable Condition Evaluation, in accordance with 10CFR Part 21, was initiated on August 24, 2010. A 60-day interim notification was issued on October 20, 2010 to extend the evaluation period.
MFN 11-023 Page 5 of 6 (vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.
The population for Marathon Control Rod Blade with the potential for cracking includes all Marathon Control Rods Blades installed in BWR/2-4, D lattice plants and BWR/6, S lattice plants. Marathon C lattice Control Blades are not affected. A list of all US plants that have been supplied these Marathon Control Rod Blades is provided in of this document. A list of all part numbers and quantities sold is listed in the table in question ii.
(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
GEH is reducing the End-of-Life depletion limits of its Marathon CRBs used in D and S lattice plants. The current 100% local B10 depletion limit is reduced to a 60% local B10 depletion limit, or 54% D lattice 1/4 segment and 55% S lattice 1/4 segment lifetime limit.
Some D & S lattice Marathon CRBs manufactured after 2006 have an improved square geometry and their lifetime is greater than stated above. Lifetimes of these specific blades will be updated and maintained in the GEH BWR Control Rod Lifetime document, NEDE-30931-12-P. GEH will update and maintain Table 3-3 of the lifetime document with revised End-of-Life Quarter Segment and 4 Segment Average B10 Depletions for all applicable control blades.
MFN 11-023 Page 6 of 6 (viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
For all plants containing D and S lattice Marathon Control Blades, remove Marathon CRBs from service prior to exceeding the revised lifetime limits.
If any Marathon CRB is in service and exceeds the new recommended lifetime limit, continue operating those blades while monitoring reactor coolant boron and tritium per normal plant procedures. If no significant increase in boron and/or tritium is observed, continue operation until the end of the cycle. If a significant increase in reactor coolant boron and/or tritium is detected, contact GEH. Continued monitoring for reactor coolant boron and/or tritium concentrations is recommended to detect cracking of any design CRB.
Continue to support the GEH Marathon CRB surveillance program as directed by NEDE-31758P-A.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
This is not an early site permit concern.
MFN 11-023 Page 1 of 1
- US Plants Potentially Affected D & S Lattice Plants C Lattice Plants Utility Plant
__X_
Constellation Nuclear Nine Mile Point 1
__X_
Constellation Nuclear.
Nine Mile Point 2
__X_
Detroit Edison Co.
Fermi 2
__X_
Dominion Generation Millstone 1
__X_
Energy Northwest Columbia
__X_
Entergy Nuclear Northeast FitzPatrick
__X_
Entergy Nuclear Northeast Pilgrim
__X_
Entergy Nuclear Northeast Vermont Yankee
__X_
Entergy Operations, Inc.
Grand Gulf
__X_
Entergy Operations, Inc.
River Bend
__X_
Exelon Generation Co.
Clinton
__X_
Exelon Generation Co.
Oyster Creek
__X_
Exelon Generation Co.
Dresden 2 & 3
__X_
Exelon Generation Co.
LaSalle 1 & 2
__X_
Exelon Generation Co.
Limerick 1 & 2
__X_
Exelon Generation Co.
Peach Bottom 2 & 3
__X_
Exelon Generation Co.
Quad Cities 1 & 2
__X_
FirstEnergy Nuclear Operating Co.
Perry 1
__X_
FPL Energy Duane Arnold
__X_
Nebraska Public Power District Cooper
__X_
Xcel Energy Monticello
__X_
Susquehanna 1 & 2
__X_
Progress Energy Brunswick 1 & 2
__X_
Southern Nuclear Operating Co.
Hatch 1 & 2
__X_
Tennessee Valley Authority Browns Ferry 1 - 3