ML043220627
| ML043220627 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/15/2004 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC0167, TAC MC0168 | |
| Download: ML043220627 (53) | |
Text
November 15, 2004 10 CFR 50.55a(a)(3)(i)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of )
Docket Nos. 50-260 Tennessee Valley Authority )
50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 2, AND 3 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM - REQUESTS FOR RELIEF 2-ISI-22, AND 3-ISI-18 FOR EXAMINATION OF REACTOR PRESSURE VESSEL (RPV)
NOZZLE-TO-VESSEL SHELL WELDS AND NOZZLE BLEND RADII - REVISION TO INCORPORATE ASME CODE CASE N-702 AS TECHNICAL BASIS FOR RELIEF (TAC NOS. MC0167 AND MC0168)
This letter submits revised BFN Units 2 and 3 requests for relief 2-ISI-22 and 3-ISI-18 for NRC review and approval. These requests for relief were revised to incorporate ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR)
Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1, as the technical basis for the requests. These revised relief requests supersede those initially submitted by TVA.
The requests for relief were initially submitted for NRC review by TVA letter dated July 25, 2003. These requests cited the Boiling Water Reactor Vessel Internals Project (BWRVIP) technical report entitled BWRVIP-108: BWR Vessel and Internals Project, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-To-Vessel Shell Welds and Nozzle Blend Radii,@ as the technical basis for the requests. Subsequent to TVAs requests for relief submittal, ASME issued Code Case N-702 (February 20, 2004).
ASME Code Case N-702 is based on the conclusions stated in the BWRVIP-108 report which used a probabilistic fracture mechanics evaluation considering: (1) sample size large enough to effectively identify aging degradation, (2) sample size consistent with current industry requirements, and
U.S. Nuclear Regulatory Commission Page 2 November 15, 2004 (3) examination sampling size reduction sufficient to result in significant cost savings and radiological dose reduction.
ASME Code Case N-702 states that the nondestructive examination frequency for RPV nozzle-to-shell welds and nozzle inner radii may be reduced from 100 percent each 10-year inspection interval to 25 percent including at least one nozzle from each system and nominal pipe size. The Code Case also states that a visual examination (VT-1) may be used for ASME Section XI, Code Examination Category Item No. B3.100, RPV nozzle inner radius sections, in lieu of a volumetric examination.
of this letter contains revised BFN Unit 2 request for relief, 2-ISI-22, for NRC review and approval. The revised BFN Unit 3 request for relief, 3-ISI-18, is provided in.
TVA requests approval of these requests for relief by November 18, 2005 (end of second ten-year inspection interval for Unit 3) to support resource planning for the Unit 3 Cycle 12 refueling outage (Spring 2006).
There are no new regulatory commitments in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, Original signed by:
T. E. Abney Manager of Licensing and Industry Affairs cc: See Page 3
U.S. Nuclear Regulatory Commission Page 3 November 15, 2004 Enclosures cc (Enclosures):
Mr. Robert Carter, EPRI BWRVIP Assessment Manager EPRI NDE Center 1300 W. T. Harris Boulevard Charlotte, North Carolina 28262 Mr. Tom Mulford, EPRI BWRVIP Integration Manager Electric Power Research Institute P.O. Box 10412 3412 Hillview Avenue Palo Alto, California 94303 (Via NRC Electronic Distribution)
Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
U.S. Nuclear Regulatory Commission Page 4 November 15, 2004 JWD:BAB Enclosures cc (Enclosures):
A. S. Bhatnagar, LP 6A-BFN Samuel Flood, PMB 2A-BFN J. C. Fornicola, LP 6A-C D. F. Helms, BR 4T-C R. G. Jones, NAB 1A-BFN K. L. Krueger, POB 2C-BFN M. J. Lorek, LP 6A-C R. F. Marks, PAB 1C-BFN F. C. Mashburn, BR 4X-C J. R. Rupert, NAB 1A-BFN K. W. Singer, LP 6A-C M. D. Skaggs, PAB 1E-BFN E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C EDMS WT CA-K s:\\lic\\submit\\subs\\Units 2, & 3 Relief Request Using BWRVIP-108 & N-702 Tech Basis1.doc
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 2-ISI-22, REVISED TO INCORPORATE ASME CODE CASE N-702 (SEE ATTACHED)
E2-2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 2-ISI-22, REVISED TO INCORPORATE ASME CODE CASE N-702 Executive Summary:
In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from inservice inspection requirements of the 1995 Edition, 1996 Addenda,Section XI of the ASME Boiler and Pressure Vessel Code for the volumetric examination of Class 1, reactor pressure vessel (RPV) nozzle-to-vessel welds and nozzle inner radius sections. The Code examination requirement is for a volumetric examination of 100 percent of the ASME Section XI, Examination Category B-D, AFull Penetration Welded Nozzles in Vessels,@
Item No. B3.90, AReactor Vessel Nozzle to Vessel Welds, and Item No. B3.100, AReactor Vessel Nozzle Inner Radius Section@ each ten-year inspection interval.
This request for relief applies to the BFN Unit 2 Reactor Pressure Vessel and RPV Head nozzles, with the exception of the six (N4) feedwater and one (N9) Control Rod Drive Return Line (capped) nozzles. These nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME,Section XI, Appendix VIII and the Performance Demonstration Initiative (PDI) Program.
TVA proposes to adopt ASME Code Case N-702, Alternate Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-To-Shell WeldsSection XI, Division 1. This Code case provides an alternative for BWRs for the examination reduction of the nozzle-to-shell welds and nozzle inner radius sections from 100 percent to a minimum of 25 percent of the nozzles and nozzle inner radius sections every ten-year inspection interval. The 25 percent coverage refers to 25 percent of the nozzle-to-shell welds for each system and nominal pipe size (e.g., 1 of 4 Main Steam
E2-3 nozzles) for items listed in ASME Section XI, Table IWB-2500-1, Examination Category B-D, Items Numbers B3.90, and B3.100.
For the reactor pressure vessel nozzle inner radius sections, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution. For the RPV head nozzle inner radius sections, TVA will perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements.
Note: The change from volumetric (UT) to enhanced visual (VT-1) was submitted as two separate requests for relief, 2-ISI-16 and 2-ISI-17 to NRC by TVA letters dated April 23, and September 5, 2002, and approved by NRC letter dated October 7, 2002.
All examinations will be performed with personnel, procedures, and equipment qualified in accordance with the ASME Section XI Code, 1995 Edition, 1996 Addenda, Appendix VIII and the Performance Demonstration Initiative (PDI)
Program requirements.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety. The 25 percent examination frequency, is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
Unit:
Two (2)
ISI Interval:
ASME Section XI, Third Ten-Year ISI Interval (May 25, 2001 to May 24, 2011)
System(s)/
Components:
Reactor Pressure Vessel (RPV), Nozzle-to-Vessel Welds and RPV Nozzle Inner Radius Sections (Total of 24 nozzles):
Reactor Recirculation Outlet Nozzles (28-inch diameter), N1A and N1B (Total of 2 nozzles)
E2-4 Reactor Recirculation Inlet Nozzles (12-inch diameter), N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, and N2K (Total of 10 nozzles)
Main Steam Nozzles (26-inch diameter), N3A, N3B, N3C, and N3D (Total of 4 nozzles)
Core Spray Nozzles (10-inch diameter), N5A and N5B (Total of 2 nozzles)
Reactor Pressure Vessel (RPV) Head Nozzles, N6A, N6B, (6-inch diameter) and N7 (4-inch diameter) (Total of 3 nozzles)
Jet Pump Instrumentation Nozzles (4-inch diameter), N8A and N8B (Total of 2 nozzles)
Standby Liquid Control Nozzle (1.5-inch diameter), N10 (Total of 1 nozzle)
ASME Code Class:
ASME Code Class 1 ASME Section XI Code Edition:
1995 Edition, 1996 Addenda Note: The Code of Record for the BFN Unit 2 Second Ten-Year ISI Interval is the 1995 Edition, 1996 Addenda for component selection. TVA has also adopted the 1995 Edition with the 1996 addenda (all TVA nuclear sites) for performance of nondestructive examinations.
Code Table:
IWB-2500-1 Examination Category:
B-D, AFull Penetration Welded Nozzles In Vessels@
Examination Item Number(s):
B3.90, ANozzle-To-Vessel Welds@, and B3.100, ANozzle Inner Radius Sections,@
Code Requirement:
The 1995 Edition, 1996 Addenda, ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and Item No. B3.100, requires a volumetric examination of 100 percent of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius sections each ten-year inspection interval.
E2-5 Code Requirements From Which Relief Is Requested:
Relief is requested from the 1995 Edition, 1996 Addenda, ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No.
B3.90 and Item No. B3.100, which requires a volumetric examination of 100 percent each ten-year inspection interval of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section.
List Of Items Associated With The Relief Request:
Reactor Pressure Vessel Nozzles, N1A, N1B, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N5A, N5B, N6A, N6B, N7, N8A, N8B, and N10 (Total of 24 nozzles)
Note: The six feedwater (N4), and one Control Rod Drive Return Line (N9) (capped) nozzle-to-vessel welds and nozzle inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Section XI, Table IWB-2500-1, Appendix VIII, and the Performance Demonstration Initiative (PDI) Program. (TVA will take both ASME Section XI Code, and GE-NE-523-A71-0594-A examination credit for all six Feedwater nozzles.)
Basis For Relief Request:
Pursuant to 10 CFR 50.55a(a)(3)(i) TVA is requesting relief from ASME Section XI requirements to perform the volumetric examinations described above.
TVA proposes to adopt ASME Code Case N-702, Alternate Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1.
This Code Case provides an alternative for BWRs for reduction of the nozzle-to-shell welds and nozzle blend radii examinations from 100 percent to 25 percent of the nozzles each 10-year inspection interval. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
E2-6 The 25 percent examination frequency, is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The 25 percent sampling level is similar to industry practice and, in some cases, exceeds current practice.
For example:
- ASME Code Section XI, IWB-2500 requires 25 percent of Category B-J (Item No. B9.11) circumferential welds to be inspected each inspection interval.
ASME Code Case N-560, (Risk Informed Inspection) requires inspection of 10 percent of higher risk Class I Category B-J piping welds.
ASME Code Case N-578, (Risk Informed Inspection) requires inspection of at least 25 percent of the highest risk, (Risk Category 1, 2, and 3) and At least 10 percent of the next highest risk, (Risk Category 4 or 5)
Class I piping welds.
ASME Code Section XI, IWC-2500 (Class II piping) Category C-F-1 and C-F-2 requires inspection of 7.5 percent of welds.
Generic Letter 88-01 requires 25 percent inspection of Category A piping welds.
The 25 percent sampling provides a significant cost savings and reduces worker dose exposure.
Several utilities have estimated that the proposed reduction of inspection requirements would result in a savings of up to $750,000 per ten-year inspection interval, not including exposure considerations. The dose savings for BFN Unit 2 would be approximately 6.5 to 7 REM over a ten-year ISI inspection interval.
In the first Unit 2 ten-year inspection interval 30 of 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination. In the second Unit 2 ten-year ISI inspection interval,
E2-7 31 of the 31 reactor pressure vessel nozzle-to-shell welds and 30 inner radius sections received a volumetric examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
In the third (current) Unit 2 ten-year ISI inspection interval, 6 of the 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections have received a volumetric (UT) examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
Also, in the third (current) Unit 2 ten-year inspection interval, seven (7) of 31 reactor pressure vessel nozzle-to-shell welds have received a volumetric examination. The inner radius sections of these nozzles received an enhanced visual (EVT-1) examination from the vessel inside diameter. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
TVA considers the above proposed alternative examinations, when considered with the examination history of the BFN RPV nozzles, will provide an acceptable level of quality and safety. The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
Alternate Examination:
In accordance with 10 CFR 50.55a(a)(3)(i),
TVA will adopt ASME Code Case N-702 (See Attachment A of this enclosure) and perform the following alternate examinations:
RPV Nozzle-To-Vessel Welds TVA will perform volumetric (UT) examinations of 25 percent of the ASME Section XI, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Item No. B3.90, Reactor Vessel Nozzle to Vessel Welds, each ten-year inspection interval. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
E2-8 RPV Nozzle, Inner Radius Section For the reactor pressure vessel nozzles inner radius section, ASME Section XI Item B3.100, TVA will perform an enhanced remote visual (VT-1) examination of 25 percent of the nozzles, capable of a 1-mil wire resolution in accordance with ASME Section XI, VT-1 requirements. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
RPV Head Nozzle, Inner Radius Section For the RPV head nozzles inner radius section, TVA will perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
Note: The change from volumetric (UT) to enhanced visual (VT-1) was submitted by TVA as two separate requests for relief, 2-ISI-16 and 2-ISI-17 to NRC by letters dated April 23, and September 5, 2002. TVAs Requests were approved by NRC letter dated October 07, 2002.
The following nozzles will be examined during the current ten-year inspection interval: N1 (1 of 2), N2 (3 of 10) N3 (1 of 4), N5 (1 of 2), N6 (1 of 2), N7 (1 of 1), N8 (1 of 1), N9 (1 of 1), and N10 (1 of 1) (Total of 11 nozzles examined).
All examinations will be performed with personnel, procedures, and equipment qualified in accordance with the ASME Section XI Code, 1995 Edition, 1996 Addenda, Appendix VIII and the Performance Demonstration Initiative (PDI) Program requirements.
Justification For The Granting Of Relief:
The BFN Unit 2 RPV nozzles were nondestructively examined during fabrication and have previously been examined using
E2-9 inservice ultrasonic (UT) techniques specific to the nozzle configuration.
No indication of fabrication defects or service related cracking has been detected by these examinations. See Attachment C of this enclosure for RPV nozzle and inner radius section listing, UT examinations performed, examination coverage, and examination results for the BFN Unit 2 first, second, and third ten-year ISI inspection intervals.
In the first Unit 2 inspection interval 30 of 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination. In the second Unit 2 ten-year inspection interval, 31 of 31 reactor pressure vessel nozzle-to-shell welds and 30 inner radius sections received a volumetric examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
In the third (current) Unit 2 ten-year inspection interval, 6 of 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections have received a volumetric (UT) examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
Also, in the third (current) Unit 2 ten-year inspection interval seven (7) of 31 reactor pressure vessel nozzle-to-shell welds received a volumetric examination. The inner radius sections of these seven nozzles received an enhanced visual (EVT-1) examination from the vessel ID. The examination results were acceptable.
A significant number of RPV nozzle weld examinations have been performed for BFN and other units in the BWR fleet, that have been operational for periods up to 30 years, using modern examination techniques capable of detecting significant cracking if it were present. No degradation or failure mechanism has been identified in nozzle-to-vessel or nozzle inner radius areas, other than feedwater and CRDM nozzles.
In summary, TVA requests a reduction in RPV nozzle and nozzle inner radius section examinations from 100 percent to 25 percent
E2-10 (of each nozzle type and size) for each ten-year inspection interval. The 25 percent examination frequency, is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The 25 percent sampling alternative also provides a significant cost savings and reduces personnel dose exposure.
Implementation Schedule:
This request for relief is applicable to the BFN Unit 2, Third Ten-Year ASME Section XI Inservice Inspection Interval (May 25, 2001 to May 24, 2011).
Attachments:
Attachment A - ASME Code Case N-702 Attachment B - (7 sketches)
Sketch SK-B2001, Reactor Pressure Vessel Assembly Sketch SK-B2017, N1, Recirculation Outlet Nozzles Sketch SK-B2018, N2, Recirculation Inlet Nozzles, N3, Main Steam Nozzles, and N5, Core Spray Nozzles Sketch SK-B2016, N6, Reactor Head Spray/Instrumentation Nozzle Sketch SK-B2015, N7, Reactor Head Vent Nozzle Sketch SK-B2019, N8, Jet Pump Instrumentation Nozzle Sketch SK-B2022, N10, Differential Pressure and Liquid Volume Control Nozzle Attachment C - Unit 2 RPV Nozzle and Inner Radius Section Examinations
E2-11 Attachment A 2-ISI-22 ASME Code Case N-702
E2-12
E2-13 Attachment B 2-ISI-22 SEVEN (7) Sketches Sketch SK-B2001, Reactor Pressure Vessel Assembly Sketch SK-B2017, N1, Recirculation Outlet Nozzles Sketch SK-B2018, N2, Recirculation Inlet Nozzles, N3, Main Steam Nozzles, and N5, Core Spray Nozzles Sketch SK-B2016, N6, Reactor Head Spray/Instrumentation Nozzle Sketch SK-B2015, N7, Reactor Head Vent Nozzle Sketch SK-B2019, N8, Jet Pump Instrumentation Nozzle Sketch SK-B2022, N10, Differential pressure and Liquid Volume Control Nozzle
E2-14 SK-B2001
E2-15 SK-B2017
E2-16 SK-B2018
E2-17 SK-B2016
E2-18 SK-B2015
E2-19 SK-B2019
E2-20 SK-B2022
E2-21 Attachment C 2-ISI-22 UNIT 2 RPV NOZZLE EXAMINATIONS
SUMMARY
E2-22 REQUEST FOR RELIEF 2-ISI-22 UNIT 2 RPV NOZZLE EXAMINATIONS
SUMMARY
COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE
- Note 1 N1A 3
7 9/24/80 10/11/94 R-065, R-067, R-070 R-1001 A
A
- Note 1 60%
N1A-IR 5B 7
7/20/90 10/6/94 R-1400 R-1002 A
A
- Note 1 100%
N1B 4
9 9/28/82 10/15/97 R-181, R-178, R-195 R-207 A
A
- Note 1 72%
N1B-IR 5B 9
7/20/90 11/3/97 R-1399 R-207A A
A
- Note 1 100%
N2A 4
9 9/28/82 10/15/97 R-171, R-183, R-199 R-208 A
A
- Note 1 77%
N2A-IR 4
9 9/28/82 11/21/97 R-202 R-208A A
A
- Note 1 100%
N2B 1/3 7
5/17/78 9/23/80 10/23/94 R-048, R-063 R-1021 A
A
- Note 1 52%
N2B-IR 1
7 5/20/78 10/6/94 R-046 R-1022 A
A
- Note 1 100%
N2C 4
9 9/28/82 10/15/97 R-172, R-182, R-196 R-209 A
A
- Note 1 77%
N2C-IR 4
9 9/28/82 11/21/97 R-200 R-209A A
A
- Note 1 100%
N2D 5B 11 9/20/86 10/22/87 4/6/01 R-137, R-829, R-832 R-126 A
A
- Note 1 67%
N2D-IR 5B 11 9/25/86 4/6/01 R-193 R-126A A
A
- Note 1 100%
N2E 5B 11 9/20/86 10/22/87 4/7/01 R-136, R-828, R-833 R-127 A
A
- Note 1 67%
N2E-IR 5B 11 9/25/86 4/7/01 R-192 R-127A A
A
- Note 1 100%
N2F 4A 7
6/6/81 10/22/94 R-006, R-011, R-013 R-1023 A
A
- Note 1 55%
N2F-IR 4A 7
6/7/81 10/6/94 R-020 R-1024 A
A
- Note 1 100%
N2G 4
9 9/28/82 10/15/97 R-179, R-180, R-198 R-210 A
A
- Note 1 77%
N2G-IR 4
9 9/28/82 11/21/97 R-206 R-210A A
A
- Note 1 100%
N2H 4
9 9/28/82 10/15/97 R-173, R-184, R-197 R-211 A
A
- Note 1 77%
N2H-IR 4
9 9/29/82 11/21/97 R-207 R-11A A
A
- Note 1 100%
N2J 4A 7
6/6/81 10/22/94 R-007, R-014, R-015 R-1025 A
A
- Note 1 55%
N2J-IR 4A 7
6/7/81 10/6/94 R-019 R-1026 A
A
- Note 1 100%
N2K 5B 11 9/16/86 10/22/87 10/7/01 R-138, R-830, R-834 R-128 A
A
- Note 1 67%
E2-23 COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N2K-IR 5B 11 9/25/86 10/7/01 R-194 R-128A A
A
- Note 1 100%
N3A 5B 11 9/27/86 10/21/87 3/31/01 R-198, R-201, R-893 R-129 A
A
- Note 1 61%
N3A-IR 5B 11 9/28/86 3/31/01 R-255 R-129A A
A
- Note 1 100%
N3B 4
9 9/26/82 10/15/97 R-067, R-074, R-075 R-212 A
A
- Note 1 75%
N3B-IR 4
9 9/21/82 11/21/97 R-142 R-212A A
A
- Note 1 100%
N3C 5B 11 9/27/86 12/21/86 3/31/01 R-196, R-199, R-892 R-130 A
A
- Note 1 61%
N3C-IR 5B 11 9/28/86 3/31/01 R-254 R-130A A
A
- Note 1 100%
N3D 1
7 5/17/78 10/13/94 R-047 R-1003 A
A
- Note 1 57%
N3D-IR 1
7 5/20/78 10/6/94 R-045 R-1004 A
A
- Note 1 100%
N4A 3
7 10/9/80 10/7/94 R-107, R-109, R-122 R-1009 A
A
- Note 1 59%
N4A-IR 3
7 10/7/80 10/17/94 R-105 R-1009 A
A
- Note 1 100%
N4B 4
9 9/12/82 10/15/97 R-089, R-091, R-094 R0213 A
A
- Note 1 67%
N4B-IR 4
9 9/21/82 11/21/97 R-140 R-213A A
A
- Note 1 100%
N4C 4
9 9/12/82 10/15/97 R-088, R-090, R-095, R-103 R-214 A
A
- Note 1 67%
N4C-IR 4
9 9/21/82 11/21/97 R-141 R-214A A
A
- Note 1 100%
N4D 5B 11 9/20/86 12/22/87 4/5/01 R-128, R-134, R-897 R-131 A
A
- Note 1 69%
N4D-IR 5B 11 9/25/86 4/5/01 R-190 R-131A A
A
- Note 1 100%
N4E 5B 11 9/20/86 10/22/87 4/5/01 R-126, R-133, R-895 R-132 A
A
- Note 1 69%
N4E-IR 5B 11 9/25/86 4/3/01 R-189 R-132A A
A
- Note 1 100%
N4F 3
7 10/9/80 10/17/94 R-108, R-110, R-121 R-1005 A
A
- Note 1 54%
N4F-IR 3
7 10/7/80 10/17/94 R-104, R-008, R-010, R-012 R-1007 A
A
- Note 1 100%
E2-24 COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N5A-IR 3
7 10/8/80 10/20/94 R-114 R-1028 A
A
- Note 1 100%
N5B 4
9 9/24/82 10/15/97 R-089, R-105, R-106 R-215 A
A
- Note 1 65%
N5B-IR 4
9 9/21/82 11/21/97 R-138 R-215A A
A
- Note 1 100%
N6A 3
6 9/18/80 2/13/93 R-050, R-051, R-052 R-064 A
A
- Note 1 100%
N6A-IR 3/5B 6
10/3/80 11/4/88 2/13/93 R-087, R-1111 R-063 A
A
- Note 1 100%
N6B 5B 10 11/16/87 4/25/90 R-859, R-862, R-865 R-353 A
A
- Note 1 100%
N6B-IR 5B 10 11/4/88 4/25/90 R-1110 R-331 A
A
- Note 1 100%
N7 5B 10 11/16/87 4/23/90 R-854, R-857, R-860 R-352 A
A
- Note 1 100%
N7-IR 5B 10 11/4/88 4/25/90 R-1112 R-335 A
A
- Note 1 100%
N8A 3
7 9/24/80 10/17/94 R-061, R-062, R-069 R-1008 A
A
- Note 1 68%
N8A-IR 3
7 10/6/80 10/18/94 R-101 R-1011 A
A
- Note 1 73%
N8B 5B 11 9/20/86 11/16/87 4/3/01 R-139, R-831, R-835 R-133 A
A
- Note 1 72%
N8B-IR 5B 11 9/25/86 4/4/01 R-191 R-133A A
A
- Note 1 100%
N9 4
9 9/24/82 10/15/97 R-098, R-104, R-161 R-216 A
A
- Note 1 75%
N9-IR 4
9 9/21/82 11/21/97 R-139 R-216A A
A
- Note 1 100%
N10 11 4/3/01 R-134 A
56%
Note 1: The examination method (UT) and techniques utilized in the First Ten-Year ISI Interval were basically the same as used in the Second Ten-Year ISI Interval, therefore the percentage of examination coverage are essentially the same for the RPV Nozzle-To-Vessel Shell Welds and Inner Radius Sections.
Note 2: In results column, A refers to acceptable per ASME Section XI, Subarticle IWB-3512 acceptance criteria.
E2-25 UNIT 2 RPV NOZZLE EXAMINATIONS THIRD (CURRENT) INTERVAL, FIRST PERIOD ONLY COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N1A 12 3/4/03 R-160 A
48.8%
N1A-IR 12 3/7/03 R-169 A
100%
N2B 12 3/3/03 R-161 A
51.5%
N2B-IR 12 3/7/03 R-167 A
60%
N2F 12 3/3/03 R-162 A
51.5%
N2F-IR 12 3/7/03 R-169 A
60%
N2J-IR 12 3/7/03 R-169 A
60%
N3D 12 3/1/03 R-164 A
47.3%
N3D-IR 12 3/3/03 R-169 A
100%
N4A 12 3/2/03 R-141 A
45.4%
N4A-IR 12 3/2/03 R-141 A
100%
N4B 12 3/4/03 R-142 A
45.4%
N4B-IR 12 3/4/03 R-142 A
100%
N4C 12 3/1/03 R-143 A
45.4%
N4C-IR 12 3/1/03 R-143 A
100%
N4D 12 3/4/03 R-144 A
45.4%
N4D-IR 12 3/4/03 R-144 A
100%
N4E 12 3/2/03 R-145 A
45.45 N4E-IR 12 3/2/03 R-145 A
100%
N4F 12 3/4/03 R-146 A
45.4%
N4F-IR 12 3/4/03 R-146 A
100%
N6A 12 2/28/03 R-110 A
90.5%
N6A-IR 12 3/1/03 R-106 A
100%
N8A 12 3/5/03 R-165 A
89.5%
N8A-IR 12 3/7/03 R-169 A
60%
Note: In results column, A refers to acceptable per ASME Section XI, Subarticle IWB-3512 acceptance criteria.
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (SECOND TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 3-ISI-18, REVISED TO INCORPORATE ASME CODE CASE N-702 (SEE ATTACHED)
E2-2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (SECOND TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 3-ISI-18, REVISED TO INCORPORATE ASME CODE CASE N-702 Executive Summary:
In accordance with 10 CFR 50.55a(a)(3)(i),
TVA is requesting relief from inservice inspection requirements of the 1989 Edition, no Addenda,Section XI of the ASME Boiler and Pressure Vessel Code for the volumetric examination of Class 1, reactor pressure vessel (RPV) nozzle-to-vessel welds and nozzle inner radius sections. The Code examination requirement is for a volumetric examination of 100 percent of the ASME Section XI, Examination Category B-D, AFull Penetration Welded Nozzles in Vessels,@ Item No. B3.90, AReactor Vessel Nozzle to Vessel Welds and Item No. B3.100, AReactor Vessel Nozzle Inner Radius Section@
each 10-year inspection interval.
This request for relief applies to the BFN Unit 3 Reactor Pressure Vessel and RPV Head nozzles, with the exception of the six (N4) feedwater and one (N9) Control Rod Drive Return Line (capped) nozzles. These nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME,Section XI, Appendix VIII and the Performance Demonstration Initiative (PDI) Program.
TVA proposes to adopt ASME Code Case N-702, Alternate Requirements for Boiling Water Reactor (BWR) Nozzle and Inner Radius and Nozzle-To-Shell WeldsSection XI, Division 1.
This Code Case provides an alternative for BWRs for examination reduction of nozzle-to-shell welds and nozzle inner radius sections from 100 percent to a minimum of 25 percent of the nozzles and nozzle inner radius sections every ten-year inspection interval. The 25 percent coverage refers to 25 percent of the nozzle-to-shell welds for each system and
E2-3 nominal pipe size (e.g., 1 of 4 Main Steam nozzles) for items listed in ASME Section XI, Table IWB-2500-1, Examination Category B-D, Items Numbers B3.90, and B3.100.
For the reactor pressure vessel nozzle inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution.
Note: The change from volumetric (UT) to enhanced visual (VT-1) was submitted as two separate requests for relief, 3-ISI-14 and 3-ISI-15, by TVA letter dated May 9, 2003.
TVAs request was approved by NRC letter dated February 11, 2004.
For the RPV head nozzle inner radius, TVA will perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements.
Note: The change from volumetric (UT) to enhanced visual (VT-1) was submitted in a request for relief, 3-ISI-11, to NRC by TVA letters dated August 13, 2001, January 9 and February 5, 2002, and approved by NRC letter dated March 13, 2002.
All examinations will be performed with personnel, procedures, and equipment qualified in accordance with the ASME Section XI Code, 1995 Edition, 1996 Addenda, Appendix VIII and the Performance Demonstration Initiative (PDI)
Program requirements.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety. The 25 percent examination frequency, is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
Unit:
Three (3)
ISI Interval:
ASME Section XI, Second Ten-Year ISI Interval (November 19, 1996 to November 18, 2005)
E2-4 System(s)/
Components:
Reactor Pressure Vessel (RPV), Nozzle-to-Shell Welds and nozzle Inner Radius Sections (Total of 24 nozzles):
Reactor Recirculation Outlet Nozzles (28-inch diameter), N1A and N1B (Total of 2 nozzles)
Reactor Recirculation Inlet Nozzles (12-inch diameter), N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, and N2K (Total of 10 nozzles)
Main Steam Nozzles (26-inch diameter), N3A, N3B, N3C, and N3D (Total of 4 nozzles)
Core Spray Nozzles (10-inch diameter), N5A and N5B (Total of 2 nozzles)
Reactor Pressure Vessel (RPV) Head Nozzles, N6A, and N6B, (6-inch diameter) and N7 (4-inch diameter) (Total of 3 nozzles)
Jet Pump Instrumentation Nozzles (4-inch diameter), N8A and N8B (Total of 2 nozzles)
Standby Liquid Control Nozzle (1.5-inch diameter), N10 (Total of 1 nozzle)
ASME Code Class:
ASME Code Class 1 ASME Section XI Code Edition:
1989 Edition with no Addenda Note: The Code of Record for the BFN Unit 3 Second Ten-Year ISI Interval is the 1989 Edition, with no Addenda for component selection. However, TVA has adopted the 1995 Edition with the 1996 addenda (all TVA nuclear sites) for performance of nondestructive examinations.
Code Table:
IWB-2500-1 Examination Category:
B-D, AFull Penetration Welded Nozzles In Vessels@
Examination Item Number(s):
B3.90, ANozzle-To-Vessel Welds@, and B3.100, ANozzle Inner Radius Sections,@
E2-5 Code Requirement:
The 1989 Edition with no Addenda, ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and Item No.
B3.100, requires a volumetric examination of 100 percent of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius sections each ten-year inspection interval.
Code Requirements From Which Relief Is Requested:
Relief is requested from the 1989 Edition with no Addenda, ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and Item No. B3.100, which requires a volumetric examination of 100 percent each ten-year inspection interval of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section.
List Of Items Associated With The Relief Request:
Reactor Pressure Vessel Nozzles, N1A, N1B, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N5A, N5B, N6A, N6B, N7, N8A, N8B, and N10 (Total of 24 nozzles)
Note: The six Feedwater (N4), and one Control Rod Drive Return Line (N9) (capped) nozzle-to-vessel welds and nozzle inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Section XI, Table IWB-2500-1, Appendix VIII, and the Performance Demonstration Initiative (PDI) Program.
Basis For Relief Request:
Pursuant to 10 CFR 50.55a(a)(3)(i) TVA is requesting relief from ASME Section XI requirements to perform the volumetric examinations described above.
TVA proposes to adopt ASME Code Case N-702, Alternate Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1.
This Code Case provides an alternative for BWRs for reduction of the nozzle-to-shell welds and nozzle blend radii examinations from 100 percent to 25 percent of the nozzles each
E2-6 ten-year inspection interval. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
The 25 percent examination frequency, is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The 25 percent sampling level is similar to industry practice and, in some cases, exceeds current practice. For example:
- ASME Code Section XI, IWB-2500 requires 25 percent of Category B-J (Item No. B9.11) circumferential welds to be inspected each inspection interval.
- ASME Code Case N-560, (Risk Informed Inspection) requires inspection of 10 percent of higher risk Class I Category B-J piping welds.
- ASME Code Case N-578, (Risk Informed Inspection) requires inspection of at least 25 percent of the highest risk, (Risk Category 1, 2, and 3) and
- At least 10 percent of the next highest risk, (Risk Category 4 or 5) Class I piping welds.
- ASME Code Section XI, IWC-2500 (Class II piping) Category C-F-1 and C-F-2 requires inspection of 7.5 percent of welds.
- Generic Letter 88-01 requires 25 percent inspection of Category A piping welds.
The 25 percent sampling alternative also provides a significant cost savings and reduces personnel dose exposure. Several utilities have estimated that the proposed reduction of inspection requirements would result in a savings of up to $750,000 per ten-year ISI interval not including exposure considerations. The dose savings at BFN Unit 3 would be approximately 6.5 to 7 REM over a ten-year ISI inspection interval.
E2-7 In the first Unit 3 inspection interval, 30 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination. In the second Unit 3 inspection interval, 24 of the 31 reactor pressure vessel nozzle-to-shell welds and 23 inner radius sections have received a volumetric examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria. One (1) inner radius section received an enhanced visual (EVT-1) examination from the vessel ID. The examination results met ASME Section XI, IWB-3512 acceptance criteria. A summary of these examinations is provided in Attachment C of this enclosure.
TVA considers the above proposed alternative examinations, when considered with the examination history of the BFN RPV nozzles, will provide an acceptable level of quality and safety. The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
Alternate Examination:
In accordance with 10 CFR 50.55a(a)(3)(i),
TVA will adopt ASME Code Case N-702 (See Attachment A of this enclosure) and perform the following alternate examinations:
RPV Nozzle-To-Vessel Welds For the reactor pressure vessel nozzles, Item No. B3.90, TVA will perform volumetric examinations of 25 percent, in lieu of the Code required 100 percent, each ten-year inspection interval. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
RPV Nozzle, Inner Radius Section For the reactor pressure vessel nozzles inner radius section, ASME Section XI Item B3.100, TVA will perform an enhanced remote visual (VT-1) examination of 25 percent of the nozzles, capable of a 1-mil wire resolution in accordance with ASME Section XI, VT-1 requirements. The 25 percent examination coverage refers to 25 percent of the nozzles
E2-8 for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
RPV Head Nozzle, Inner Radius sections For the RPV head nozzle inner radius sections, TVA will perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements. The 25 percent examination coverage refers to 25 percent of the nozzles for each nozzle type and nominal pipe size (e.g., 1 of 4 main steam nozzles would be inspected).
Note: The change from volumetric (UT) to enhanced visual (VT-1) was submitted by requests for relief, 3-ISI-14 and 3-ISI-15, by TVA letter dated May 9, 2003. TVAs request was approved by NRC letter dated February 11, 2004. A request for relief 3-ISI-11 for the RPV Head Nozzles was submitted to NRC by TVA letters dated August 13, 2001, January 9 and February 5, 2002, and approved by NRC letter dated March 13, 2002.
The following nozzles will be examined:
N1 (1 of 2), N2 (3 of 10), N3 (1 of 4), N4 (1 of 2), N6 (1 of 2), N7 (1 of 1), N8 (1 of 1), N9 (1 of 1), and N10 (1 of 1)
(Total of 11 nozzles examined).
All examinations will be performed with personnel, procedures, and equipment qualified in accordance with the ASME Section XI Code, 1995 Edition, 1996 Addenda, Appendix VIII and the Performance Demonstration Initiative (PDI)
Program requirements.
Justification For The Granting Of Relief:
The BFN Unit 3 RPV nozzles were nondestructively examined during fabrication and have previously been examined using inservice ultrasonic techniques specific to the nozzle configuration.
No indication of fabrication defects or service related cracking has been detected by these examinations. See Attachment C of this enclosure for RPV nozzle and inner radius
E2-9 section listing, UT examinations performed, examination coverage, and examination results for the Unit 3 first and second 10-year ISI inspection interval.
In the first Unit 3 inspection interval, 30 of 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
In the second (current) Unit 3 inspection interval, 20 of 31 reactor pressure vessel nozzle-to-shell welds and 19 inner radius sections have received a volumetric examination, the results were acceptable.
One (1) inner radius section received an enhanced visual (EVT-1) examination from the vessel inside diameter in accordance with TVA request for relief 3-ISI-11. The examination results met ASME Section XI, IWB-3512 acceptance criteria.
A significant number of examinations have been performed on units in the BWR fleet that have been operational, for periods up to 30 years, using modern examination techniques capable of detecting significant cracking if it were present. No degradation or failure mechanism has been identified in nozzle-to-vessel or blend radius areas, other than feedwater and CRDM nozzles.
In summary, TVA requests a reduction in RPV nozzle and nozzle inner radius section examinations from 100 percent to 25 percent (of each nozzle type) each 10-year inspection interval. The 25 percent examination frequency is sufficient to identify any aging degradation or failure mechanisms of the BFN RPV nozzles and nozzle inner radius sections. The 25 percent sampling alternative also provides a significant cost savings and reduces personnel dose exposure.
Implementation Schedule:
This request for relief is applicable to the BFN Unit 3, Second Ten-Year ASME Section XI Inservice Inspection Interval, (November 19, 1996 to November 18, 2005).
E2-10 Attachments:
Attachment A - ASME Code Case N-702 Attachment B - (7) sketches)
Sketch SK-B3001, Reactor Pressure Vessel Assembly Sketch SK-B3017, N1, Recirculation Outlet Nozzle Sketch SK-B3018, N2, Recirculation Inlet Nozzles, N3, Main Steam Nozzles, and N5, Core Spray Nozzles Sketch SK-B3016, N6, Reactor Head Spray/Instrumentation Nozzle Sketch SK-B3015, N7, Reactor Head Vent Nozzle Sketch SK-B3019, N8, Jet Pump Instrumentation Nozzle Sketch SK-B3022, N10, Differential pressure and Liquid Volume Control Nozzle Attachment C - Unit 3 RPV Nozzle and Inner Radius Section Examinations
E2-11 Attachment A 3-ISI-18 ASME Code Case N-702
E2-12
E2-13 Attachment B 3-ISI-18 SEVEN (7) Sketches Sketch SK-B3001, Reactor Pressure Vessel Assembly Sketch SK-B3017, N1, Recirculation Outlet Nozzles Sketch SK-B3018, N2, Recirculation Inlet Nozzles, N3, Main Steam Nozzles, and N5, Core Spray Nozzles Sketch SK-B3016, N6, Reactor Head Spray/Instrumentation Nozzles Sketch SK-B3015, N7, Reactor Head Vent Nozzle Sketch SK-B3019, N8, Jet Pump Instrumentation Nozzles Sketch SK-B3022, N10, Differential pressure and Liquid Volume Control Nozzle
E2-14
E2-15 SK-B3001 SK-B3017
E2-16 SK-B3018
E2-17 SK-B3016
E2-18 SK-B3015
E2-19 SK-B3019
E2-20 SK-B3022
E2-21 Attachment C 3-ISI-18 UNIT 3 RPV NOZZLE EXAMINATIONS
SUMMARY
E2-22 REQUEST FOR RELIEF 3-ISI-18 UNIT 3 RPV NOZZLE EXAMINATIONS
SUMMARY
COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N1A 2
8 10/18/79 10/8/98 R-256/R-272 R-205 A
A 25%
72%
N1A-IR 5B 8
11/16/93 10/8/98 R-1172 R-205A A
A 100%
100%
N1B 4
10 12/8/81 3/29/02 R-112, R-149, R-157 R-156 A
A 20%
77%
N1B-IR 5B 10 11/16/93 3/29/02 R-1173 R-157 A
A 100%
100%
N2A 4
10 12/7/81 4/1/02 R-109, R-127, R-152 R-158 A
A 20%
77%
N2A-IR 4
10 12/9/81 4/1/02 R-161 R-159 A
A 100%
100%
N2B 2
8 10/19/79 10/8/98 R-238, R-258, R-265 R-206 A
A 25%
77%
N2B-IR 2
8 1016/79 10/8/98 R-233 R-206A A
A 100%
100%
N2C 4
10 12/7/81 4/1/02 R-111, R-119, R-153 R-160 A
A 20%
77%
N2C-IR 4
10 12/9/81 4/1/02 R-162 R-161 A
A 100%
100%
N2D 2
8 10/16/79 10/8/98 R-235, R-260, R-266 R-207 A
A 25%
77%
N2D-IR 2
8 10/16/79 10/8/98 R-229 R-207A A
A 100%
100%
N2E 4
10 12/7/81 4/1/02 R-110, R-150, R-154 R-162 A
A 20%
77%
N2E-IR 4
10 12/9/81 4/1/02 R-163 R-163 A
A 100%
100%
N2F 2
8 10/19/79 10/8/98 R-237, R-261, R-269 R-208 A
A 25%
77%
N2F-IR 2
8 10/16/79 10/8/98 R-231 R-208A A
A 100%
100%
N2G 4
- 11 12/8/81 R-113, R-148, R-158 A
20%
N2G-IR 4
- 11 12/8/81 R-165 A
100%
N2H 5B
- 11 11/13/93 R-1174 A
42%
N2H-IR 5B
- 11 11/12/93 R-1204 A
100%
E2-23 COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N2J 5B
- 11 11/15/93 R-1175 A
42%
N2J-IR 5B
- 11 11/14/93 R-1205 A
100%
N2K 5B
- 11 11/15/93 R-1176 A
42%
N2K-IR 5B
- 11 11/15/93 R-1206 A
100%
N3A 4
10 11/20/93 3/31/02 R-045, R-047, R-049, R-051, R-052 R-164 A
A 20%
77%
N3A-IR 4
10 11/22/93 3/10/02 R-061 R-165 A
A 100%
100%
N3B 2
8 10/23/79 10/8/98 R-273, R-293, R-253 R-209 A
A 25%
75%
N3B-IR 2
8 10/16/79 10/8/98 R-226 R-209A A
A 100%
100%
N3C 5B
- 11 11/10/93 R-1177 A
28%
N3C-IR 5B
- 11 11/17/93 R-1207 A
100%
N3D 5B
- 11 11/10/93 R-1178 A
28%
N3D-IR 5B
- 11 11/11/93 R-1178 A
100%
N4A 4
10 11/30/81 3/20/02 R-083, R-084, R-085 R-166 A
A 20%
77%
N4A-IR 4
10 11/23/81 3/20/02 R-067 R-167 A
A 100%
100%
N4B 2
8 10/22/79 10/14/98 R-251, R-270, R-281 R-211 A
A 25%
68%
N4B-IR 2
8 10/15/79 10/9/98 R-221 R-211A A
A 100%
100%
N4C 2
8 10/22/79 10/14/98 R-250, R-268, R-282 R-212 A
A 25%
68%
N4C-IR 2
8 10/16/79 10/9/98 R-232 R-212A A
A 100%
100%
N4D 5B 11 11/16/93 3/08/04 R-1182 R-182 A
A 44%
94.37%
N4D-IR 5B 11 11/9/93 3/12/04 R-1208 R-184 A
A 100%
100%
N4E 5B 11 11/16/93 3/08/04 R-1183 R-183 A
A 43%
94.37%
N4E-IR 5B 11 11/12/93 3/12/04 R-1209 R-185 A
A 100%
100%
E2-24 COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N4F 4
10 11/20/81 3/20/02 R-054, R-057, R-068 R-168 A
A 20%
77%
N4F-IR 4
10 11/23/81 3/20/02 R-068 R-169 A
A 100%
100%
N5A 2
8 10/22/79 10/8/98 R-249, R-267, R-284 R-216 A
A 20%
64%
N5A-IR 2
8 10/16/79 10/8/98 R-228 R-216A A
A 75%
100%
N5B 4
10 12/3/81 4/2/02 R-093, R-101, R-105 R-170 A
A 20%
71%
N5B-IR 4
10 11/24/81 3/31/02 R-081 R-171 A
A 83%
100%
N6A 5B 7
8/1795 9/27/91 3/1/97 R-591, R-591A R-247 A
A 100%
100%
N6A-IR 5B 7
9/28/91 3/1/97 R-598 R-243 A
A 100%
100%
N6B 5B 11 8/1795 9/27/91 3/06/04 R-592, R-592A R-186 A
A 100%
93.12%
N6B-IR 5B 11 9/28/91 3/07/04 R-597 R-093 A
A 100%
100%
N7 5B 10 8/1795 9/27/91 3/29/02 R-590, R-590A R-125 A
A 100%
70%
N7-IR 5B 10 9/28/91 3/30/02 R-599 R-115 A
A 100%
100%
N8A 2
8 10/19/79 10/9/98 R-247, R-259, R-271 R-217 A
A 68%
71%
N8A-IR 2
8 10/16/79 10/9/98 R-230 R-217A A
A 100%
100%
N8B 5B
- 11 11/6/93 R-1185 A
68%
N8B-IR 5B
- 11 11/7/93 R-1185 A
100%
N9 4
10 12/3/81 4/1/02 R-092, R-103, R-099 R-172 A
A 25%
74%
N9-IR 4
10 1124/81 4/1/02 R-079 R-173 A
A 100%
100%
N10 11 3/04/04 R-187 A
97.31%
N10-IR 11 3/04/04 R-188 A
90%
- Scheduled for examination in Unit 3 Cycle 11 (Spring 2004) Refueling Outage, but deferred to Unit 3 Cycle 12 (Spring 2006) Refueling Outage.
Note: In results column, A refers to acceptable per ASME Section XI, Subarticle IWB-3512 acceptance criteria.