ML032190543
| ML032190543 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/25/2003 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032190543 (51) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 25, 2003 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 In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from certain inservice inspection (ISI) requirements in Section XI of the ASME Section XI Code, for the volumetric examination of Class 1, reactor pressure vessel (RPV) nozzle-to-vessel welds and nozzle inner radius sections.
The enclosure to this letter contains BFN Units 2 and 3 requests for relief 2-ISI-22, and 3-ISI-18 for NRC review and approval.
The justification for TVA's requests for relief is the technical basis described in the Boiling Water Reactor Vessel Internals Project (BWRVIP) technical report 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."
The BWRVIP-108 report concludes that nondestructive examination frequency for RPV nozzle-to-shell welds and nozzle blend radii may be reduced
%4D17 Printed on recyded paper
U.S. Nuclear Regulatory Commission Page 2 July 25, 2003 from 100 percent each 10-year inspection interval to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles, each 10-year interval).
It should be noted that the term "blend radiin is a generic term used in the BWRVIP-108 report which is synonymous with the RPV nozzle "inner radius."
The 25 percent examination sampling size was selected by the BWRVIP and justified by a probabilistic fracture mechanics evaluation (Section 5 of BWRVIP-108) considering the following criteria:
(1) sample size large enough to effectively identify aging degradation, (2) sample size consistent with current industry requirements, and (3) examination sampling size reduction sufficient to result in significant cost savings and radiological dose reduction. of this letter contains BFN Unit 2 request for relief 2-ISI-22 for NRC review and approval.
BFN Unit 3 request for relief 3-ISI-18 is provided in Enclosure 2.
TVA requests approval of these requests for relief by January 16, 2004, to support resource planning for the Unit 3, Cycle 11 (Spring 2004) refueling outage.
There are no new regulatory commitments in this letter.
If you have any questions, please contact me at (256) 729-2636.
Sipcerely,
U.S. Nuclear Regulatory Commission Page 3 July 25, 2003 Enclosures cc (Enclosures):
(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 Mr. Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
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 (See Attached)
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 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 inner radius sections.
The examination requirement is for a volumetric examination of 100 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, and Item No.
B3.100, "Reactor Vessel Nozzle Inner Radius Section" each 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 nozzles.
The six feedwater nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Code,Section XI, Appendix VIII and the Performance Demonstration Initiative (PDI) Program.
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii from 100 percent to 25 percent of the nozzles each 10-year interval.
E1-2
The 25 percent coverage refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
TVA is also proposing an alternate examination for the nozzle blend radii (i.e.,
inner radius).
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-i requirements.
This 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 letters dated April 23, and September 5, 2002, and approved by NRC letter dated October 7, 2002.
TVA is requesting that the reduction from 100 percent to 25 percent of the nozzles each 10-year inspection interval in this request for relief apply to the above aforementioned requests for relief, for the enhanced remote or direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-i requirements.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety.
The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
The 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.
Unit:
Two (2)
ISI Interval:
ASME Section XI, Third Ten-Year ISI Interval (May 25, 2001 to May 24, 2011)
E1-3
System(s)
Components:
Reactor Pressure Vessel (RPV), Nozzle-to-Vessel Welds and RPV Nozzle Inner Radius Sections:
Reactor Recirculation Outlet Nozzles, NMA and NlB (Total of 2 nozzles)
Reactor Recirculation Inlet Nozzles, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, and N2K (Total of 10 nozzles)
Main Steam Nozzles, N3A, N3B, N3C, and N3D (Total of 4 nozzles)
Core Spray Nozzles, N5A and N5B (Total of 2 nozzles)
Reactor Pressure Vessel(RPV)Head Nozzles, N6A, N6B, and N7 (Total of 3 nozzles)
Jet Pump Instrumentation Nozzles, N8A and N8B (Total of 2 nozzles)
Control Rod Drive Return Line Nozzle, (capped) N9 (Total of 1 nozzle)
Standby Liquid Control Nozzle, N10 (Total of 1 nozzle)
ASME Code Class:
ASME Section XI Code Edition:
Code Table:
Examination Category:
Examination Item Number(s):
Code Requirement:
ASME Code Class 1 1995 Edition, 1996 Addenda IWB-2500-1 B-D, "Full Penetration Welded Nozzles In Vessels" B3.90, "Nozzle-To-Vessel Welds", and B3.100, "Nozzle Inner Radius Sections,"
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 section each inspection interval.
E1-4
Code Requirements From Which Relief Is Requested:
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 each inspection interval of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section.
Relief is requested from the requirement to perform a volumetric examination of 100 percent of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section each inspection interval.
List Of Items Associated With The Relief Request:
Reactor Pressure Vessel Nozzles, NlA, NlB, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N5A, N5B, N6A, N6B, N7, N8A, N8B, N9 (capped), and N10 (Total of 25 nozzles)
Note:
The six feedwater nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Code,Section XI, 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 examination described above.
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii from 100 percent to 25 percent of the nozzles each 10-year inspection interval.
The 25 percent coverage El-5
refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
This report was submitted by the Boiling Water Reactor Vessel Internals Project (BWRVIP) Committee to the NRC by letter dated November 25, 2002.
As stated in the above report, the 25 percent inspection sampling level was selected, in part, because it was considered to be sufficient to effectively identify aging degradation in the nozzle-to-shell welds and nozzle blend radii.
It is consistent with current industry and regulatory sampling practice, and there is significant dose reduction and cost savings.
The determination of whether the 25 percent inspection sampling is sufficient is the object of the Probabilistic Failure Mechanics (PFM) evaluation.
The PFM evaluation shows very low probability of failure, and the 25 percent inspection sampling is considered sufficient to identify aging degradation.
The 25 percent sampling level is similar to industry practice and, in some cases, exceeds current practice.
For example:
- The ASME Code Section XI, IWB-2500 requires 25 percent of Category B-J (Item No. B9.11) circumferential welds be inspected each inspection interval.
- The ASME Code Case N-560, (Risk Informed Inspection) requires inspection of 10 percent of higher risk Class I Category B-J piping welds.
- The 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.
E1-6
- The 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 also 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 10-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 interval.
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-i) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles 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 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 letters April 23, and September 5, 2002, and approved by NRC letter dated October 7, 2002.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety.
The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
In the first Unit 2 inspection interval 30 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination.
In the second Unit 2 inspection interval, 31 of the 31 reactor pressure vessel nozzle-to-shell welds and 30 inner radius sections received a volumetric examination.
The results were acceptable.
In the third Unit 2 inspection interval, E1-7
6 of the 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections have received a volumetric examination.
The examination results were all acceptable.
Also, in the third Unit 2 inspection interval, seven (7) of the 31 reactor pressure vessel nozzle-to-shell welds received a volumetric examination.
The inner radius sections of these nozzles received an enhanced visual (EVT-1) examination from the vessel ID.
The examination results were acceptable.
Alternate Examination:
In accordance with 10 CFR 50.55a(a)(3)(i) TVA will perform the following alternate examinations:
TVA will perform the following.
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii from 100 percent to 25 percent of the nozzles each 10-year inspection interval.
The 25 percent coverage refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements.
This was submitted as two separate requests for relief, 2-ISI-16 and 2-ISI-17 to NRC by letters dated April 23, and September 5, 2002, and approved by NRC letter dated October 07, 2002.
El-8
In summary, TVA's proposed alternative examinations are as follows.
Perform examination of 25 percent each inspection interval in lieu of 100 percent, of the ASME Section XI, Examination Category B-D, "Full Penetration Welded Nozzles in Vessels,"f Item No. B3.90, "Reactor Vessel Nozzle to Vessel Welds and an enhanced remote or direct visual (VT-1) examination capable of a 1-mil wire resolution in accordance with ASME Section XI, VT-l of Item No. B3.100, "Reactor Vessel Nozzle Inner Radius Section."
(Reference request for relief 2-ISI-16 and 2-ISI-17)
The following nozzles will be examined:
N1 (1), N2 (3), N3 (1), N5 (1), N6 (1), N7 (1),
N8 (1), N9 (1), and N10 (1) (Total of 11 nozzles in ten years).
The 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 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 B for RPV nozzle and inner radius section listing and UT examinations and coverage for Unit 2 first, second, and third ISI inspection interval.
In the first Unit 2 inspection interval 30 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination.
In the second Unit 2 inspection interval, 31 of 31 reactor pressure vessel nozzle-to-shell welds and 30 inner radius sections received a volumetric examination.
The examination results were acceptable.
El-9
In the third Unit 2 inspection interval, 6 of the 31 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination.
The results of all examinations were acceptable.
Also, in the third Unit 2 inspection interval Seven (7) of the 31 reactor pressure vessel nozzle-to-shell welds received a volumetric examination.
The inner radius sections of these nozzles received an enhanced visual (EVT-1) examination from the vessel ID.
The examination results were acceptable.
As presented in the BWRVIP-108 report, 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.
An evaluation of reactor pressure vessel reliability was performed.
The nozzles considered were the core spray, main steam, recirculation inlet, and outlet nozzles.
The analyses were performed using the worst weld chemistry from the BWR vessel fleet.
Stresses were conservatively selected.
Any cracks were assumed to occur at the highest stressed locations around the nozzle.
Both stress corrosion and fatigue crack growth were included in the evaluation.
In summary, based on the selection criteria used in the BWRVIP-108 report, TVA has concluded that the RPV nozzles considered in the BWRVIP-108 analysis are representative of the BFN Units 2 and 3 RPV nozzles.
- Further, based on the conservatisms used in the analysis:
(1) poor water chemistry, (2) stresses selected from limiting azimuth in the nozzle, (3) cracks assumed to occur at the highest stressed locations around the nozzle azimuth and (4) both stress corrosion and fatigue crack growth were included in the evaluation, TVA has determined that the conclusions reached in the BWRVIP-108 report apply to the BFN Units 2 and 3 RPV nozzles.
Therefore, TVA requests a reduction in RPV nozzle and nozzle inner radius section El-10
examinations from 100 percent to 25 percent (of each nozzle type) each 10-year inspection interval.
The 25 percent examination frequency, as stated in the BWRVIP-108 report, is sufficient to identify any aging degradation of the nozzles.
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 -
(8 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-B2020, N9, Control Rod Drive Return Line Nozzle (capped)
Sketch SK-B2022, N10, Differential pressure and Liquid Volume Control Nozzle Attachment B -
Unit 2 RPV Nozzle and Inner Radius Section Examinations El-11
Attachment A 2-ISI-22 EIGHT (8)
Sketches Sketch SK-B2001, Vessel Assembly Sketch SK-B2017, Outlet Nozzles Reactor Pressure N1, Recirculation Sketch SK-B2018, N2, Recirculation Inlet Nozzles, N3, Main Steam Nozzles, and N5, Core Spray Nozzles Sketch SK-B2016, N6, Reactor Read Spray/Instrumentation Nozzle Sketch SK-B2015, N7, Reactor Head Vent Nozzle Sketch SK-B2019, N8, Jet Pump Instrumentation Nozzle Sketch SK-B2020, N9, Control Rod Drive Return Line Nozzle (capped)
Sketch SK-B2022, N10, Differential pressure and Liquid Volume Control Nozzle E1-12
SK-B2 001 E1-13
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Attachment B
2-ISI-22 UNIT 2 RPV NOZZLE EXAMINATIONS
SUMMARY
E1-21
REQUEST FOR RELIEF 2-ISI-22 UNIT 2 RPV NOZZLE EXAMINATIONS
SUMMARY
COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE
=__
_ _ _ _ _ _ _ _ _ _* Note 1 NIA 3
7 9/24180 10/11/94 R-065, R-067, R-1001 A
A
- Note 1 60%
R-070 NIA-IR SB 7
7/20/90 10/6/94 R-1400 R-1002 A
A
- Note 1 100%
NIB 4
9 9/28/82 10/15/97 R-181, R-178, R-207 A
A
- Note 1 72%
R-195 NIB-IR SB 9
7/20/90 11/3/97 R-1399 R-207A A
A
- Note 1 100%
- Note 1 4
9 9/28/82 10/15/97 R-171, R-183, R-208 A
A
- Note 1 77%
R-199 N2A N2A-IR 4
9 9/28/82 11/21/97 R-202 R-208A A
A
- Note 1 100%
N2B 1/3 7
5117178 10/23/94 R-048, R-063 R-1021 A
A
- Note 1 52%
9/23/80 N2B-IR 1
7 5120/78 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-209 A
A
- Note 1 77%
R-196 N2C-lR 4
9 9/28/82 11/21/97 R-200 R-209A A
A
- Note 1 100%
N2D SB 11 9/20/86 416/01 R-137, R-829, R-126 A
A
- Note 1 67%
10/22/87 R-832 N2D-IR SB 11 9/25/86 4/6/01 R-193 R-126A A
A
- Note 1 100%
N2E SB 11 9/20/86 4/7/01 R-136, R-828, R-127 A
A
- Note 1 67%
10/22/87 R-833 N2E-IR SB 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-1023 A
A
- Note 1 55%
R-013 N2F-IR 4A 7
6n/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-210 A
A
- Note 1 77%
R-198 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-211 A
A
- Note 1 77%
R-197 N2H-IR 4
9 9/29/82 11/21/97 R-207 R-1IA A
A
- Note 1 100%
N2J 4A 7
6/6/81 10/22/94 R-007, R-014, R-1025 A
A
- Note 1 55%
R-015 N2J-IR 4A 7
6/7/81 10/6/94 R-019 R-1026 A
A
- Note 1 100%
N2K SB 11 9/16/86 10/7/01 R-138, R-830, R-128 A
A
- Note 1 67%
10/22/87 R-834 N2K-IR SB 11 9/25/86 10/7/01 R-194 R-128A A
A
- Note I 100%
N3A SB 11 9/27/86 3/31/01 R-198, R-201, R-129 A
A
- Note 1 61%
10/21/87 R-893 N3A-IR 5B 11 9/28186 3/31/01 R-255 R-129A A
A
- Note I 100%
N3B 4
9 9/26/82 10/15/97 R-067, R-074, R-212 A
A
- Note 1 75%
R-075 N3B-IR 4
9 9/21/82 11/21/97 R-142 R-212A A
A
- Note 1 100%
E1-22
COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N3C SB 11 9/27/86 3/31/01 R-196, R-199, R-130 A
A
- Note 1 61%
12/21/86 R-892 N3C-IR SB 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 5/20178 10/6/94 R-045 R-1004 A
A
- Note 1 100%
N4A 3
7 10/9/80 1017/94 R-107, R-109, R-1009 A
A
- Note 1 59%
R-122 N4A-IR 3
7 1017/80 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, R0213 A
A
- Note 1 67%
R-094 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-214 A
A
- Note 1 67%
R-095, R-103 N4C-IR 4
9 9/21/82 11/21/97 R-141 R-214A A
A
- Note 1 100%
N4D SB 11 9/20/86 4/5/01 R-128, R-134, R-131 A
A
- Note 1 69%
12/22/87 R-897 N4D-IR SB 11 9/25/86 4/5/01 R-190 R-131A A
A
- Note 1 100%
N4E SB 11 9/20/86 4/5/01 R-126, R-133, R-132 A
A
- Note 1 69%
10/22/87 R-895 N4E-IR SB 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-1005 A
A
- Note 1 54%
R-121 N4F-IR 3
7 10/7/80 10/17/94 R-104, R-008, R-1007 A
A
- Note I 100%
R-010, R-012 NSA 1/4A 7
5/19/78 10/21/94 R-051 R-1027 A
A
- Note 1 53%
6/6/81 NSA-IR 3
7 10/8/80 10/20/94 R-114 R-1028 A
A
- Note 1 100%
NSB 4
9 9/24/82 10/15/97 R-089, R-105, R-215 A
A
- Note 1 65%
R-106 NSB-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-064 A
A
- Note 1 100%
R-052 N6A-IR 3/SB 6
10/3/80 2/13/93 R-087, R-063 A
A
- Note 1 100%
11/4/88 R-1111 N6B SB 10 11/16/87 4/25/90 R-859, R-862, R-353 A
A
- Note 1 100%
R-865 N6B-IR SB 10 11/4/88 4/25/90 R-1110 R-331 A
A
- Note 1 100%
N7 SB 10 11/16/87 4/23/90 R-854, R-857, R-352 A
A
- Note 1 100%
R-860 N7-lR SB 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-1008 A
A
- Note 1 68%
R-069 N8A-IR 3
7 10/6/80 10/18/94 R-101 R-1011 A
A
- Note 1 73%
N8B SB 11 9/20/86 4/3/01 R-139, R-831, R-133 A
A
- Note 1 72%
11/16/87 R-835 N8B-IR SB 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-216 A
A
- Note 1 75%
R-161 N9-IR 4
9 9/21/82 11/21/97 R-139 R-216A A
A
- Note 1 100%
NIO 11 4/3/01 R-134 A
56%
E1-23
UNIT 2 RPV NOZZLE EXAMINATIONS THIRD INTERVAL, FIRST PERIOD ONLY COMPONENT CYCLE DATE REPORT#
RESULTS COVERAGE NIA 12 3/4/03 R-160 A
48.8%
NlA-IR 12 3/7/03 R-169 A
100%
N2B 12 3/3/03 R-161 A
51.5%
N2B-IR 12 3/1703 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 12 3/3/03 R-163 A
51.5%
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 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.
E1-24
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 (See Attached)
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 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 inner radius sections.
The examination requirement is for a volumetric examination of 100 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 and Item No.
B3.100, "Reactor Vessel Nozzle Inner Radius Section" each 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 nozzles.
The six feedwater nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Code,Section XI, Appendix VIII and the Performance Demonstration Initiative (PDI) Program.
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii from 100 percent to 25 percent of the nozzles each 10-year E2-2
inspection interval.
The 25 percent coverage refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
TVA is also proposing an alternate examination of the nozzle blend radii (i.e.,
inner radius).
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles perform an enhanced direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-l requirements.
The change from volumetric (UT) to enhanced visual (VT-1) has been submitted as two separate requests for relief, 3-ISI-14 and 3-ISI-15, by TVA letter dated May 9, 2003, and is pending NRC approval.
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, also applies.
TVA is requesting that the reduction from 100 percent to 25 percent of the nozzles every 10-year inspection interval in this request for relief apply to the above aforementioned requests for relief, for the enhanced remote or direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety.
The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
The 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.
E2-3
Unit:
Three (3)
ISI Interval:
System(s):
Components:
ASME Section XI, Second Ten-Year ISI Interval (November 19, 1996 to November 18, 2005)
Reactor Pressure Vessel (RPV), Nozzle-to-Shell Welds and Inner Radius Sections:
Reactor Recirculation Outlet Nozzles, NlA and NlB (Total of 2 nozzles)
Reactor Recirculation Inlet Nozzles, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, and N2K (Total of 10 nozzles)
Main Steam Nozzles, N3A, N3B, N3C, and N3D (Total of 4 nozzles)
Core Spray Nozzles, N5A and N5B (Total of 2 nozzles)
Reactor Pressure Vessel(RPV)Head Nozzles, N6A, N6B, and N7 (Total of 3 nozzles)
Jet Pump Instrumentation Nozzles, N8A and N8B (Total of 2 nozzles)
Control Rod Drive Return Line Nozzle, (capped) N9 (Total of 1 nozzle)
Standby Liquid Control Nozzle, N10 (Total of 1 nozzle)
ASME Code Class:
ASME Section XI Code Edition:
ASME Code Class 1 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.
However, TVA has adopted the 1995 Edition with the 1996 addenda (all TVA nuclear sites) for performance of nondestructive examinations.
Code Table:
Examination Category:
IWB-2500-1 B-D, "Full Penetration Welded Nozzles In Vessels" E2-4
Examination Item Number(s):
Code Requirement:
Code Requirements From Which Relief Is Requested:
B3.90, "Nozzle-To-Vessel Welds", and B3.100, "Nozzle Inner Radius Sections,"
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 section each inspection interval.
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 each inspection interval of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section.
Relief is requested from the requirement to perform a volumetric examination of 100 percent of the reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius section each inspection interval.
List Of Items Associated With The Relief Request:
Reactor Pressure Vessel Nozzles, NlA, NlB, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N5A, N5B, N6A, N6B, N7, N8A, N8B, N9 (capped), and N10 (Total of 25 nozzles)
Note:
The six feedwater nozzle-to-vessel welds and inner radius sections will continue to be examined with ultrasonic examination (UT) techniques in accordance with ASME Code,Section XI, 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 alternate examination described above.
E2-5
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii (i.e., inner radius section) from 100 percent to 25 percent of the nozzles each 10-year inspection interval.
The 25 percent coverage refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
This report was submitted by the Boiling Water Reactor Vessel Internals Project (BWRVIP) Committee to the NRC by letter dated November 25, 2002, for staff review.
As stated in the above report, the 25 percent inspection sampling level was selected, in part, because it was considered to be sufficient to effectively identify aging degradation in the nozzle-to-shell welds and nozzle blend radii.
It is consistent with current industry and regulatory sampling practice, and there is significant dose reduction and examination cost savings.
The determination of whether the 25 percent inspection sampling is sufficient is the object of the Probabilistic Failure Mechanics (PFM) evaluation.
The PFM evaluation shows very low probability of failure, and the 25 percent inspection sampling is considered sufficient to identify aging degradation.
The 25 percent sampling level is similar to industry practice and, in some cases, exceeds current practice.
For example:
B9.11) circumferential welds be inspected each inspection interval.
E2-6
- 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 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 10-year interval not including exposure considerations.
The dose savings at BFN Unit 3 would be approximately 6.5 to 7 REM over a ten-year interval.
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles 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 change from volumetric (UT) to enhanced visual (VT-1) has been submitted as two separate requests for relief, 3-ISI-14 and 3-ISI-15, by TVA letter dated May 9, 2003, and is pending NRC approval.
A request for relief 3-ISI-11 for the RPV Head Nozzles, submitted to NRC by TVA letters dated August 13, 2001, January 9 and February 5, 2002, and approved by NRC letter E2-7
dated March 13, 2002, also applies.
TVA is requesting that the reduction from 100 percent to 25 percent of the nozzles each 10-year inspection interval in this request for relief will apply to the above aforementioned requests for relief, for the enhanced remote or direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1 requirements.
TVA considers the above proposed alternative examinations will provide an acceptable level of quality and safety.
The proposed alternatives will also provide a significant savings in examination resources and radiation exposure.
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, 20 of the 31 reactor pressure vessel nozzle-to-shell welds and 19 inner radius sections have received a volumetric examination.
The examination results were acceptable.
One (1) inner radius section received an enhanced visual (EVT-1) examination from the vessel ID.
The examination results were acceptable.
Alternate Examination:
In accordance with 10 CFR 50.55a(a)(3)(i) TVA will perform the following alternate examinations:
TVA proposes to utilize the technical basis contained in the Boiling Water Reactor Vessel Internals Project (BWRVIP) Report, 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."
This report provides the technical basis for the reduction of the nozzle-to-shell welds and nozzle blend radii from 100 percent to 25 percent of the nozzles each 10-year inspection interval.
The 25 percent coverage E2-8
refers to 25 percent of the nozzles for each nozzle type (e.g., 1 of 4 main steam nozzles would be inspected).
For the reactor pressure vessel nozzles inner radius section, TVA will perform an enhanced remote visual (VT-1) examination, capable of a 1-mil wire resolution, and on the RPV head nozzles 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 change from volumetric (UT) to enhanced visual (VT-1) has been submitted as two separate requests for relief, 3-ISI-14 and 3-ISI-15, by TVA letter dated May 9, 2003, and is pending NRC approval.
A request for relief 3-ISI-l1 for the RPV Head Nozzles 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, also applies.
TVA is requesting that the reduction from 100 percent to 25 percent of the nozzles each 10-year inspection interval in this request for relief will apply to the above aforementioned requests for relief, for the enhanced remote or direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-i examination requirements.
In summary, TVA's proposed alternative examinations are as follows.
Perform volumetric examination of 25 percent each inspection interval in lieu of 100 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 and an enhanced remote or direct visual (VT-1) examination, capable of a 1-mil wire resolution, in accordance with ASME Section XI, VT-1, of Item No.
B3.100, "Reactor Vessel Nozzle Inner Radius Section."
(Reference request for relief 3-ISI-14 and 3-ISI-15)
The following nozzles will be examined:
N1 (1), N2 (3), N3 (1), N5 (1), N6 (1), N7 (1),
N8 (1), N9 (1), and N10 (1) (Total of 11 nozzles in ten years).
E2-9
The 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 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 B for RPV nozzle and inner radius section listing and UT examinations and coverage for the Unit 3 first and second 10-year ISI inspection interval.
In the first Unit 3 inspection interval, 30 reactor pressure vessel nozzle-to-shell welds and inner radius sections received a volumetric examination.
The examination results were acceptable.
In the second 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 ID.
The results were acceptable.
(Reference request for relief 3-ISI-ll)
As presented in the BWRVIP-108 report, 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.
An evaluation of reactor pressure vessel reliability was performed.
The nozzles considered were the core spray, main steam, recirculation inlet and outlet E2-10
nozzles.
The analyses were performed using the worst weld chemistry from the BWR vessel fleet.
Stresses were conservatively selected.
Any cracks were assumed to occur at the highest stressed locations around the nozzle.
Both stress corrosion and fatigue crack growth were included in the evaluation.
In summary, based on the selection criteria used in the BWRVIP-108 report, TVA has concluded that the RPV nozzles considered in the BWRVIP-108 analysis are representative of the BFN Units 2 and 3 RPV nozzles.
- Further, based on the conservatisms used in the analysis:
(1) poor water chemistry, (2) stresses selected from limiting azimuth in the nozzle, (3) cracks assumed to occur at the highest stressed locations around the nozzle azimuth and (4) both stress corrosion and fatigue crack growth were included in the evaluation, TVA has determined that the conclusions reached in the BWRVIP-108 report apply to the BFN Units 2 and 3 RPV nozzles.
Therefore, 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, as stated in the BWRVIP-108 report, is sufficient to identify any aging degradation of the nozzles.
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).
Attachments:
Attachment A -
(8 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 E2-11
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-B3020, N9, Control Rod Drive Return Line Nozzle (capped)
Sketch SK-B3022, N10, Differential pressure and Liquid Volume Control Nozzle Attachment B Unit 3 RPV Nozzle and Inner Radius Section Examinations E2-12
Attachment A 3-ISI-18 EIGHT (8)
Sketches Sketch SK-B3001, Vessel Assembly Sketch SK-B3017, Outlet Nozzles Reactor Pressure N1, Recirculation 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-B3020, N9, Control Rod Drive Return Line Nozzle (capped)
Sketch SK-B3022, N10, Differential pressure and Liquid Volume Control Nozzle E2-13
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Attachment B 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 10118n9 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%
NIB 4
10 12/8181 3/29102 R-112, R-149, R-156 A
A 20%
77%
R-157 NIB-IR 5B 10 11/16/93 3f29/02 R-1173 R-157 A
A 100%
100%
N2A 4
10 12/7/81 4/1/02 R-109,R-127, R-158 A
A 20%
77%
R-152 N2A-IR 4
10 12/9/81 4/1/02 R-161 R-1S9 A
A 100%
100%
N2B 2
8 10/9in9 10/8/98 R-238, R-258, R-206 A
A 25%
77%
R-265 N2B-IR 2
8 101619 10/8/98 R-233 R-206A A
A 100%
100%
N2C 4
10 12n181 4/1/02 R-11,R-119, R-160 A
A 20%
77%
R-153 N2C-IR 4
10 12/9/81 4/1/02 R-162 R-161 A
A 100%
100%
N2D 2
8 10/16n9 10/8/98 R-235, R-260, R-207 A
A 25%
77%
R-266 N2D-IR 2
8 10116n9 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-162 A
A 20%
77%
R-154 N2E-IR 4
10 12/9/81 4/1/02 R-163 R-163 A
A 100%
100%
N2F 2
8 10/1919 10/8/98 R-237, R-261, R-208 A
A 25%
77%
R-269 N2F-IR 2
8 10/16n9 10/8/98 R-231 R-208A A
A 100%
100%
N2G 4
- 11 12/8/81 R-113, R-148, A
20%
R-158 N2G-IR 4
- 11 1218/81 R-165 A
100%
N2H SB
- 11 11/13/93 R-1174 A
42%
N2H-IR 5B
- 11 11/12/93 R-1204 A
100%
N2J 5B
- 11 11/15/93 R-1175 A
42%
N2J-IR 5B
- 11 11/14/93 R-1205 A
100%
N2K SB
_*11 11/15/93 R-1176 A
42%
N2K-lR 5B
- 11 11/1S/93 R-1206 A
100%
N3A 4
10 11/20/93 3/31/02 R-045, R-047, R-164 A
A 20%
77%
R-049, R-05 1,
.R-052 N3A-IR 4
10 11/22/93 3/10/02 R-061 R-165 A
A 100%
100%
N3B 2
8 10123n9 10/8/98 R-273, R-293, R-209 A
A 25%
75%
R-253 N3B-IR 2
8 10/16n9 10/8/98 R-226 R-209A A
A 100%
100%
N3C 5B
- 11 11/10/93 R-1177 A
28%
- 11 11/17/93 R-1207 A
100%
N3D 5B
- 11 11/10/93 R-1178 A
28%
- 11 11/11/93 R-1178 A
100%
E2-23
COMPONENT CYCLE DATE REPORT #
RESULTS COVERAGE N4A 4
10 11/30/81 3/20/02 R-083, R-084, R-166 A
A 20%
77%
R-085 N4A-IR 4
10 11/23/81 3/20/02 R-067 R-167 A
A 100%
100%
N4B 2
8 10122/79 10/14/98 R-251, R-270, R-211 A
A 25%
68%
R-281 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-212 A
A 25%
68%
R-282 N4C-IR 2
8 10/16/79 10/9/98 R-232 R-212A A
A 100%
100%
N4D SB
- 11 11/16/93 R-1182 A
44%
- 11 11/9/93 R-1208 A
100%
N4E SB
- 11 11/16/93 R-1183 A
43%
- 11 11/12/93 R-1209 A
100%
N4F 4
10 11/20/81 3/20/02 R-054, R-057, R-168 A
A 20%
77%
R-068 N4F-IR 4
10 11/23/81 3/20/02 R-068 R-169 A
A 100%
100%
NSA 2
8 10/22/79 10/8/98 R-249, R-267, R-216 A
A 20%
64%
R-284 NSA-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-170 A
A 20%
71%
R-10S NSB-IR 4
10 11/24/81 3/31/02 R-081 R-171 A
A 83%
100%
N6A SB 7
8/1795 3/1/97 R-591, R-591A R-247 A
A 100%
100%
9/28/91 3/1/97 R-598 R-243 A
A 100%
100%
N6B SB
- 11 8/1795 R-592, R-592A A
100%
- 11 9/28/91 R-597 A
100%
N7 SB 10 8/1795 3/29/02 R-590, R-590A R-125 A
A 100%
70%
9/27/91 N7-lR SB 10 9/28/91 3/30/02 R-599 R-11S A
A 100%
100%
N8A 2
8 10/19/n 10/9/98 R-247, R-259, R-217 A
A 68%
71%
R-271__
N8A-IR 2
8 10/16/79 10/9/98 R-230 R-217A A
A 100%
100%
N8B SB
- 11 11/6/93 R-1185 A
68%
- 11 ll/7/93 R-1185 A
100%
N9 4
10 12/3/81 4/1/02 R-092, R-103, R-172 A
A 25%
74%
N;O____________
4____
- 11 1124/81__
4//2R-079 R-9173_AA 100%_
100 N9-IR 4
10 1124/81 4/1/02 R-079 R-173 A
A 100%
100%0/
N 10
- 11 I__
I__
- Note: Scheduled for examination in Unit 3 Cycle 11 Refueling Outage.
E2-24