RS-14-038, Relief Request 14R-20, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval
| ML14023A865 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/23/2014 |
| From: | Simpson P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-14-038 | |
| Download: ML14023A865 (15) | |
Text
4300 Winfield Road Warrenville, iL 60555 Exelon Generation.. 630 657 2000 Office RS-14-038 10 CFR 50.55a January 23, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR -29 and DPR-30 NRC Docket Nos. 50 -254 and 50-265
Subject:
Relief Request 14R- 20, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC (EGC), requests NRC approval of the attached relief request associated with the fourth inservice inspection (ISI) interval for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. Relief is requested due to the impracticality of satisfying the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
due to plant design. The fourth ISI interval for QCNPS ended April 8, 2013.
The relief request is based on the limitations that precluded completion of full Code examination requirements of ASME Class 1 components during the fourth interval. Code examination of the components was limited due to the materials of construction and design configurations. The QCNPS fourth ten-year ISI program plan was developed in accordance with ASME Code,Section XI, 1995 Edition through 1996 Addenda.
EGC requests approval of the proposed relief request by January 23, 2015. There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.
Attachment:
10 CFR 50.55a Relief Request 14R-20 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 1 of 14)
Request for Relief for Inservice Inspection Impracticality Due to the Limited Examination Coverage In Accordance with 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality
- 1. ASME Code Component(s) Affected:
Code Class: 1
Reference:
IWB-2500, Table IWB-2500-1, IWF-2500, Table IWF-2500-1, ASME Code Case N-460 ASME Code Case N-578-1, Table 1 Examination Category: B-A, B-D, F-A, R-A Item Number: B1.12, B1.40, B1.51, B3.90, F1.40, R1.20
Description:
Limited examination coverage Component Number: See Tables I4R-20.1 and I4R-20.2 below for specific component identification
2. Applicable Code Edition and Addenda
The Inservice Inspection (ISI) Program for the Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, fourth ISI interval was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 1995 Edition through 1996 Addenda.
3. Applicable Code Requirement
Table IWB-2500-1 and Table 1 of Code Case N-578-1 Examination Categories/Item Numbers B-A, B1.12, B1.40, B1.51; B-D, B3.90; and R-A, R1.20 require a volumetric and/or surface examination, which includes essentially 100% of the weld. QCNPS Units 1 and 2 adopted ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1," which defines "essentially 100%" as greater than 90% coverage of the examination volume or surface area, as applicable.
Table IWF-2500-1, Examination Category F-A, Item Number F1.40 requires a VT-3 visual examination of these supports. Footnote 3 of Table IWF-2500-1 indicates that at least one component be examined for multiples of similar components, within a system of similar design, function, and service. There is no equivalent component to the reactor vessel skirt; therefore, this component is required to be examined. The VT-3 visual examination is in accordance with the boundaries shown in Figure IWF-1300-1.
- 4. Impracticality of Compliance:
Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii), on the basis that conformance with these Code requirements is impractical. Conformance would require extensive structural modifications to the component or surrounding structure.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 2 of 14)
QCNPS, Units 1 and 2, obtained Construction Permits CPPR-23 and CPPR-24, respectively, on February 15, 1967. The piping systems and associated components were designed and fabricated before the examination requirements of ASME Section XI were formalized and published. Since QCNPS, Units 1 and 2, were not specifically designed to meet the requirements of ASME Section XI, full compliance is not feasible or practical within the limits of the current plant design.
Physical obstructions imposed by design, geometry, and materials of construction are typical of vessel appurtenances and sacrificial shield, insulation support rings, structural and component support members, adjacent component weldments in close proximity, unique component configurations and dissimilar metal weldments.
Tables I4R-20.1 and I4R-20.2 below indicate the refueling outage in which these components were examined, and the coverage percentages obtained for those components that have been examined. These tables are cumulative lists of multiple components with limited examination coverage during the fourth ISI interval.
Based on the above considerations, Exelon Generation Company, LLC (EGC) requests relief from the requirement to achieve greater than 90% volume and/or area coverage for the components listed in Tables I4R-20.1 and I4R-20.2 below, where greater than 90%
coverage is impractical.
- 5. Burden Caused by Compliance:
Compliance with the examination requirements of ASME Section XI would require modification of plant components to remove obstructions, redesigning of plant systems, and replacement of components where geometry is inherent to component design.
- 6. Proposed Alternative and Basis for Use:
Proposed Alternative In accordance with 10 CFR 50.55a(g)(5)(iii), EGC requests relief from ASME Section XI Code requirements on the basis that the required "essentially 100%" coverage examination is impractical due to physical obstructions and limitations imposed by design, geometry, and materials of construction for the components listed in Tables I4R-20.1 and I4R-20.2 below. Because of the inherent interferences associated with the components listed in Tables I4R-20.1 and I4R-20.2, and the permanent insulation surrounding the reactor vessel skirt, there are no qualified alternative examination techniques currently available to increase coverage.
EGC will continue to perform best effort examinations in order to achieve the maximum amount of coverage possible. Additionally, a VT-2 examination is performed on the subject pressure-retaining components during system pressure tests per examination category B-P each refueling outage.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 3 of 14)
Basis for Use Examination techniques have been progressively upgraded during this interval to augment the required Section XI examinations. EGC continues to partner with the Electric Power Research Institute (EPRI), the Performance Demonstration Initiative (PDI), Inservice Inspection vendors and other industry sources to encourage the development and provide an awareness of improved examination techniques. The goal of these initiatives is to enhance coverage and flaw detection commensurate with radiation dose reduction.
EGC examination procedures are revised on a continuing basis to incorporate proven techniques for a higher level of safety and quality as they become available. The examinations and techniques used today exceed the examinations conducted in the past on each component.
All components received as a minimum, the required examination(s) to the extent practical due to the limited or lack of access available. The examinations conducted confirmed satisfactory results evidencing no unacceptable flaws present, even though "essentially 100%" coverage was not attained. EGC has concluded that if any active degradation mechanisms were to exist in the subject welds, those degradations would have been identified in the examinations performed.
Based on the above, with the vintage of the QCNPS, Units 1 and 2, designs, the underlying objectives of the code required volumetric and surface examinations have been met. The examinations were completed to the extent practical and evidenced no unacceptable flaws present. Additionally, a VT-2 examination is performed on the subject components during system pressure tests per examination category B-P each refueling outage and provides additional assurance that the structural integrity of the subject components is maintained.
- 7. Duration of Proposed Alternative:
Relief is requested for the fourth ten-year ISI interval of the Inservice Inspection Program for QCNPS, Units 1 and 2.
- 8. Precedents:
Relief was granted for the QCNPS, Units 1 and 2, third ISI intervals in NRC safety evaluations dated September 6, 2000, June 28, 2002, and May 10, 2005.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 4 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type 1/REACTOR The completed examination was limited to RPV COURSE VESSEL/RPV- IWB-2500-2 UT-SLIC 36.0% coverage due to the proximity of the
- 1 197 DEG B1.12 Q1R18 36.0%
VSC1- Volumetric 40/0°/55° core shroud repair tie rod and the sensing VERT SEAM 197/WELD line clamps.
1/REACTOR RPV COURSE The completed examination was limited to VESSEL/RPV- IWB-2500-2 UT-SLIC
- 1 317 DEG B1.12 Q1R18 85.0% 85.0% coverage due to the proximity of the VSC1- Volumetric 40/0°/55° VERT SEAM baffle plate.
317/WELD 1/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT-SLIC VESSEL/RPV- #1 55 DEG B1.12 Q1R18 78.0% 78.0% coverage due to the proximity of the Volumetric 40/0°/55° VSC1-55/WELD VERT SEAM baffle plate and the diffuser.
1/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT-SLIC VESSEL/RPV- #1 77 DEG B1.12 Q1R18 85.0% 85.0% coverage due to the proximity of the Volumetric 40/0°/55° VSC1-77/WELD VERT SEAM baffle plate.
1/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT-SLIC VESSEL/RPV- #2 22 DEG B1.12 Q1R18 66.0% 66.0% coverage due to proximity of the Volumetric 40/0°/55° VSC2-22/WELD VERT SEAM core shroud repair tie rod.
1/REACTOR The completed examination was limited to RPV COURSE VESSEL/RPV- IWB-2500-2 UT-SLIC 72.0% coverage due to the proximity of the
- 3 197 DEG B1.12 Q1R18 72.0%
VSC3- Volumetric 40/0°/55° core spray and feedwater spargers and VERT SEAM 197/WELD the core shroud tie rod repair brackets.
1/REACTOR RPV COURSE The completed examination was limited to VESSEL/RPV- IWB-2500-2 UT-SLIC
- 3 317 DEG B1.12 Q1R18 80.0% 80.0% coverage due to the proximity of the VSC3- Volumetric 40/0°/55° VERT SEAM core spray and feedwater spargers.
317/WELD
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 5 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type 1/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT- SLIC VESSEL/RPV- #3 77 DEG B1.12 Q1R18 80.0% 80.0% coverage due to the proximity of the Volumetric 40/0°/55° VSC3-77/WELD VERT SEAM core spray and feedwater spargers.
1/REACTOR RPV TOP IWB-2500-5 UT- The completed examination was limited to HEAD/RPV- HEAD TO Volumetric and B1.40 Q1R19 72.6% 60° RL, 72.6% coverage due to flange THHF/WELD FLANGE WELD Surface 60° L; MT configuration.
The completed examination was limited to 1/REACTOR RPV WELD IWB-2500-1 UT-SLIC 83.0% coverage due to proximity of the jet VESSEL/BMR- BELTLINE IWB-2500-2 B1.51 Q1R18 83.0%
40/0°/55° pump riser brackets and the core shroud 016-295/WELD REPAIR AREA Volumetric repair tie rod.
1/REACTOR RPV WELD IWB-2500-1 The completed examination was limited to UT-SLIC VESSEL/BMR- BELTLINE IWB-2500-2 B1.51 Q1R18 87.0% 87.0% coverage due to proximity of the jet 40/55° 167-305/WELD REPAIR AREA Volumetric pump riser bracket.
1/REACTOR The completed examination was limited to HEAD-NOZZLE IWB-2500-7 HEAD/N6A B3.90 Q1R19 56.5% UT-60° L 56.5% coverage due to nozzle (HEAD SPRAY) Volumetric NOZ/WELD configuration 1/REACTOR HEAD-NOZZLE The completed examination was limited to IWB-2500-7 HEAD/N6B (SPARE B3.90 Q1R19 56.5% UT-60° L 56.5% coverage due to nozzle Volumetric NOZ/WELD NOZZLE) configuration 1/REACTOR The completed examination was limited to HEAD-NOZZLE IWB-2500-7 HEAD/N7 B3.90 Q1R19 82.0% UT-60° L 82.0% coverage due to nozzle (HEAD VENT) Volumetric NOZ/WELD configuration.
1/REACTOR VESSEL- The completed examination was limited to IWB-2500-7 UT-60° L, VESSEL/N9 NOZZLE (CRD B3.90 Q1R21 81.9% 81.9% coverage due to nozzle Volumetric 45° S NOZ/WELD RETURN) configuration.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 6 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type VESSEL-1-0201H-12"- The completed examination was limited to NOZZLE IWB-2500-7 UT-60° L, A/N2A B3.90 Q1R18 43.0% 43.0% coverage due to nozzle (RECIRCULA- Volumetric 60° S NOZ/WELD configuration.
TION)
VESSEL-1-0201J-12"- The completed examination was limited to NOZZLE IWB-2500-7 UT-60° L, A/N2B B3.90 Q1R18 43.0% 43.0% coverage due to nozzle (RECIRCULA- Volumetric 60° S NOZ/WELD configuration.
TION)
VESSEL-1-0201K-12"- The completed examination was limited to NOZZLE IWB-2500-7 A/N2C B3.90 Q1R19 39.5% UT-60° RL 39.5% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD configuration.
TION)
VESSEL-1-0201L-12"- The completed examination was limited to NOZZLE IWB-2500-7 UT-60° S, A/N2D B3.90 Q1R18 43.0% 43.0% coverage due to nozzle (RECIRCULA- Volumetric 60° RL NOZ/WELD configuration.
TION)
VESSEL-1-0201M-12"- The completed examination was limited to NOZZLE IWB-2500-7 UT-60° L, A/N2E B3.90 Q1R18 43.0% 43.0% coverage due to nozzle (RECIRCULA- Volumetric 60° S NOZ/WELD configuration.
TION)
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 7 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type UT-60° L, Q1R21 34.2% 70° S, VESSEL- 60° S 1-0202A-28"- B3.90 The completed examination was limited to NOZZLE IWB-2500-7 A/N1A 34.2% total coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD UT-60° S, configuration.
TION)
Q1R18 30.0% 70° S, 60° L VESSEL-1-0202B-28"- UT-60° L, The completed examination was limited to NOZZLE IWB-2500-7 A/N1B B3.90 Q1R21 34.2% 70° S, 34.2% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 60° S configuration.
TION)
The completed examination was limited to VESSEL-1-1403-10"- UT-60° S, 42.0% coverage due to nozzle NOZZLE IWB-2500-7 A/N5A B3.90 Q1R18 42.0% 70° S, configuration and proximity of insulation (CORE Volumetric NOZ/WELD 60° L support ring below. Insulation support ring SPRAY) located 9" below nozzle.
VESSEL-1-1404-10"- The completed examination was limited to NOZZLE IWB-2500-7 A/N5B B3.90 Q1R19 27.7% UT-60° RL 27.7% coverage due to nozzle (CORE Volumetric NOZ/WELD configuration.
SPRAY) 1-3001A-20"- VESSEL- UT-60° S, The completed examination was limited to IWB-2500-7 B/N3A NOZZLE (MAIN B3.90 Q1R18 41.0% 70° S, 41.0% coverage due to nozzle Volumetric NOZ/WELD STEAM) 60° RL configuration.
1-3001B-20"- VESSEL- UT-60° S, The completed examination was limited to IWB-2500-7 B/N3B NOZZLE (MAIN B3.90 Q1R18 41.0% 70° S, 41.0% coverage due to nozzle Volumetric NOZ/WELD STEAM) 60° L configuration.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 8 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type 1-3001C-20"- VESSEL- The completed examination was limited to IWB-2500-7 B/N3C NOZZLE (MAIN B3.90 Q1R19 37.9% UT-60° RL 37.9% coverage due to nozzle Volumetric NOZ/WELD STEAM) configuration.
1-3001D-20"- NOZZLE- The completed examination was limited to IWB-2500-7 B/N3D VESSEL (MAIN B3.90 Q1R19 37.9% UT-60° RL 37.9% coverage due to nozzle Volumetric NOZ/WELD STEAM) configuration.
UT-45° S, 1-3204C-12"- NOZZLE- The completed examination was limited to IWB-2500-7 60° L, C/N4A VESSEL B3.90 Q1R19 33.5% 33.5% coverage due to nozzle Volumetric 70° L, NOZ/WELD (FEEDWATER) configuration.
60° S UT-45° S, 1-3204D-12"- VESSEL- The completed examination was limited to IWB-2500-7 60° L, C/N4B NOZZLE B3.90 Q1R19 34.5% 34.5% coverage due to nozzle Volumetric 70° L, NOZ/WELD (FEEDWATER) configuration and bioshield interferences.
60° S UT- 45° S, 1-3204F-12"- VESSEL- The completed examination was limited to IWB-2500-7 60° L, C/N4C NOZZLE B3.90 Q1R19 34.2% 34.2% coverage due to nozzle Volumetric 70° L, NOZ/WELD (FEEDWATER) configuration and bioshield interferences.
60° S UT- 45° S, 1-3204E-12"- VESSEL- The completed examination was limited to IWB-2500-7 60° L, C/N4D NOZZLE B3.90 Q1R19 33.5% 33.5% coverage due to nozzle Volumetric 70° L, NOZ/WELD (FEEDWATER) configuration.
60° S The completed examination was limited to 1/REACTOR 7.0% coverage due to lower portion and ID VESSEL/0200- RPV SKIRT IWF-1300-1 F1.40 Q1R21 7.0% VT-3 covered with permanent insulation and W-184 RTD instrumentation.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 9 of 14)
Table I4R-20.1: QCNPS Unit 1 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type IWB-2500-8(c) UT-E The completed examination was limited to 1/REACTOR IWB-2500-9 35-65° S, NOZZLE-SAFE 86.2% coverage due to nozzle VESSEL/03- IWB-2500-10 R1.20 Q1R21 86.2%
END 25-70° L configuration upstream and safe end F1A/WELD IWB-2500-11 configuration downstream Volumetric UT-E IWB-2500-8(c) 30° S The completed examination was limited to 1-1102-1 1/2"- IWB-2500-9 45° S NOZZLE-SAFE 85.8% coverage due to the configuration A/N10- IWB-2500-10 R1.20 Q1R22 85.8%
END 31° L and geometry of the weld, safe end and F1/WELD IWB-2500-11 45° L nozzle.
Volumetric 60° L
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 10 of 14)
Table I4R-20.2: QCNPS Unit 2 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type 2/REACTOR The completed examination was limited to RPV COURSE VESSEL/RPV- IWB-2500-2 UT-SLIC 38.0% coverage due to the proximity of the
- 1 197 DEG B1.12 Q2R18 38.0%
VSC1- Volumetric 40/55° baffle plate, the jet pump, diffuser, and the VERT SEAM 197/WELD core shroud repair tie rod.
2/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT-SLIC VESSEL/RPV- #2 22 DEG B1.12 Q2R18 66.0% 66.0% coverage due to the proximity of the Volumetric 40/55° VSC2-22/WELD VERT SEAM core shroud repair tie rod.
The completed examination was limited to 2/REACTOR RPV COURSE 75.0% coverage due to the proximity of the VESSEL/RPV- IWB-2500-2 UT-SLIC
- 3 197 DEG B1.12 Q2R18 75.0% core spray and feedwater spargers. The VSC3- Volumetric 40/55° VERT SEAM guide rod, and core shroud tie rod repair 197/WELD brackets.
2/REACTOR RPV COURSE The completed examination was limited to VESSEL/RPV- IWB-2500-2 UT-SLIC
- 3 317 DEG B1.12 Q2R18 79.0% 79.0% coverage due to the proximity of the VSC3- Volumetric 40/55° VERT SEAM core spray and feedwater spargers.
317/WELD 2/REACTOR RPV COURSE The completed examination was limited to IWB-2500-2 UT-SLIC VESSEL/RPV- #3 77 DEG B1.12 Q2R18 82.0% 82.0% coverage due to the proximity of the Volumetric 40/55° VSC3-77/WELD VERT SEAM core spray and feedwater spargers.
2/REACTOR RPV COURSE The completed examination was limited to VESSEL/RPV- IWB-2500-2 UT-SLIC
- 4 219 DEG B1.12 Q2R17 86.0% 86.0% coverage due to the proximity of the VSC4- Volumetric 40/0°/55° VERT SEAM Steam Dryer Support Bracket.
219/WELD 2/REACTOR RPV TOP IWB-2500-5 UT- The completed examination was limited to HEAD/RPV- HEAD TO Volumetric and B1.40 Q2R19 67.2% 60° RL; 67.2% coverage due to the proximity of the THHF/WELD FLANGE WELD Surface MT Top Head Flange.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 11 of 14)
Table I4R-20.2: QCNPS Unit 2 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type UT-2/REACTOR The completed examination was limited to HEAD-NOZZLE IWB-2500-7 60° RL, HEAD/N6A B3.90 Q2R19 63.3% 63.3% coverage due to nozzle (HEAD SPRAY) Volumetric 45° S, NOZ/WELD configuration.
60° S UT-2/REACTOR HEAD-NOZZLE The completed examination was limited to IWB-2500-7 60° RL, HEAD/N6B (SPARE B3.90 Q2R19 63.3% 63.3% coverage due to nozzle Volumetric 45° S, NOZ/WELD NOZZLE) configuration.
60° S 2/REACTOR UT- The completed examination was limited to HEAD-NOZZLE IWB-2500-7 HEAD/N7 B3.90 Q2R19 82.5% 60° RL, 82.5% coverage due to nozzle (HEAD VENT) Volumetric NOZ/WELD 60° S configuration.
The completed examination was limited to 2/REACTOR VESSEL- UT-IWB-2500-7 77.5% coverage due to nozzle VESSEL/N9 NOZZLE (CRD B3.90 Q2R19 77.5% 60° RL, Volumetric configuration and insulation support NOZ/WELD RETURN) 45° S bracket.
VESSEL-2-0201H-12"- UT-0° L, The completed examination was limited to NOZZLE IWB-2500-7 A/N2A B3.90 Q2R17 28.0% 60° RL, 28.0% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 45° S configuration.
TION)
VESSEL-2-0201J-12"- UT- The completed examination was limited to NOZZLE IWB-2500-7 A/N2B B3.90 Q2R18 37.2% 60° RL, 37.2% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 60° S configuration.
TION)
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 12 of 14)
Table I4R-20.2: QCNPS Unit 2 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type VESSEL-2-0201K-12"- UT-0° L, The completed examination was limited to NOZZLE IWB-2500-7 A/N2C B3.90 Q2R17 28.0% 60° RL, 28.0% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 45° S configuration.
TION)
VESSEL-2-0201L-12"- UT- The completed examination was limited to NOZZLE IWB-2500-7 A/N2D B3.90 Q2R18 37.2% 60° RL, 37.2% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 60° S configuration.
TION)
VESSEL-2-0201M-12"- The completed examination was limited to NOZZLE IWB-2500-7 UT-60° A/N2E B3.90 Q2R18 37.2% 37.2% coverage due to nozzle (RECIRCULA- Volumetric RL, 60° S NOZ/WELD configuration.
TION)
VESSEL-2-0202A-28"- UT-60° The completed examination was limited to NOZZLE IWB-2500-7 A/N1A B3.90 Q2R18 21.0% RL, 60° S, 21.0% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 70° S configuration.
TION)
VESSEL-2-0202B-28"- UT-60° The completed examination was limited to NOZZLE IWB-2500-7 A/N1B B3.90 Q2R20 35.4% RL, 60° S, 35.4% coverage due to nozzle (RECIRCULA- Volumetric NOZ/WELD 70° S configuration.
TION)
VESSEL- The completed examination was limited to 2-1403-10"- UT-NOZZLE IWB-2500-7 43.1% coverage due to nozzle A/N5A B3.90 Q2R19 43.1% 60° RL, (CORE Volumetric configuration and insulation support NOZ/WELD 60° S SPRAY) bracket.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 13 of 14)
Table I4R-20.2: QCNPS Unit 2 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type VESSEL- The completed examination was limited to 2-1404-10"- UT-NOZZLE IWB-2500-7 43.1% coverage due to nozzle A/N5B B3.90 Q2R19 43.1% 60° RL, (CORE Volumetric configuration and insulation support NOZ/WELD 60° S SPRAY) bracket.
UT-2-3001B-20"- VESSEL- The completed examination was limited to IWB-2500-7 60° RL, B/N3B NOZZLE (MAIN B3.90 Q2R19 40.8% 40.8% coverage due to nozzle Volumetric 60° S, NOZ/WELD STEAM) configuration.
70° S UT-2-3001D-20"- VESSEL- The completed examination was limited to IWB-2500-7 60° RL, B/N3D NOZZLE (MAIN B3.90 Q2R19 40.8% 40.8% coverage due to nozzle Volumetric 60° S, NOZ/WELD STEAM) configuration.
70° S The completed examination was limited to 2-3204C-12"- VESSEL- UT-0° L, IWB-2500-7 33.0% coverage due to nozzle C/N4A NOZZLE B3.90 Q2R17 33.0% 60° RL, Volumetric configuration, thermocouple pad, and NOZ/WELD (FEEDWATER) 45° S bioshield interferences.
2-3204D-12"- VESSEL- UT-0° L, The completed examination was limited to IWB-2500-7 C/N4B NOZZLE B3.90 Q2R17 33.0% 60° RL, 33.0% coverage due to nozzle Volumetric NOZ/WELD (FEEDWATER) 45° S configuration and bioshield interferences.
The completed examination was limited to 2-3204F-12"- VESSEL- UT-0° L, IWB-2500-7 33.0% coverage due to nozzle C/N4C NOZZLE B3.90 Q2R17 33.0% 60° RL, Volumetric configuration, thermocouple pad, and NOZ/WELD (FEEDWATER) 45° S bioshield interferences.
2-3204E-12"- VESSEL- UT-0° L, The completed examination was limited to IWB-2500-7 C/N4D NOZZLE B3.90 Q2R17 33.0% 60° RL, 33.0% coverage due to nozzle Volumetric NOZ/WELD (FEEDWATER) 45° S configuration and bioshield interferences.
ATTACHMENT 10 CFR 50.55a Relief Request I4R-20 Revision 0 (Page 14 of 14)
Table I4R-20.2: QCNPS Unit 2 - List of Components with Limited Examination Coverage Weld Exam Item Outage Actual Exam Component ID Remarks Description Requirements Number Examined Coverage Type The completed examination was limited to 2/REACTOR 5.3% coverage due to lower portion and ID VESSEL/0200- RPV SKIRT IWF-1300-1 F1.40 Q2R21 5.3% VT-3 covered with permanent insulation and W-178 RTD instrumentation.