ML100191797
| ML100191797 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/15/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ISI-23 | |
| Download: ML100191797 (22) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 January 15, 2010 10 CFR 50.4 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
American Society of Mechanical Engineers,Section XI Inservice Inspection Program for the Unit I Second Ten-Year Inspection Interval and the Units 2 and 3 Third Ten-Year Inspection Interval, Request for Relief ISI-23 In accordance with 10 CFR 50.55a(a)(3)(i), the Tennessee Valley Authority (TVA) is requesting relief from certain inservice inspection (ISI) requirements in Section XI of the American Society of Mechanical Engineers (ASME) Code, for the volumetric examination of Class 1, reactor pressure vessel (RPV) nozzle-to-vessel welds and nozzle inner radius sections for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. An alternative to the Section XI requirements is requested for the BFN Unit 1 Second Ten-Year Inspection Interval and the BFN Units 2 and 3 Third Ten-Year Inspection Interval. The enclosure to this letter contains BFN Units 1, 2, and 3 request for relief ISI-23, for NRC review and approval.
TVA proposes to use ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds," in lieu of the examination requirements of ASME Section XI, Table IWB-2500-1, "Examination Categories," to allow reduced percentage requirements for Nozzle-to-Vessel Weld and Inner Radius Section examinations.
The technical basis for ASME Code Case N-702 is documented in the Electric Power Research Institute (EPRI) Technical Report 1003557, dated October 2002, for the Boiling Water Reactor Vessel and Internals Project (BWRVIP), "BWRVIP-108, BWR Vessel and Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 January 15, 2010 Internals Project, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius," which was approved by the NRC in a Safety Evaluation Report dated December 19, 2007 (ML073600374).
This request for relief is consistent with a request for relief submitted for the Duane Arnold Energy Center by letter dated February 28, 2008. This request was approved by NRC as documented in a safety evaluation dated August 28, 2008.
TVA requests approval of this request for relief by September 2, 2010 to support the BFN Unit 1 fall refueling outage.
There are no new regulatory commitments in this letter. If you have any questions, please contact Dan Green at (423) 751-8423.
Respectfully, R. M. Krich Vice President Nuclear Licensing
Enclosure:
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request for Relief ISI-23 cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3 American Society of Mechanical Engineers,Section XI Inservice Inspection Program, Unit 1 Second Ten-Year Inspection Interval and Units 2 and 3 Third Ten-Year Inspection Interval Request for Relief ISI-23 Executive Summary: In accordance with 10 CFR 50.55a(a)(3)(i), the Tennessee Valley Authority (TVA) is requesting relief from inservice inspection requirements of the 2001 Edition through 2003 Addenda of Section Xl, Table IWB-2500-1, "Examination Category B-D, Full Penetration Welded Nozzles in Vessels-Inspection Program B," Item No.B3.90, "Reactor Vessel Nozzle to Vessel Welds," and Item No. B3.100, "Reactor Vessel Nozzle Inner Radius Section" of the ASME Boiler and Pressure Vessel Code (BFN Units 1 and 3) and from inservice inspection requirements of the 1995 Edition, 1996 Addenda of Section Xl, Table IWB-2500-1 Examination Category B-D, "Full Penetration Welded Nozzles in Vessels-Inspection Program B", Item No.B3.90, "Reactor Vessel Nozzle to Vessel Welds,"
and Item No. B3.100, "Reactor Vessel Nozzle Inner Radius Section" of the ASME Boiler and Pressure Vessel Code (Unit 2).
As an alternative, TVA proposes to use ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds," in lieu of the examination requirements of ASME Section XI, Table IWB-2500-1, "Examination Categories," to allow reduced percentage requirements for Nozzle-to-Vessel Weld and Inner Radius Section examinations.
Unit: Browns Ferry Nuclear Plant, Units 1, 2, and 3 ASME Code Components Affected: Reactor Pressure Vessel (RPV), Nozzle-to-Vessel Welds and RPV Nozzle Inner Radius Sections:
Reactor Recirculation Inlet Nozzles, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, and N2K Main Steam Nozzles, N3A, N3B, N3C, and N3D Core Spray Nozzles, N5A and N5B Reactor Pressure Vessel (RPV) Head Nozzles, N6A, N6B, and N7 Jet Pump Instrumentation Nozzles, N8A and N8B ASME Code Class: ASME Code Class 1 E-1
Section Xl Edition: 2001 Edition, 2003 Addenda for BFN Units 1 and 3 and 1995 Edition, 1996 Addenda for BFN Unit 2. Additionally, for ultrasonic examinations, Section Xl, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the 2001 Edition (BFN Units 1 and 3) or 1995 Edition, 1996 Addenda (BFN Unit 2) is implemented as required and modified by 10 CFR 50.55a(b)(2)(xv).
Code Table: Table IWB-2500-1, "Examination Categories" Code Examination Category: B-D, "Full Penetration Welded Nozzles in Vessels" -
Inspection Program B Code Examination Item Number: B3.90, "Nozzle-To-Vessel Welds" and B3.100, "Nozzle Inside Radius Section" Code Requirement: The 2001 Edition, 2003 Addenda and 1995 Edition, 1996 Addenda, of ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and Item No. B3.100, require 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.
Reason for Request: The RPV Nozzle-to-Vessel Shell Welds and RPV Nozzle Inner Radius Sections listed in Attachment A are scheduled to be examined prior to the end of the current inspection interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed alternative provides an acceptable level of quality and safety and the reduction in examination scope could provide a total reduction in personnel radiation exposure of as much as 17.9 Person-REM (see Attachment A) over the remainder of the current inspection interval for each of the BFN units.
Proposed Alternative and Basis for Use: Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from performing the required examinations on 100 percent of the identified nozzles. As an alternative, TVA proposes to examine 25 percent of the nozzle-to-vessel welds and nozzle inner radius sections, except for the Recirculation Outlet welds, including at least one nozzle from each system and nominal pipe size in accordance with ASME Code Case N-702. For the nozzles identified in Attachment A, the number of components to be examined from each group is provided in Table 1 below. For BFN Units 2 and 3, TVA is taking credit for nozzle-to-vessel welds and inner radius section examinations previously completed during the current ten-year interval for each unit. This relief is not requested to be applied to the Recirculation Outlet Nozzle welds.
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Table 1 Number of Nozzles / Inner Radius to be Examined System and Nozzle Number of Nozzles Number to be Comments ID Examined Reactor 10 3
See Attachment C for Recirculation Inlet history of previous (N2A, N2B, N2C, examinations.
N2D, N2E, N2F, N2G, N2H, N2J, and N2K)
1 See Attachment C for (N3A, N3B, N3C, history of previous and N3D) examinations.
1 See Attachment C for (N5A and N5B) history of previous examinations.
Reactor Pressure 3
1 See Attachment C for Vessel (RPV) Head history of previous (N6A, N6B, and N7) examinations.
Jet Pump 2
1 See Attachment C for Instrumentation (N8A history of previous and N8B) examinations.
Code Case N-702 states that a VT-1 visual examination may be used in lieu of volumetric examination for the inner radii (Item B3.100). TVA is currently using Code Case N-648-1, Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles, Section Xl Division 1, subject to the conditions provided in Regulatory Guide 1.147, Revision 15, dated October 2007.
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Basis For Relief: Electric Power Research Institute (EPRI) Technical Report 1003557, dated October 2002, "BWRVIP-108: Boiling Water Reactor 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 Radius," provides the basis for ASME Code Case N-702. EPRI Technical Report 1003557 found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell weld due to a Low Temperature Overpressure event are very low (i.e., <1 x 10-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25 percent of each nozzle type is technically justified.
The NRC documented their review of the EPRI report in an NRC Safety Evaluation Report (SER) dated December 19, 2007. In Section 5.0, "Plant Specific Applicability," of the SER, the NRC stated that each licensee who plans to request relief from the ASME Code,Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radius sections may reference the BWRVIP-108 report as the technical basis for the use of ASME Code Case N-702 as an alternative. However, each licensee should demonstrate the plant-specific applicability for the BWRVIP-1 08 report to each unit in the relief request by showing that all the general and nozzle-specific criteria addressed below are satisfied (See Attachment B):
(1)
The maximum Reactor Pressure Vessel (RPV) heatup/cooldown rate is limited to less than 11 5°F per hour. The BFN Units 1, 2, and 3 Technical Specifications (TS)
Surveillance Requirement (SR) 3.4.9.1.b limits Reactor Coolant System (RCS) heatup and cooldown rates to < 100°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pressure and temperature limits specified in TS Figure 3.4.9-1, "Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations." For the pressure and temperature limits specified in TS Figure 3.4.9-2, "Pressure/Temperature Limits for In-Service Leak and Hydrostatic Testing," Note 2 to BFN Units 1, 2, and 3, TS SR 3.4.9.1 limits RCS heatup and cooldown rates to
< 150 F/hour. The TVA surveillance procedures that require monitoring of reactor vessel heatup/cooldown (Surveillance Procedure 1-, 2-, 3-SR-3.4.9.1(1) and 1-, 2-,
3-SR-3.4.9.1(2)) limit the heatup and cooldown rates to less than or equal to 1 00°F/hr for Browns Ferry TS Figure 3.4.9-1 pressure/temperature limits and less than or equal to 150F/hr for TS Figure 3.4.9-2 pressure/temperature limits.
For the Recirculation Inlet Nozzles the following criteria must be met:
(2)
(pr/t)/CRPV<1.15, the calculation for BFN Recirculation Inlet (N2) Nozzles results in 1.0986 which is less than 1.15 which satisfies Criterion 2.
(3)
[p(r02 +ri2)/(ro2-ri2)]/CNOZZLE<1.15, the calculation for BFN N2 Nozzles results in 1.0012 which is less than 1.15 which satisfies Criterion 3.
For the Recirculation Outlet Nozzles the following criteria must be met:
(4)
(pr/t)/CRPV< 1.15, the calculation for BFN Recirculation Outlet (Ni) Nozzles results in 1.3134 which is higher than 1.15. Therefore, Criterion 4 is not satisfied for the BFN N1 nozzles. Therefore, these nozzles are not in the scope of this relief request.
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(5)
[p(ro2 +ri2)/(ro2-ri 2)]/CNOZZLE<1.15, the calculation for the BFN N1 Nozzles results in 1.0751 which is less than 1.15 which satisfies Criterion 5.
Based upon the above information, all RPV nozzle-to-vessel shell welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles, meet the BWRVIP-108 Report criteria and therefore Code Case N-702 is applicable. The Recirculation Outlet Nozzles do not meet all of the BWRVIP-108 Report criteria. Therefore, Code Case N-702 is not applicable to these nozzles. As such, this relief is not requested to be applied to the Recirculation Outlet Nozzles. See Attachment B for details.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), TVA considers that the use of Code Case N-702 provides an acceptable level of quality and safety for all RPV nozzle-to-vessel shell welds and nozzle inner radii sections for each BFN unit, with the exception of the Recirculation Outlet Nozzles (N1A and N1B).
Implementation Schedule:
This alternative is requested for the BFN Units 1, 2, and 3 current Ten-Year Inspection intervals as listed below:
Unit 1, Second Ten-Year Inspection interval (June 2, 2008 through June 1, 2017)
Unit 2, Third Ten-Year Inspection interval (May 25, 2001 through May 24, 2011)
Unit 3, Third Ten-Year Inspection interval (November 19, 2005 through November 18, 2015)
Precedent:
The NRC has approved a similar request for the Duane Arnold Energy Center. This approval is documented in an NRC safety evaluation dated August 28, 2008 (ML082040046).
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'I tt~achment A - Annlid-h1ck Nn,77I0 I Inncar q~rii"Q fnr "nit I RPV Nozzle Component ID Category Item Number Nozzle ID (NOM)
Comments/Dose Estimates Man-hrs Dose Rate Dose (mR-hr) (Rem) 8 85 0.680 N2A N2A-NV B-D B3.90 11.56" N2A-IR B-D B3.100 11.56" 8
85 0.680 N2B N2B-NV B-D B3.90 11.56" N2B-IR B-D B3.100 11.56" 8
85 0.680 N2C N2C-NV B-D B3.90 11.56" N2C-IR B-D B3.100 11.56" 8
85 0.680 N2D N2D-NV B-D B3.90 11.56" N2D-IR B-D B3.100 11.56" 8
85 0.680 N2E N2E-NV B-D B3.90 11.56" N2E-IR B-D B3.100 11.56" 8
85 0.680 N2F N2F-NV B-D B3.90 11.56" N2F-IR B-D B3.100 11.56" 8
85 0.680 N2G N2G-NV B-D B3.90 11.56" N2G-IR B-D B3.100 11.56"° 8
85 0.680 N2H N2H-NV B-D B3.90 11.56" N2H-IR B-D B3.100 11.56" 8
85 0.680 N2J N2J-NV B-D B3.90 11.56" N2J-IR B-D B3.100 11.56" 8
85 0.680 N2K N2K-NV B-D B3.90 11.56" N2K-IR B-D B3.100 11.56" 10 60 0.600 N3A N3A-NV B-D B3.90 23.75" N3A-IR B-D 63.100 23.75"
'A-1
RPV Nozzle Component ID Category Item Number Nozzle ID (NOM)
Comments/Dose Estimates Man-hrs Dose Rate Dose (mR-hr) (Rem) 10 60 0.600 N3B N3B-NV B-D B3.90 23.75" N3B-IR B-D B3.100 23.75" 10 60 0.600 N3C N3C-NV B-D B3.90 23.75" N3C-IR B-D B3.100 23.75" 10 60 0.600 N3D N3D-NV B-D B3.90 23.75" N3D-IR B-D B3.100 23.75" 6
30 0.180 N5A N5A-NV B-D B3.90 8.78" N5A-IR B-D B3.100 8.78" 6
30 0.180 N5B N5B-NV B-D B3.90 8.78" N51B-IR B-D B3.100 8.78" 6
15 0.090 N6A N6A-NV B-D B3.90 6-7/32" N6A-IR B-D B3.100 6-7/32" 6
15 0.090 N6B N6B-NV B-D B3.90 6-7/32" N6B-IR B-D B3.100 6-7/32" 5
30 0.150 N7 N7-NV B-D B3.90 4-1/4" N7-IR B-D B3.100 4-1/4" 5
40 0.200 N8A N8A-NV B-D B3.90 3-13/16" N8A-IR B-D B3.100 3-l 3/16" 5
40 0.200 N8B N8B-NV B-D B3.90 3-13/16" N8B-IR B-D B3.100 3-13/16" Total Dose Savings for Remainder of the 2nd Interval (Note 1) 7.18 Rem Note 1: Dose savings of 7.18 Rem is based on performance of the reduced number of components to be examined as shown in Table 1.
A-2
Attachment A - Applicable Nozzles / Inner Radius for Unit 2 RPV Nozzle Component ID Category Item Number Nozzle ID (NOM)
Comments/Dose Estimates Man-hrs Dose Rate Dose (mR-hr) (Rem) 8 85 Note 2 N2A N2A-NV B-D B3.90 11.56" N2A-IR B-D B3.100 11.56" 8
85 Note 2 N2B N2B-NV B-D B3.90 11.56" N2B-IR B-D B3.100 11.56" 8
85 Note 2 N2C N2C-NV B-D B3.90 11.56" N2C-IR B-D B3.100 11.56" 8
85 0.680 N2D N2D-NV B-D B3.90 11.56" N2D-IR B-D B3.100 11.56" 8
85 0.680 N2E N2E-NV B-D B3.90 11.56" N2E-IR B-D B3.100 11.56" 8
85 Note 2 N2F N2F-NV B-D B3.90 11.56" N2F-IR B-D B3.100 11.56" 8
85 Note 2 N2G N2G-NV B-D B3.90 11.56" N2G-IR B-D B3.100 11.56" 8
85 Note2 N2H N2H-NV B-D B3.90 11.56" N2H-IR B-D B3.100 11.56" 8
85 Note 2 N2J N2J-NV B-D B3.90 11.56" N2J-IR B-D B3.100 11.56" 8
85 0.680 N2K N2K-NV B-D B3.90 11.56" 8
50.0 N2K-IR B-D B3.100 11.56" 10 60 0.600 N3A N3A-NV B-D B3.90 23.75 N3A-IR B-D B3.100 23.75" A-3
RPV Nozzle ComponentlD Category Item Number Nozzle ID (NOM)
Comments/Dose Estimates Man-hrs Dose Rate D os e (mR-hr) (Rem) 10 60 Note 2 N3B N3B-NV B-D B3.90 23.75" N3B-IR B-D B3.100 23.75" 10 60 0.600 N3C N3C-NV B-D B3.90 23.75" N3C-IR B-D B3.100 23.75" 10 60 Note 2 N3D N3D-NV B-D B3.90 23.75" N3D-IR B-D B3.100 23.75" 6
30 Note 2 N5A N5A-NV B-D B3.90 8.78" N5A-IR B-D B3.100 8.78" 6
30 Note 2 N5B N5B-NV B-D B3.90 8.78" N5B-IR B-D B3,. 100 8.78" 6
15 Note 2 N6A N6A-NV B-D B3.90 6-7/32" N6A-IR B-D B3.100 6-7/32" 6
15 0.090 N6B N6B-NV B-D B3.90 6-7/32" N6B-IR B-D B3.100 6-7/32" 5
30 Note 2 N7 N7-NV B-D B3.90 4-1/4" N7-IR B-D B3.100 4-1/4" 5
40 Note 2 N8A N8A-NV B-D B3.90 3-13/16" N8A-IR B-D B3.100 3-13/16" 5
40 0.200 N8B N8B-NV B-D B3.90 3-13/16" N8B-IR B-D B3.100 3-13/16" Total Dose Savings for Remainder of the 2nd Interval 3.53 Rem Note 2: Previously examined during the interval. Not included in dose savings.
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Attachment A - Applicable Nozzles / Inner Radius for Unit 3 RPV Nozzle Component ID Category Item Number Nozzle ID (NOM)
Comments/DoseEstimates Man-hrs Dose Rate Dose (mR-hr) (Rem) 8 85 0.680 N2A N2A-NV B-D B3.90 11.56" N2A-IR B-D B3.100 11.56" 8
85 Note 3 N2B N2B-NV B-D B3.90 11.56" N2B-IR B-D B3.100 11.56" 8
85 0.680 N2C N2C-NV B-D B3.90 11.56" N2C-IR B-D B3.100 11.56" 8
85 Note 3 N2D N2D-NV B-D B3.90 11.56" N2D-IR B-D B3.100 11.56" 8
85 0.680 N2E N2E-NV B-D B3.90 11.56" N2E-IR B-D B3.100 11.56" 8
85 Note 3 N2F N2F-NV B-D B3.90 11.56" N2F-IR B-D B3.100 11.56" 8
85 0.680 N2G N2G-NV B-D B3.90 11.56" N2G-IR B-D B3.100 11.56" 8
85 0.680 N2H N2H-NV B-D B3.90 11.56" N2H-IR B-D B3.100 11.56" 8
85 0.680 N2J N2J-NV B-D B3.90 11.56" N2J-IR B-D B3.100 11.56" 8
85 0.680 N2K N2K-NV B-D B3.90 11.56" N2K-IR B-D B3.100 11.56" 10 60 0.600 N3A N3A-NV B-D B3.90 23.75" N3A-IR B-D B3.100 23.75" 7
1 A-5
RPV Nozzle ComponentlD Category Item Number Nozzle ID (NOM)
Comments/Dose Estimates Man-hrs Dose Rate Dose (mR.hr)
(Rem) 10 60 Note 3 N3B N3B-NV B-D B3.90 23.75" N3B-IR B-D B3.100 23.75" 10 60 0.600 N3C N3C-NV B-D B3.90 23.75" N3C-IR B-D B33100 23.75" 10 60 0.600 N3D N3D-NV B-D B3.90 23.75" N3D-IR B-D B3.100 23.75" 6
30 Note 3 N5A N5A-NV B-D B3.90 8.78" N5A-IR B-D B3.100 8.78" 6
30 0.180 N5B N5B-NV B-D B3.90 8.78" N5B-IR B-D B3.100 8.78" 6
15 Note 3 N6A N6A-NV B-D B3.90 6-7/32" N6A-IR B-D B3.100 6-7/32" 6
15 0.090 N6B N6B-NV B-D B3.90 6-7/32" N6B-IR B-D B3.100 6-7/32" 5
30 0.150 N7 N7-NV B-D B3.90 4-1/4" N7-IR B-D B3.100 4-1/4" 5
40 Note 3 N8A N8A-NV B-D B3.90 3-13/16" N8A-IR B-D B3.100 3-13/16" 5
40 0.200 N8B N8B-NV B-D B3.90 3-13/16" N8B-IR B-D B3.100 3-13/16" Total Dose Savings for Remainder of 3rd Interval 7.18 Rem Note 3: Previously examined during the interval. Not included in dose savings A-6
Attachment B Responses to NRC Plant Specific Applicability Unit 1 (1) The maximum Reactor Pressure Vessel (RPV) heatup / cooldown rate is limited to less than 115 0F/hour.
Technical Specification Surveillance Requirement SR 3.4.9.1.b limits RCS heatup and cooldown rates to less than or equal to 1 00°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
Recirculation Inlet Nozzles Recirculation Outlet Nozzles (2)
(pr/t)/CRPV< 1.15 (4)
(pr/t)/CRPV< 1.15 p = RPV normal operating 1035 p = RPV normal operating 1035 pressure pressure r = RPV inner radius 125-11/16" r = RPV inner radius 125-11/16" t = RPV wall thickness 6.125" t = RPV wall thickness 6.125" CRPV 19332 CRPV 16171 1.0986 < 1.15 1.3134 > 1.15: Criterion Not Satisfied (3)
[p(r0 2 + ri2)/(ro2 - ri2 )]/CNOzZLE < 1.15 (5)
[p(ro2 + ri2)/(ro2 - ri2)]/CNOZZLE < 1.15 p = RPV normal operating pressure 1035 p = RPV normal operating pressure 1035 ro = nozzle outer radius 12.5" r, = nozzle outer radius 26.5" ri = nozzle inner radius 5.941 ri = nozzle inner radius 15.566" CNOZZLE 1637 CNOZZLE 1977 1.0012 < 1.15 1.0751 < 1.15 B-1
Attachment B Responses to NRC Plant Specific Applicability Unit 2 (1) The maximum Reactor Pressure Vessel (RPV) heatup / cooldown rate is limited to less than 115 0F/hour.
Technical Specification Surveillance Requirement SR 3.4.9.1-.b limits RCS heatup and cooldown rates to less than or equal to 100°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
Recirculation Inlet Nozzles Recirculation Outlet Nozzles (2)
(pr/t)/CRPV<1.15 (4)
(pr/t)/CRPV< 1.15 p = RPV normal operating pressure 1035 p = RPV normal operating 1035 pressure r = RPV inner radius 125-r = RPV inner radius 125-11/16" 11/16" t = RPV wall thickness 6.125" t = RPV wall thickness 6.125" CRPV 19332 CRPV 16171 1.0986 < 1.15 1.3134 > 1.15: Criterion Not Satisfied (3)
[p(r0 2 + ri2)/(ro2 - rF2)]/CNOZZLE < 1.15 (5)
[p(ro2 + ri2)/(r 0 2 - ri2)]/CNoZZLE < 1.15 p = RPV normal operating pressure 1035 p = RPV normal operating 1035 pressure ro = nozzle outer radius 12.5" ro nozzle outer radius 26.5" ri = nozzle inner radius 5.941" ri = nozzle inner radius 15.566" CNOZZLE 1637 CNOZZLE 1977 1.0012 < 1.15 1.0751 < 1.15 B-2
Attachment B Responses to NRC Plant Specific Applicability Unit 3 (1) The maximum Reactor Pressure Vessel (RPV) heatup / cooldown rate is limited to less than 115 0F/hour.
Technical Specification Surveillance Requirement SR 3.4.9.1.b limits RCS heatup and cooldown rates to less than or equal to 1 00°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
Recirculation Inlet Nozzles Recirculation Outlet Nozzles (2)
(pr/t)/CRPV< 1.15 (4)
(pr/t)/CRPV <1.15 p = RPV normal operating 1035 p = RPV normal operating 1035 pressure pressure r = RPV inner radius 125-11/16" r = RPV inner radius 125-11/16" t = RPV wall thickness 6.125" t = RPV wall thickness 6.125" CRPV 19332 CRPV 16171 1.0986 < 1.15 1.3134 > 1.15: Criterion Not Satisfied (3)
[p(r0 2 + r 2)/(ro2 - rF2 )]/CNOZZLE < 1.15 (5)
[p(ro2 + ri2)/(ro2 - ri2)]/CNOZZLE < 1.15 p = RPV normal operating 1035 p = RPV normal operating 1035 pressure pressure ro = nozzle outer radius 12.5" ro = nozzle outer radius 26.5" ri= nozzle inner radius 5.941" r = nozzle inner radius 15.566" CNOZZLE 1637 CNOZZLE 1977 1.0012 < 1.15 1.0751 < 1.15 B-3
Attachment C Unit I Applicable Nozzles Component ID Category Item System Nominal CYCLE DATE Comments Number Number Pipe Size N2ANV(Note 1)
B-D B3.90 Recirc Inlet 12" 4
5/06/81 5/10/81 5/09/81 N2A-IR(Note 1)
B-D B3.100 Recirc Inlet 12" 4
5/09/81 N2BNVNOte 1)
B-D B3.90 Recirc Inlet 12" 4
5/04/81 5/10/81 5/08/81 N2BIR'Note 1)
B-D B3.100 Recirc Inlet 12" 4
5/08/81 N2CNVNot e 1)
B-D B3.90 Recirc Inlet 12" 4
5/10/81 5/06/81 N2C-IR"Note 17 B-D B3.100 Recirc Inlet 12" 4
5/09/81 N2DNV(Note 1)
B-D B3.90 Recirc Inlet 12" 4
5/04/81 5/10/81
-N2DIR(Note 1)
B-D B3.100 Recirc Inlet 12" 4
5/12/81 N2E-NVINote 1 B-D B3.90 Recirc Inlet 12" 1
6R 12/8/75 4/11/06 PDI Exam 6R N2E-IR(NOte 1)
B-D B3.100 Recirc Inlet 12" 1
12/5/75 N2FNV(NOe 1)
B-D B3.90 Recirc Inlet 12" 4
6R 5/10/81 4/11/06 PDI Exam 6R 5/05/81 N2F-IR *oe B-D B3.100 Recirc Inlet 12" 4
5/12/81 N2GNVNoie 1)
B-D B3.90 Recirc Inlet 12" 2
6R 12/13/78 2/15/06 PDI Exam 6R N2G-IR (Noe 1)
B-D B3.100 Recirc Inlet 12" 2
10/8/79 N2H-NV B-D B3.90 Recirc Inlet 12" 6R 5/24/05 PDI Exam 6R N2H-IR B-D B3.100 Recirc Inlet 12" 6R 9/14/05 N2J-NVNote,)
B-D B3.90 Recirc Inlet 12" 5
6R 6/17/83 2/15/06 PDI Exam 6R 6/16/83 N2J-IR(Note I)
B-D B3.100 Recirc Inlet 12" 5
6/18/83 N2K-NV B-D B3.90 Recirc Inlet 12" 6R 5/24/05 PDI Exam 6R N2K-IR B-D B3.100 Recirc Inlet 12" 6R 9/14/05 N3A-NV B-D B3.90 Main Steam 26" 6R 9/13/05 PDI Exam 6R N3A-IR B-D B3. 100 Main Steam 26" 6R 1/10/07 N3B-NV B-D B3.90 Main Steam 26" 6R 9/19/05 PDI Exam 6R N3B-IR B-D B3.100 Main Steam 26" 6R 1/10/07 N3C-NV Note,)
B-D B3.90 Main Steam 26" 4
5/11/81 5/07/81 5/09/81 N3C-IR(Note 1)
B-D B3.100 Main Steam 26" 4
5/16/81 N3D-NV(Noie i)
B-D B3.90 Main Steam 26" 2
12/08/78 N3DIRkNoie 1)
B-D B3.100 Main Steam 26" 2
1/09/79 N5A-NV B-D B3.90 Core Spray 10" 1
12/08/78 N5A-IR B-D B3.100 Core Spray 10" 1
1/09/79 N5B-NV B-D B3.90 Core Spray 10" 5
6R 5/04/81 4/17/06 PDI Exam 6R 5/05/81 5/06/81 N5B-IR B-D B3.100 Core Spray 10" 5
5/08/81 C-1
Attachment C Unit I Applicable Nozzles (Continued)
-IR I
B-D I
B3.100 1 Jet Pump Inst 4"
16R 1 1 9/14/05 1 1
Note 1: The examination method (UT) and techniques utilized in the First Ten-Year ISI Interval documented the scan limitations on the NDE reports.
Note 2: "6R" refers to the Unit 1 restart which concluded the extended outage (1984 to 2007) for the unit.
C-2
Attachment C Unit 2 Applicable Nozzles Component ID Category Item System Nominal CYCLE DATE Comments Number Number Pipe Size N2A-NV B-D B3.90 Recirc Inlet 12" 14 3/19/07 PDI Exam N2A-IR B-D B3.100 Recirc Inlet 12" 14 3/16/07 N2BNV(Note,)
B-D B3.90 Recirc Inlet 12" 12 14 3/3/03 3/19/07 PDI Exam N2B-IR B-D B3.100 Recirc Inlet 12" 12 3/7/03 N2C-NV B-D B3.90 Recirc Inlet 12" 14 3/19/07 PDI Exam N2C-IR B-D B3.100 Recirc Inlet 12" 14 3/16/07 N2D-NV(NOte )
B-D B3.90 Recirc Inlet 12" 14 3/22/07 PDI Exam N2D-IR B-D B3.100 Recirc Inlet 12" N2E-NV B-D B3.90 N2E-IR B-D B3.100 N2F-NV B-D B3.90 Recirc Inlet 12" 12 3/3/03 PDI Exam N2F-IR B-D B3.100 Recirc Inlet 12" 12 3/7/03 N2G-NV B-D B3.90 Recirc Inlet 12" 14 3/13/07 PDI Exam N2G-IR B-D B3.100 Recirc Inlet 12" 14 3/16/07 N2H-NV B-D B3.90 Recirc Inlet 12" 14 3/20/07 PDI Exam N2H-IR B-D B3. 100 Recirc Inlet 12" 14 3/16/07 N2J-NV B-D B3.90 Recirc Inlet 12" 12 3/3/03 PDI Exam N2J-IR B-D B3.100 Recirc Inlet 12" 12 3/7/03
--N2K-NV"N°ie)
B-D B3.90 Recirc Inlet 12" 14 3/21/07 PDI Exam N2K-IR B-D B3. 100 Recirc Inlet 12" N3A-NVo°e B-D B3.90 Main 26" 14 3/22/07 PDI Exam Steam N3A-IR B-D B3.100 Main 26" Steam N3B-NV B-D B3.90 Main 26" 14 3/15/07 PDI Exam Steam N3B-IR B-D B3.100 Main 26" 14 3/16/07 Steam N3C-NV(Nole 2)
B-D B3.90 Main 26" 14 3/22/07 PDI Exam Steam N3C-IR B-D B3.100 Main 26"
/
Steam N3D-NV B-D B3.90 Main 26" 12 3/1/03 PDI Exam Steam N3D-IR B-D B3.100 Main 26"
-12 3/3/03 Steam N5A-NV B-D B3.90 Core Spray 10" 14 3/14/07 PDI Exam N5A-IR B-D B3.100 Core Spray 10" 14 3/16/07 N5B-NV B-D B3.90 Core Spray 10" 14 3/23/07 PDI Exam N5B-IR B-D B3.100 Core Spray 10" 14 3/16/07 N6A-NV B-D B3.90 Head Vent 6"
12 2/28/03 PDI Exam N6A-IR B-D B3.100 Head Vent 6"
12 3/1/03 N6B-NV B-D B3.90 Head Vent 6"
N6B-IR B-D B3.100 Head Vent 6"
N7-NV B-D B3.90 Head Vent 4"
14 3/2/07 PDI Exam N7-IR B-D B3.100 Head Vent 4"
14 3/2/07 C-3
Attachment C Unit 2 Applicable Nozzles (Continued)
Component ID Category Item System Nominal CYCLE DATE Comments Number Number Pipe Size N8A-NV B-D B3.90 Jet Pump 4"
12 3/5/03 PD1 Exam Inst N8A-IR B-D B3.100 Jet Pump 4"
12 3/7/03 Inst N8BNV No'e7 B-D B3.90 Jet Pump 4"
3/22/07 PDI Exam Inst N8B-IR B-D B3.100 Jet Pump 4"
1__ _
_Inst I
I Note 2:
RPV Nozzles; N2B-NV, N2D-NV, N2K-NV, N3A-NV, N3C-NV, and N8B-NV were expanded scope examinations for Cycle 14 due to the N9-NV failing UT examination. The N9-NV indication did not meet IWB-3500 criteria. It was determined to be a sub-surface flaw not serviced induced. The flaw was evaluated and accepted as is for continued operation.
Note:
Examinations listed for Unit 2 in this attachment are for the current Ten-Year ISI interval. Examinations for the nozzle-to-vessel welds and inner radius sections in previous ISI intervals were completed in accordance with ASME Section Xl Code requirements.
C-4
Attachment C Unit 3 Applicable Nozzles Component ID Category Item System Nominal CYCLE DATE Comments Number Number Pipe Size N2A-NV B-D B3.90 Recirc Inlet 12" N2A-IR B-D B3.100 Recirc Inlet 12" N2B-NV B-D B3.90 Recirc Inlet 12" 12 3/10/06 PDI Exam N2B-IR B-D B3.100 Recirc Inlet 12" 12 3/7/06 N2C-NV B-D B3.90 Recirc Inlet 12" N2C-IR B-D B3.100 Recirc Inlet 12" N2D-NV B-D B3.90 Recirc Inlet 12" 12 3/10/06 PDI Exam N2D-IR B-D B3.100 Recirc Inlet 12" 12 3/7/06 N2E-NV B-D B3.90 Recirc Inlet 12" N2E-IR B-D B3.100 Recirc Inlet 12" N2F-NV B-D B3.90 Recirc Inlet 12" 12 3/10/06 PDI Exam N2F-IR B-D B3.100 Recirc Inlet 12" 12 3/7/06 N2G-NV(Note j)
B-D B3.90 Recirc Inlet 12" 12
./3/7/06 PDI Exam N2G-IR(Note 3)
B-D B3.100 Recirc Inlet 12" 12 3/17/06 N2H-NV/Notei, B-D B3.90 Recirc Inlet 12" 12 3/17/06 PDI Exam N2H-IR(Nole )
B-D B3. 100 Recirc Inlet 12" 12 3/7/06 N2J-N B-D B3.90 Recirc Inlet 12" 12 3/17/06 PDI Exam N2J-IR(No te j)
B-D B3.100 Recirc Inlet 12" 12 3/7/06 N2K-NV(Nte j)
B-D B3.90 Recirc Inlet 12" 12 3/10/06 PDI Exam N2K-IR(Notea)
B-D B3.100 Recirc Inlet 12" 12 3/7/06 N3A-NV B-D B3.90 Main 26" Steam N3A-IR B-D B3.100 Main 26" Steam N3B-NV B-D B3.90 Main 26" 12 3/7/06 PDI Exam Steam N3B-IR B-D B3.100 Main 26" 12 3/7/06 Steam N3C-NVTNole 3)
B-D 63.90 Main 26" 12*
3/17/06 PDI Exam Steam N3C-IR(Note 3)
B-D B3.100 Main 26" 12*
3/7/06 Steam N3D-NV*Nte '7 B-D B3.90 Main 26" 12*
3/17/06 PDI Exam Steam N3D-IR(Note J)
B-D B3.100 Main 26" 12*
3/7/06 Steam N5A-NV B-D B3.90 Core Spray 10" 12 3/08/06 PDI Exam N5A-IR B-D B3.100 Core Spray 10" 12 3/7/06 N5B-NV B-D B3.90 Core Spray 10"1 N5B-IR B-D B3.100 Core Spray 10"1 N6A-NV B-D B3.90 Head Vent 6"
13 3/27/08 PDI Exam N6A-IR B-D B3.100 Head Vent 6"
13 3/25/08 N6B-NV B-D B3.90 Head Vent 6"
N6B-IR B-D B3.100 Head Vent 6"
C-5
Attachment C Unit 3 Applicable Nozzles (Continued)
Component Categor Item System Nominal CYCLE DATE Comments ID y
Number Pipe Size Number N7-NV B-D B3.90 Head Vent 4"
N7-IR B-D B3.100 Head Vent 4"
N8A-NV B-D B3.90 Jet Pump Inst 4"
12 3/7/06 PDI Exam N8A-IR B-D B3.100 Jet Pump Inst 4"
12 3/7/06 N8B-NV,*,te B-D B3.90 Jet Pump Inst 4"
12 3/17/06 PDI Exam N8B-IR(NoteJ)
B-D B3.100 Jet Pump Inst 4"
12 3/7/06 Note 3:
Cycle 11 RPV Nozzles: N2G-NV, N2G-IR, N2H-NV, N2H-IR, N2J-NV, N2J-IR, N2K-NV, N2K-IR, N3C-NV, N3C-IR, N3D-NV, N3D-IR, and N8B-NV, N8B-IR, were deferred to Cycle 12, 3rd Interval.
Note:
Examinations listed for Unit 3 in this attachment are for the current Ten-Year ISI interval. Examinations for the nozzle-to-vessel welds and inner radius sections in previous ISI intervals were completed in accordance with ASME Section Xl Code requirements.
C-6