NL-06-0309, NRC First Revised Order EA-03-009: Revised Relaxation Request for Inspection of IP3 Reactor Pressure Vessel Head
| ML060960068 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/15/2006 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-03-009, NL-06-0309 | |
| Download: ML060960068 (9) | |
Text
`~v Entergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSE.
P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration March 15, 2006 NL-06-030 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001
SUBJECT:
Indian Point Nuclear Generating Unit 3 Docket No. 50-286 NRC First Revised Order EA-03-009: Revised Relaxation Reque t for Inspection of IP3 Reactor Pressure Vessel Head
REFERENCES:
- 1. NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for ReactDr Pressure Vessel Heads at Pressurized Water Reactors", dated February 20, 2004
- 2. Entergy letter NL-05-040, "NRC First Revised Order EA 009, Revised Relaxation Request for Inspection of IP3 Reactor Pressure Vessel Head", dated March 30, 2005
- 3. Entergy letter NL-05-043, "NRC First Revised Order EA 009, Revised Relaxation Request for Inspection of IP3 Reactor Pressure Vessel Head - Supplemental Information", dated April 1, 2005
- 4. Entergy letter NL-04-060, 'NRC First Revised Order EA-03-009, Relaxation Requests for Inspection of Reactor Pressure Vessel Heads", dated May 19, 2004
Dear Sir:
Entergy Nuclear Operations, Inc (Entergy) is submitting a revised relaxation request pertaining to inspection of the Indian Point Nuclear Generating Unit 3 (IP3) Reactor Pressure Vessel (RPV) head in accordance with NRC First Revised Order EA-03-009 (Reference 1). The affected relaxation request is Reference 2, as supplemented by Reference 3. The relaxation
NL-06-.030 Docket 50-286 Page 2 of 2 request concerns non-destructive examination (NDE) of the nozzle region below the J-groove weld. Due to the physical dimensions of the nozzles and the presence of a threaded region at the bo1:tom of the nozzles, relaxation is needed regarding the requirement in NRC First Revised Order EA-03-009, section IV.C.5(b). Entergy is requesting that the relaxation be applicable to those penetrations with inspection coverage of less than 1 inch below the J-groove weld as specified in Attachment 1. Note that the previously approved relaxation request regarding extent of coverage for the bare metal visual examination of the RPV head (Reference 4) remains in effect.
A response to this relaxation request is needed by February 1, 2007 to support the IP3 refueling outage planned for Spring 2007. Commitment NL-05-040-1 previously made within Reference 2 remains unchanged (see Attachment 2). No new commitments are being made in this letter. If you have any questions or require additional information, please contact Mr. Patric W. Conroy at 914-7:34-6668.
Sin Iy Fred R. Dacimo Site Vice President Indian Point Energy Center Attachment I (Revised Relaxation Request For IP3 Regarding Ultrasonic and Eddy Current Testing of Reactor Pressure Vessel Head Nozzles in Accordance with First Revised NRC Order EA-03-009,Section IV.F.) (List of Commitments) cc:
Mr. John P. Boska, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 3 Nuclear Power Plant U.S. Nuclear Regulatory Commission Mr. Paul Eddy New York State Public Service Commission to NL-06..030 Docket 50-286 Page 1 of 6 ATTACHMENT I TO NL-06-030 REVISED RELAXATION REQUEST FOR IP3 REGARDING ULTRASONIC AND EDDY CURRENT TESTING OF REACTOR PRESSURE VESSEL HEAD NOZZLES IN ACCORDANCE WITH FIRST REVISED NRC ORDER EA-03-009. SECTION IV.F.
A. ASME COMPONENTS AFFECTED Component Number: B4.12
==
Description:==
Reactor Pressure Vessel (RPV) Head Penetration Nozzles Code Class:
1 B. REQUIREMENTS OF FIRST REVISED NRC ORDER EA-03-009 Section IV.C.5(b)(i) of the Revised Order (Reference 1) requires ultrasonic testing (UT) of the RPV head penetration nozzle volume (i.e., nozzle base material) from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld... OR 1.0 inch below the lowest point at the toe of the J-groove weld... including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level (including all residual and normal operating stresses) of 20 ksi tension or greater.
Section IV.C.5(b)(ii) of the Revised Order (Reference 1) provides an option to perform eddy current testing (ECT) or dye penetrant testing (PT) of the entire wetted surface of the J-groove weld and the wetted surface of the RPV head penetration nozzle base material from at least 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld... OR 1.0 inch below the lowest point at the toe of the J-groove weld... including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level (including all residual and normal operating stresses) of 20 ksi tension or greater.
C. PROPOSED ALTERNATIVE Entergy Indian Point 3 will perform UT from the inside surface of each RPV head penetration nozzle (i.e., nozzle base material) from 2 inches above the J-groove weld and extending down the nozzle to at least the top of the threaded region or further down the threaded region to the extent allowed by technology and geometry, but in all cases achieving the minimum requirements specified in Table 1. Although not presently planned, Entergy to NL-06-030 Docket 50-286 Page 2 of 6 may choose to perform ECT in lieu of UT of the wetted surface excluding any threaded suifaces and the chamfer region in selected nozzles. If ECT is performed, the minimum requirements of Table 1 will apply. The 3R14 refueling outage is currently scheduled for March, 2007. The next non-visual NDE inspection of the RPV head is currently planned for the spring of 2009 during 3R15. Indian Point 3 is a high susceptibility category plant.
D. REASON FOR RELAXATION REQUEST The proposed alternative provides an acceptable level of quality and safety.
E. JUSTIFICATION Th.e design of the RPV head penetration nozzles (see Figure 1-1) includes a threaded section, approximately 3/4 inches long, at the bottom of the nozzles. The dimensional configuration at some nozzles is such that the inspectable distance from the lowest point of the toe of the J-groove weld to the bottom of the scanned region is less than the 1 -inch lower boundary limit specified in Section IV.C.5(b) of the First Revised Order. Review of previous NDE data shows that in some cases I" coverage cannot be achieved. Entergy will attempt to maximize coverage to comply with the First Revised NRC Order (Ref.1).
u rfrom the inside surface of the threaded region of the nozzle is partially achievable by new vendor scanning techniques. ECT probes are not capable of examining the threaded surfaces.
Although dye penetrant testing (PT) of threaded surfaces is possible, it would require that personnel be located under the RPV head to manually perform the surface cleaning and penetrant testing operations, resulting in significant personnel radiation exposure. Based on previous IP2 experience, a PT of a weld performed under the RPV head on an indication would result in a person rem exposure of approximately 1.7 REM. Therefore, UT from -the inside surface of the threaded region of the nozzle is the primary method at 1P3 to remotrly inspect the portion of the nozzle below the J-groove weld to minimize radiation exposure to inspection personnel.
Entergy performed stress analysis and crack growth evaluations for postulated through-wall axial flaws extending upwards from the nozzle towards the lower J-groove weld. The time to reach the lowest point at the toe of the J-groove weld is greater than 2 EFPY (Table 1) based on a minimum inspection coverage below the J-groove weld.
The performed stress analysis consisted of a three-dimensional elastic-plastic finite element analysis that considered all the pertinent loadings on the penetrations. The three-dimensional finite element model comprised of iso-parametric brick and wedge elements was used to obtain the stresses.
The penetration nozzle, weld metal, cladding and the vessel head were modeled in accordance with the relevant material properties. The most important loading conditions were to NL-06-030 Docket 50-286 Page 3 of 6 found to be those which normally exist on the penetration nozzle in the majority of cases.
These loadings included pressure and temperature loading associated with the steady state operation condition. In addition, the residual stresses resulting from the weld fabrication process were also considered.
The crack growth evaluation for a hypothetical flaw used the MRP-55 recommended PWSCC crack growth rate taking into account a head temperature of 595.3° F. Entergy recognizes that the NRC staff has not yet made a final determination on the acceptability of MRP-55. Should the staff determine the crack growth formula used by Entergy is unacceptable, Entergy will revise the analysis that justifies relaxation of the First Revised Order within 30 days after the NRC advises Entergy of an NRC approved crack growth formula. If the revised analysis shows that the crack growth acceptance criteria are exceeded prior to the end of the then current operating cycle, this relaxation will be considered rescinded and written justification for continued operation shall be submitted to the NRC within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the revised analysis shows that the crack growth acceptance criteria are exceeded during the subsequent operating cycle, Entergy will submit the revised analysis for NRC review within 30 days. If the revised analysis shows that the crack growth acceptance criteria are not exceeded during the current operating cycle or the next operating cycle, Entergy shall confirm that the analysis was performed in a letter to the NRC within 30 days.
Any crack growth analyses performed for RPV head inspections after the NRC advises Entergy of an NRC approved crack growth formula shall use that formula.
The service life required for any of the upper crack tips to reach the lowest point of the toe of the J-groove weld all exceeded 2 EFPY. The time duration between inspection cycles is 2 years in accordance with the NRC First Revised Order for high category plants. Therefore, as a screening rule, if inspection coverage of Table 1 is achieved below the J-groove weld on the downhill side of all the head penetration nozzles in 3R14, the upper crack tip of any undetected axial through-wall flaw in the region not being inspected is not expected to reach th-lowest point of the toe of the J-groove weld in less than 2 EFPY, or before the subsequent 31R15 nozzle inspection. Consequently, the intent of the requirements in the NRC First Revised Order is met.
F. DURATION OF RELAXATION Entergy requests relaxation of this requirement for all nozzle inspections to be performed in 3R14 and in future outages in accordance with the Order EA-03-009.
G. ATTACHMENTS TO RELAXATION REQUEST Table 1: IP3 RPV Head Penetrations - Minimum Coverage Requirements Below J-Groove Weld Figure 1-1: IP3 RPV Head Penetrations - Nozzle Weld Detail to NL-06-030 Docket 50-286 Page 4 of 6 H. REFERENCES
- 1. NRC Letter dated February 20, 2004, "Issuance of First Revised NRC Order (EA 009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors"
- 2.
Westinghouse Letter dated November 2005, "Technical Justification to Support Submittal of Relaxation Request from NRC Order EA-03-009 for Indian Point Units 2 and 3"
Attachment I to NL 030 Docket 50-286 Page 5 of 6 TABLE 1 IP3 RPV Head Penetrations - Minimum Coverage Requirements Below J-Groove Weld Nozzle Angle of Incidence ("
Minimum Required UT Coverage Below J-Time (EFPY)
Penetration (Degrees)
Groove Weld with > 2 EFPY by Crack to Reach the No.
Growth Evaluation (Inches)
Lowest Poirt of the Toe cf the J-Groova Weld I through 29 0 to 24.8 0.4 3.0 30 through 69 26.2 to 38.6 0.4 2.7 70 through 73 44.3 0.3 3.0 74 through 78 48.7 0.3 4.4 Note:
(1) Length below the lowest point at the toe of the J-groove weld (downhill side) that has an operating stress level of 20 ksi: 0.86 inches at nozzles 1 through 29; 0.50 inches at nozzles 30 through 69; 0.35 inches at nozzles 70 through 73 and 0.35 inches at nozzles 74 through 78.
to NL-06-030 Docket 50-286 Page 6 of 6 FIGURE 1-1 IP3 RPV Head Penetrations - Nozzle Weld Detail JGROOVK WELD reference datum - bottom of J-groove weld threaded region z
approximatelY 0.75' Ijchamfer region (appro): 0.25 ')
to NL-06-030 Docket 50-286 Page 1 of I List of Commitments Number Commitment NL-05-040-1 Entergy recognizes that the NRC staff has not yet made a final determination on the acceptability of MRP-55. Should the staff detennine the crack growth formula used by Entergy is unacceptable, Entergy will revise the analysis that justifies relaxation of the First Revised Order within 30 days after the NRC advises Entergy of an NRC approved crack growth formula. If the revised analysis shows that the crack growth acceptance criteria are exceeded prior to the end of the then current operating cycle, this relaxation will be considered rescinded and written justification for continued operation shall be submitted to the NRC within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the revised analysis shows that the crack growth acceptance criteria are exceeded during the subsequent operating cycle, Entergy will submit the revised analysis for NRC review within 30 days.
If the revised analysis shows that the crack growth acceptance criteria are not exceeded during the current operating cycle or the next operating cycle, Entergy shall confirm that the analysis was performed in a letter to the NRC within 30 days. Any crack growth analyses performed for RPV head inspections after the NRC advises Entergy of an NRC approved crack growth formula shall use that formula.