|
---|
Category:Letter type:CNRO
MONTHYEARCNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00023, Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities2016-12-0101 December 2016 Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1. CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual CNRO-2015-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2015-03-27027 March 2015 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2015-00011, Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 20142015-03-27027 March 2015 Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 2014 CNRO-2014-00009, Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations2014-07-24024 July 2014 Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2014-00004, Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/20142014-04-0303 April 2014 Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/2014 CNRO-2014-00001, Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-0962014-02-26026 February 2014 Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-096 CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2013-00006, Decommissioning Funding Status Report - Entergy Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report - Entergy Operations, Inc CNRO-2013-00004, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2013-03-25025 March 2013 Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications CNRO-2012-00007, Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc2012-10-15015 October 2012 Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc CNRO-2012-00004, Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications2012-05-21021 May 2012 Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications CNRO-2011-00007, 2011 Recertification of Foreign Ownership Control or Interest2011-10-0606 October 2011 2011 Recertification of Foreign Ownership Control or Interest CNRO-2011-00005, Response to Request for Additional Information on 2011 Decommissioning Fund Status Report2011-07-0505 July 2011 Response to Request for Additional Information on 2011 Decommissioning Fund Status Report CNRO-2011-00004, Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2011-04-29029 April 2011 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00001, Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc2011-03-31031 March 2011 Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc CNRO-2011-00002, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2011-03-31031 March 2011 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2010-00002, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2010-04-29029 April 2010 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 2021-10-06
[Table view] |
Text
CORRECTED COPY: INADVERTENTLY LEFT OUT 5 PAGES OF ENCLOSURE 1.
Entergy Operations, Inc.
I 'En tergy 1340 Echelon Parkway Jackson, MS 39213-8298 Tel 601 368 5758 Michael A. Krupa Director Nuclear Safety & Licensing CNRO-2003-00047 September 25, 2003 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Operations, Inc.
Relaxation Request to NRC Order EA-03-009 for Control Element Drive Mechanism Nozzles ArkansAt Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCE:
Entergy Operations, Inc. letter CNRO-2003-00033 to the NRC, "Relaxation Request to NRC Order EA-03-009," dated August 27, 2003
Dear Sir or Madam:
In the referenced letter, Entergy Operations, Inc. (Entergy) requested relaxation from Section IV.C(1)(b) of NRC Order EA-03-009 for Arkansas Nuclear One, Unit 2 (ANO-2) via ANO-2 Relaxation Request #1 pertaining to the control element drive mechanism (CEDM) nozzles.
Since submitting Relaxation Request #1, Entergy has discovered typographical errors in the request and in the supporting Engineering Report M-EP-2003-002, Rev. 1. Specifically, Table 2 of Relaxation Request #1 was mislabeled and Figures 8 through 11 and 15 of the engineering report contained mislabeled reference lines. These corrections do not impact any technical information or conclusions of the report. A corrected table and corrected figures are provided in Enclosure 1. These supercede the previous table and figures.
In a recent telephone conversation with Entergy representatives discussing ANO-2 Relaxation Request #1, the NRC staff requested that Entergy provide information regarding the eddy current testing (ECT) instrumentation to be utilized in the augmented inspections of the CEDM nozzle blind zone area. This information is provided in Enclosure 2.
This letter contains no new commitments.
D(
CNRO-2003-00047 Page 2 of 2 If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
Sincerely, MAKIGHD/bal
Enclosure:
- 1. Corrected Table and Figures
- 2. Eddy Current Testing Instrumentation cc: Mr. C. G. Anderson (ANO)
Mr. W. A. Eaton (ECH)
Mr. G. A. Williams (ECH)
Mr. T. W. Alexion, NRR Project Manager (ANO-2)
Mr. R. L. Bywater, NRC Senior Resident Inspector (ANO)
Mr. B. S. Mallett, NRC Region IV Regional Administrator
ENCLOSURE I CNRO-2003-00047 CORRECTED TABLE AND FIGURES
TABLE 2 Industry History of Known Cracking for Heats of Alloy 600 Material Used in Combustion Engineering CEDM Nozzles Plant Nozzle Heat Form Supplier Inspection Inspection Total Number Nozzles With Function Date Type of Nozzles Cracks Plant A CEDM A6785 SB-166 Standard Steel Spring 2003 100% UT 9 1 of 9 Cracked Plant A CEDM E03045 SB-166 Standard Steel Spring 2003 100% UT 35 1 of 35 Cracked Plant B CEDM NX1045 SB-167 Huntington Alloy Not Known 100% UT 3 3 of 58 Cracked Page 20 of 29
Engineering Report M-EP-2003-002 Rev. 01 Page 17 of 62 li~~~Heei _
1 0.000 -25.088 -27.546 -27.787 -25.624 -23.763 101 0.485 -0.56305 -0.53856 -2.1108 -4.851 -6.1565 201 0.874 21.515 18.635 17.122 14.843 10.089 301 1.186 32.751 28.494 24.136 19.645 14.45 401 1.436 35.667 29.598 26.166 25.589 28.417 501 1.635 34.244 29.574 28.286 35.408 45.379 E _~~~__ _ aS2MMI 701 1.932 23.674 26.502 33.261 47.609 64.65 801 2.068 18.928 24.564 33.968 49.071 65.876 901 2.204 16.541 22.854 34.789 49.525 62.795 1001 2.341 17.561 22.683 33.806 47.49 63.558 1101 2.477 22.026 23.229 32.421 44.118 58.478 1201 2.613 26.382 25.611 31.17 41.606 52.552 1301 2.750 30.043 28.69 33.688 38.959 45.295 1401 2.886 33.132 31.073 37.166 43.676 36.261 0 ° nozzle. This nozzle is symmetric about the nozzle axis hence these Table 1: Nodal stress for stresses prevail over the entire circumference. The weld location is shown by the shaded row.
."40 k
Reference- Ln N X.'Top of ompression X4 2D 20 Zn 0 4 20 B~~~~~~~~~~~~~~~~~~
oto of Weld 00 05 ,10- 15 ' -20 25 30!i
'.-Distance from NoizleBottom (nhs Figure 8: Plot showing hoop stress distribution along tube axis for the 00 nozzle. The top of compressive zone, the reference line, and the bottom of the weld are shown.
Enile'ring Report M-EP-2003-002 Rev. 01
~~~~~~~~~~~~~~a n---
,_ aG I10
.. C7 nV 6)
If Row '4 eight ID, ~~ 5%'/.7O. >D 1 0.000 -27.404 -24.356 -22.209 -20.407 -18.978 101 0.483 0.63328 -1.486 -3.5987 -4.4402 -5.2679 201 0.870 17.665 1:16.422 14.61 12.415 9.3756 301 1.180 29.79 26.049 22.723 18.95 14.201 401 1.428 33.623 27.792 24.8 24.321 26.989 501 1.627 32.364 28.469 27.591 34.284 45.104 701 1.919 21.498 25.556 33.55 48.089 66.365 801 2.051 16.944 23.793 34.064 49.472 67.672 901 2.183 14.834 22.263 34.779 49.055 63.377 1001 2.315 15.852 21.898 33.764 46.61 61.537 1101 2.448 20.835 22.531 32.095 42.501 53.972 1201 2.580 25.973 25.072 30.748 39.365 47.486 1301 2.712 29. 955 28.372 32.593 36.879 39.934 1401 2.844 33.46 31.26 36.351 41.573 31.302 Table 2: Nodal stress for 8.8 nozzle at the downhill location. The weld location is shown by the shaded row.
I
__________ID Distribu.tion< . .. . .~zutt'L-60-- ~~~~ Ditributo
-, ~
, ; Line
_ VReference 40 ,r _,..b ..; Rg !n 4 -- ~,
.i: _t=.i->- .S:
m20-
- ';t~~~~. -.
'j-:.-. -*, -C:' t.
Top of ompeso S Zone 0
-201
.40 I -i--r' -0 Distac frmNozzle Bottm{nh)
Figure 9: Plot showing hoop stress distribution along tube axis for the 8.8° nozzle at the downhill location. The top of compressive zone, reference line, and the bottom of the weld are shown.
Engineering Report M-EP-2003-002 Rev. 01 Page 19 of 62
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
It~~~H ht= goi ... 1 5 5 'i a3 10001 0 -27.118 -24.146 -22.087 -20.358 -18.981 10101 0.48843 0.64978 -1.526 -3.6985 -4.5989 -5.4683 10201 0.87972 17.955 16.435 14.447 12.118 8.9948 10301 1.1932 29.829 26.102 22.672 18.714 13.833 10401 1.4443-- 33.679 27.823 24.722 24.104 26.541 10501 1.E<> 32.389 28.385 27.447 34.121 44.818 10701 1.9403 21.477 25.458 33.3 47.738 65.934 10801 2.074 16.919 23.701 33.846 49.217 67.244 10901 2.2076 14.769 22.095 34.557 48.869 62.964 11001 2.3413 15.756 21.725 33.561 46.369 61.153 11101 2.4749 20.717 22.317 31.908 42.308 53.889 11201 2.6085 25.789 24.923 30.579 39.284 47.365 11301 2.7422 29.737 28.248 32.847 37.236 40.412 11401 2.8758 33.001 30.843 35.887 41.552 34.5 Table 3: Nodal stress for 8. 8 nozzle at 22.50 rotatedfrom the downhill location. The weld location is shown by the shaded row.
m~oopsfress Fidt > A:.fi>t
-o- IDHo pStress 40 A'-eference L~n X~ ~ ~ ~~~~~~~~~~~~~'vi A- -'- 1',.' . ':
', , 'A a-3 0 Top opression one -]
0~~~~~~~~~~~~~~~~~~~~Bto of Weld 20 41~~~~~~~~~~~~~~
Dstane from ozzle Bottm{nh Figure 10: Plot showing hoop stress distributionalong tube axis forthe 8.80nozzle at 22.50rotated from the downhill location. The top of compressive zone, reference line, and the bottom of the weld are shown.
- ,~- i441.I t.;
Engineering Report M-EP-2003-002 Rev. 01 Page 20 of 62 20001 0 -26.311 -23.544 -21.718 -20.18 -18.943 20101 0.50592 -0.3769 -2.2224 -3.9683 -5.0362 -6.0278 20201 0.91123 20.089 16.851 14.017 11.337 7.9165 20301 1.2359 29.934 26.239 22.486 18.067 12.788 20401 1.4961 33.829 27.906 24.526 23.554 25.421 20501 1.7045 32.487 28.206 27.053 33.58 44.169 20701 2.0063 21.433 25.168 32.645 46.971 64.949 20801 2.1413 16.793 23.322 33.237 48.59 66.19 20901 2.2762 14.561 21.627 33.983 48.342 62.067 21001 2.4111 15.505 21.303 33.027 45.936 60.887 21101 2.5461 20.329 21.914 31.51 42.056 54.174 21201 2.681 25.223 24.532 30.274 39.283 47.704 21301 2.8159 29.209 27.786 32.709 37.408 41.335 21401 2.9509 32.564 30.324 35.521 41.82 35.243 Table 4: Nodal stress for 8.80 nozzle at 450 rotated from the downhill location. The weld location is shown by the shaded row.
IDH o pStress 60 - H op Stres
.OD i=_r 40~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-
~~~~~~~-',
.s_k ¢:.M re LineX !;
~,' .-0 <.O',- 5Xi w2 'nX X
-. ~~~~~~~.;,.. : i. = ..
->4 Boto of Weld:
Figure 11: Plot showing hoop stress distribution along tube axis for the 8.80 nozzle at 450 rotated from the downhill location. The top of compressive zone, reference line, and the bottom of the weld are shown.
Engineering Report M-EP-2003-002 Rev. 01 Page 24 of 62 P~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
1 0.000 -17.414 -13.552 -11.113 -8.8843 -6.6283 101 0.461 -8.4943 -6.31 -4.924 -3.7058 -2.5412 201 0.830 0.088906 0.17947 0.11003 0.18625 0.2839 301 1.126 7.0251 6.9534 6.3144 5.2078 4.6462 401 1.363 8.2154 10.954 10.85 9.5121 5.6465 501 1.552 13.266 16.41 16.061 17.131 25.256 701 1.825 29.036 28.83 31.285 53.547 64.082 801 1.946 33.945 30.929 36.407 61.6 71.01 901 2.066 29.591 31.788 40.536 64.612 76.418 1001 2.187 23.26 29.738 41.2 64.193 79.626 1101 2.308 18.689 27.734 41.29 61.777 78.117 1201 2.428 15.391 26.097 40.668 58.596 72.784 1301 2.549 14.546 24.118 39.369 54.107 62.074 1401 2.670 16.833 23.402 37.135 47.479 45.328 1501 2.790 22.94 24.557 33.686 39.867 31.733 1601 2.911 30.347 28.824 34.637 35.903 24.215 1701 3.032 36.319 33.178 37.13 37.761 22.663 1801 3.152 40.587 36.14 41.105 36.249 -4.0021 Table 8: Nodal stress for 28.80 nozzle at downhill location. The weld location is shown by the shaded row.
1 Figure 15: Plot showing hoop stress distribution along tube axis for the 28.80 nozzle at downhill location. The top of compressive zone, reference line, and the bottom of the weld are shown.
ENCLOSURE 2 CNRO-2003-00047 EDDY CURRENT TESTING INSTRUMENTATION
EDDY CURRENT TESTING INSTRUMENTATION The portions of the ANO-2 control element drive mechanism (CEDM) nozzles that will be subjected to augmented inspections are addressed in Section IV.B.2 of ANO-2 Relaxation Request #1 (Enclosure 1 of Entergy letter CNRO-2003-00033). The top of the augmented inspection zone is defined as the upper limit of the blind zone (i.e., 1.544 inches above the bottom of the nozzle). The bottom and circumferential extent of the blind zone were established by fracture mechanics analysis. The bottom of the augmented inspection zone was determined by identifying a point at the downhill (00) azimuthal location from which a crack could not propagate into the weld region within one cycle of operation. Likewise, the circumferential extent of the augmented inspection zone was determined by identifying a point along the upper limit of the blind zone from which a crack could not propagate into the weld in one cycle of operation. Based on this evaluation, the minimum augmented inspection zone boundaries were defined as shown in the table below.
CEDM Nozzle Boundary for Augmented Surface Examination Location Azimuth Top Elevation Bottom Axial Length Circumferential Location Elevation Extent 00 Downhill 1.544" 1.090" 0.454" DH +/- 1800 8.80 Downhill 1.544" 1.090" 0.454" DH +/- 67.50 28.80 Downhill 1.544" 1.224" 0.320" DH +/- 22.50 49.60 Downhill 1.544" 0.883" 0.661" DH +/- 450 Entergy intends to use the eddy current testing (ECT) method as the primary surface examination method for augmented inspections of the CEDM nozzles. Entergy recognizes the NRC staffs expectation that inspections be performed to the maximum extent possible.
Accordingly, Entergy intends to meet these expectations as described below.
ECT inspection equipment was specifically designed by Westinghouse to perform the required augmented inspections of the CEDM nozzles. The design objectives for the equipment were:
- 1. Inspection coverage bounds the portion of the blind zone identified by analysis.
- 2. The equipment can be consistently applied to all CEDM nozzle locations.
- 3. The equipment setup and operation minimizes radiation exposure.
- 4. The equipment setup and operation minimizes operator error.
The ECT inspection tool (sled) is designed with an array of transducer coils that allow a single scan to be performed without multiple setups. A one-inch scan length was chosen to envelop the areas identified by analysis (maximum axial length of 0.661 inch) and to prevent interference issues associated with the guide cones and steep angles on the outer nozzle rows. The scan length is fixed by the design of the inspection tool and the size of the ECT coil block. The position of the ECT coil block is fixed relative to the vertical axis of the nozzle.
Page 1 of 3
The ECT inspection equipment is manually installed on each CEDM nozzle and manually operated via hand cranks. The ECT equipment inspects the nozzle from 0.2 inch above to 0.8 inch below the top of blind zone. This one-inch inspection band width exceeds the requirements of the analysis. Entergy does not have any inspection equipment that is capable of inspecting below this range. In particular, while the table above indicates an axial length to be inspected ranging from 0.320 inch to 0.661 inch below the top of the blind zone, Entergy will be inspecting an axial length of 0.8 inch below the top of the blind zone.
See Figure 1 for a conceptual sketch of the ECT instrumentation and delivery system.
Page 2 of 3
FIGURE 1 ECT INSPECTION TOOL FOR CEDM NOZZLE BLIND ZONE EC Probes Dummy Array r Shoe Bottoming Spacers Tool positioned and engaged for scanning on CEDM Penetration Tool positioned and disengaged on CEDM Penetration Axial actuators engaging the EC probe array and dummy shoes (spring-type)
Page 3 of 3 Cc)!