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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-21-0905, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R292022-01-26026 January 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R29 NL-19-1491, Update to the Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval2019-12-0909 December 2019 Update to the Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval NL-19-0726, Inservice Inspection Program Owner'S Activity Report for Outage 2R252019-06-17017 June 2019 Inservice Inspection Program Owner'S Activity Report for Outage 2R25 NL-19-0317, Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update2019-04-0202 April 2019 Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update NL-17-1194, Submittal of Response to Request for Information Fourth Interval Relief Requests RR-13, RR-14, RR-18, RR19, RR-23, and RR-242017-07-10010 July 2017 Submittal of Response to Request for Information Fourth Interval Relief Requests RR-13, RR-14, RR-18, RR19, RR-23, and RR-24 NL-17-0951, Inservice Inspection Program, Owner'S Activity Report for Outage 2R242017-05-30030 May 2017 Inservice Inspection Program, Owner'S Activity Report for Outage 2R24 NL-16-2707, Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707)2016-12-27027 December 2016 Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707) ND-16-1437, Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval2016-08-24024 August 2016 Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval NL-16-0795, Inservice Inspection Program - Owner'S Activity Report for Outage IR272016-06-0101 June 2016 Inservice Inspection Program - Owner'S Activity Report for Outage IR27 NL-16-0421, Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems, Nondestructive Examination Results - Spring 2016 Outage (1R27)2016-03-17017 March 2016 Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems, Nondestructive Examination Results - Spring 2016 Outage (1R27) NL-15-1096, Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-06-18018 June 2015 Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-15-1032, E. I. Hatch, Unit 2 - Inservice Inspection Program Owner'S Activity Report for Outage 2R232015-06-12012 June 2015 E. I. Hatch, Unit 2 - Inservice Inspection Program Owner'S Activity Report for Outage 2R23 NL-15-0784, Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-05-0404 May 2015 Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-14-1821, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information2014-11-13013 November 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information NL-14-1276, Snubber Inspection Plan Submittal in Accordance with ASME OM Code2014-10-31031 October 2014 Snubber Inspection Plan Submittal in Accordance with ASME OM Code NL-14-1250, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.02014-09-19019 September 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 NL-14-0840, Lnservice Inspection Program Owner'S Activity Report for Outage 1R262014-06-0303 June 2014 Lnservice Inspection Program Owner'S Activity Report for Outage 1R26 NL-14-0231, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 1.02014-03-0606 March 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 1.0 NL-12-1266, Inservice Inspection Program, Owner'S Activity Report for Outage 1R252012-06-14014 June 2012 Inservice Inspection Program, Owner'S Activity Report for Outage 1R25 NL-10-0989, Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Requests2010-07-0808 July 2010 Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Requests NL-10-1023, Inservice Inspection Program, Owner'S Activity Report for Outage 1R242010-06-11011 June 2010 Inservice Inspection Program, Owner'S Activity Report for Outage 1R24 NL-08-1798, Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-012008-12-19019 December 2008 Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-01 NL-08-0901, Unit 1, Inservice Inspection Program Owner'S Activity Report for Outage 1R23 and Structural Integrity Design Report for the N9 CRD Nozzle-to-Cap Full Structural Weld Overlay2008-06-13013 June 2008 Unit 1, Inservice Inspection Program Owner'S Activity Report for Outage 1R23 and Structural Integrity Design Report for the N9 CRD Nozzle-to-Cap Full Structural Weld Overlay NL-07-0987, Fourth Interval Inspection (ISI) Plan Correction2007-05-0909 May 2007 Fourth Interval Inspection (ISI) Plan Correction NL-07-0802, Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests2007-04-13013 April 2007 Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests ML0704300922006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 1, Revision 2, Introduction Fourth Ten-Year Examination Plan. ML0704301002006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 3, Revision 1.0, Class 1, 2 and 3 Figures Fourth Ten-Year Inservice Inspection Plan. ML0704300942006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 2, Revision 1, Class 1, 2 and 3 Components Fourth Ten-Year Examination Plan. ML0704301012006-08-10010 August 2006 E. I. Hatch, Unit 2, Version 1.0, Pressure Test Section Fourth Ten-Year Examination Plan. NL-06-1358, Inservice Inspection Program, Owner'S Activity Report for Outage 1R222006-06-29029 June 2006 Inservice Inspection Program, Owner'S Activity Report for Outage 1R22 ML0704300812006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 1, Revision 1, Introduction Fourth Ten-Year Inservice Inspection Plan. ML0704300832006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 2, Revision 1, Class 1, 2 and 3 Components Fourth Ten-Year Inservice Inspection Plan. ML0704300872006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 3, Revision 1, Class 1, 2 and 3 Figures, Fourth Ten-Year Inservice Inspection Plan. ML0704300962005-08-31031 August 2005 E. I. Hatch, Unit 1, Version 1.0, Pressure Test Section Fourth Ten-Year Examination Plan. NL-05-1190, Fourth 10-Year Interval Inservice Testing (Ist)Program Updates Submittal for Edwin I. Hatch Nuclear Plant2005-07-11011 July 2005 Fourth 10-Year Interval Inservice Testing (Ist)Program Updates Submittal for Edwin I. Hatch Nuclear Plant ML0516403852005-06-0707 June 2005 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report NL-04-0813, Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report2004-06-0707 June 2004 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report NL-04-0478, Third 10-Year Interval Inservice Inspection Program Submittal of Relief Requests (RR) RR-38, RR-39, and RR-402004-03-29029 March 2004 Third 10-Year Interval Inservice Inspection Program Submittal of Relief Requests (RR) RR-38, RR-39, and RR-40 NL-03-1380, Third 10-Year Interval Inservice Testing Program, Submittal of Relief Requests RR-V-182003-07-11011 July 2003 Third 10-Year Interval Inservice Testing Program, Submittal of Relief Requests RR-V-18 ML0230903562002-11-0101 November 2002 Third 10-Year Interval Inservice Inspection (ISI) Program, Revision of Relief Request RR-11 ML0228200262002-10-0404 October 2002 Third 10-Year Interval Inservice Inspection Program, Response to Request for Additional Information (RAI) ML0226604362002-09-17017 September 2002 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report 2024-07-09
[Table view] Category:Letter type:NL
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Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 3521]1-1295 Tel 205.992.5000 SOUIHERNA COMPANY December 19, Energy to Serve )'our World'" Docket No.: NL-08-1798 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant -Unit Fourth 10-Year Intervallnservice Inspection Submittal of Relief Request Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(g}(5}(iii}, Southern Nuclear Operating Company hereby submits the enclosed relief request for the Hatch Nuclear Plant -Unit 1, Fourth 10-Year Intervallnservice Inspection Program. This relief request is needed due to impracticality where there is reasonable assurance of structural integrity.
The relief is requested to be approved by December 31, 2009. This letter contains no NRC commitments.
If you have any questions, please advise. Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJA/MNW/daj
Enclosure:
RR-01, Hatch -Unit 1, Reactor Pressure Vessel Longitudinal Welds Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President
-Hatch Mr. D. H. Jones, Vice President
-Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatorv Mr. L. A. Reyes, Regional Mr. R. E. Martin, NRR Project Manager -Mr. J. A. Hickey, Senior Resident Inspector
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Edwin I. Hatch Nuclear Plant -Unit Relief Request RR-01, Reactor Pressure Vessel Longitudinal SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR Plant Unit: Interval Dates: Requested Date for Approval and Basis: ASMECode Components Affected:
Applicable Code Edition and Addenda: Applicable Code Requirements:
Impracticality of Compliance:
Burden Caused by Compliance:
Fourth Interval RR-Ol, Version 1.0 Plant -Hatch Unit 1. 4th lSI Interval -December 31,2005 through December 31,2015. Approval is requested by December 31, 2009 Class 1, ASME Section XI Category B-A, Item Number B 1.12 reactor pressure vessel (RPV) longitudinal welds as shown in Table 1. ASME Section XI, 2001 Edition with 2003 addenda. Examination Category B-A, Table IWB-2500-1 of the 2001 Edition with 2003 addenda of the ASME Section XI Code requires a volumetric examination.
The examinations were performed from the inside of the reactor vessel using automated tooling. The examination volumes are shown in ASME Section XI Figures IWB-2500-2 and include essentially 100% of the weld length. Physical obstruction of some examination surfaces due to permanently attached equipment adjacent to the examination areas caused restricted coverage of the examination volume as required by Figure IWB-2500-2.
Nine of the eleven weld examinations were affected.
The nine welds with limitations are described in Table RR-01-1 and the obstructions are depicted in Figures 01-01 through RR-01-09.
Compliance would require removal of the permanently attached adjacent structures located inside the reactor vessel to achieve a complete examination.
Page 1 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED REUEF REQUEST IN ACCORDANCE WITH 10 CFR Proposed Alternative and Basis for Use: Duration of Proposed Relief Request: Precedents:
References:
Status: Fourth Interval RR*01, Version 1.0 Volumetric examinations for the 4 th Inspection Interval were performed on the Hatch-1 RPV longitudinal welds using a newly developed scanning tool. The tool scans from the inside surface of the reactor vessel and provided greatly improved coverage of the welds located in the high fluence areas of the beltline region and similar composite coverage of welds not in the beltline region when compared to the previous examination.
The previous interval examination coincided with RPV insulation replacement and some of the scanning was performed from the vessel exterior.
All examinations performed during the 4 th interval were done from the vessel interior.
Coverage for the higher fluence welds (C-3-A, C-3-B, C-3-C, C-4-A, C-4-B, and C-4-C) was an average of approximately 80%. This coverage, in addition to the coverage obtained for lower fluence welds C-2-A, C-2-B, and C-2-C, provides reasonable assurance of structural integrity of these welds. Therefore, relief should be granted per 10 CFR 50.55a(g)(6)(i).
The proposed relief request is applicable for the Hatch Unit 14th Inspection Interval.
The physical limitations described in this relief request are similar to Hatch-1 for the 3rd lSI interval which was approved by the NRC on March 11, 1999. The ultrasonic examinations performed for the 4 th interval under this relief request contained an overall higher composite coverage and significantly greater coverage in the beltline region of the RPV, including the previously inaccessible weld C-4-B. The NRC SER TAC No. for the 3rd interval "Edwin I. Hatch Nuclear Plant Unit 1-relief request for authorization to alternative reactor pressure vessel examination for circumferential welds" is (MB3843).
Awaiting NRC approval.
Page 2 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR Fourth Interval RR-01, Version Class 1 Vessel Table Weld Identification No. Description Limitation Coverage Examination Results Weld C-2-A o degree Az. Site Elevation 189' 7" to 189' 7" Reactor Vessel Longitudinal Weld Non-beltline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by the Upper guide rod located at 0 degrees, feed water spargers and core spray piping. See Figure RR-01-01 for depiction of obstructions.
12.3% No Recordable Indications Weld C-2-B 120 degree Az Site Elevation 177' 1" to 189' 7" Reactor Vessel Longitudinal Weld Non-beltllne region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by feed water spargers and core spray piping. See Figure RR-01-02 for depiction of obstructions.
77.3% No Recordable Indications Weld C-2-C 240 degree Az Site Elevation 177' 1" to 189'. 7" Reactor Vessel Longitudinal Weld Non-beltline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by feed water spargers and core spray piping. See Figure RR-01-03 for depiction of obstructions.
78.4% No Recordable Indications Weld C-3-A 30 degree Az Site Elevation 164' 6" to 177' 1" Reactor Vessel Longitudinal Weld I Located in beltline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by specimen brackets and jet pump riser braces. See Figure RR-01-04 for depiction of obstructions.
69.3% No Recordable Indications Weld C-3-B 150 degree Az Site Elevation 164' 6" to 177' 1") Reactor Vessel Longitudinal Weld Located In beilline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by jet pump riser braces. See Figure RR-01-05 for depiction of obstructions.
90.0% No Recordable Indications.
Page 3 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR Fourth Interval RR-01. Version Class 1 Vessel Welds Table RR*01*1 (continued)
Identification No.1 Exam. History Description limitation Coverage Examination Results Weld C-3-C 270 degree Az Site Elevation 164' 6" to 177' 1") Reactor Vessel Longitudinal Weld Located in beltline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by jet pump riser braces. See Figure RR-01-06 for depiction of obstructions.
83.0% No Recordable Indications.
Weld C-4-A 18 degree Az Site Elevation 152' 1" to 164' 6") Reactor Vessel Longitudinal Weld Located in belthne region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by gusset plates. See Figure 07 for depiction of obstructions.
82.3% No Recordable Indications Weld C-4-B 138 degree Az Site Elevation 152' 1" to 164' 6 n ) Reactor Vessel Longitudinal Weld Located in beltline region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by gusset plates and shroud repair hardware.
See Figure RR-Ol-09 for depiction of obstructions 71.5% No Recordable Indications.
Weld CA-C 258 degree Az Site Elevation 152' 1" to 164' 6") Reactor Vessel Longitudinal Weld Located in belt line region Limited UT examination coverage due to adjacent permanently mounted equipment in the reactor vessel. Obstructions are caused by gusset plates. See Figure 10 for depiction of obstructions.
82.3% No Recordable Indications.
Page 4 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
Fourth Interval RR-01, Version 1.0 C-2
- n I I J> c .0" Sketch of obstructions for Hatch 1 RPV longitudinal weld C-2-A (as viewed from vessel inside diameter)
Figure RR-01-01 Page 5 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR Fourth Interval RR-01, Version Sketch of obstructions for Hatch 1 RPV longitudinal weld C-2-B (as viewed from vessel inside diameter)
Figure RR-01-02 Page 6 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR SO.SSa(g)(S){iii)
Fourth Interval RR-01, Version 1.0 Sketch of obstructions for Hatch 1 RPV longitudinal weld C-2-C (as viewed from vessel inside diameter)
Figure RR-01-03 Page 7 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
Fourth Interval RR-01, Version 1.0 n o ON 30' Sketch of obstructions for Hatch 1 RPV longitudinal weld C-3-A (as viewed from vessel inside diameter)
Figure RR-01-04 Page 8 of 13 SOUTHERN NUCLEAR OP RATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR SO.SSa(g)(S)(iii)
Fourth Interval RR*01, Version 1.0 -3 .0 W I Cd Sketch of obstructions for Hatch 1 RPV longitudinal weld C-3-B (as viewed from vessel inside diameter)
Figure RR-01-05 Page 9 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
Fourth Interval RR-01, Version 1.0 C-3 3 O' 578 N j n Sketch of obstructions for Hatch 1 RPV longitudinal weld C-3-C (as viewed from vessel inside diameter)
Figure RR-01-06 Page to of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR SO.SSa(g)(S)(iii)
Fourth Interval RR-01, Version 1.0 Sketch of obstructions for Hatch 1 RPV longitudinal weld C-4-A (as viewed from vessel inside diameter)
Figure RR-01-07 Page J 1 of 13 SOUTHERN NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5}(iii}
Fourth Interval RR-01, Version 1.0 Sketch of obstructions for Hatch 1 RPV longitudinal weld C-4-B (as viewed from vessel inside diameter)
Figure RR-01-08 Page 12 of 13 SOUTHER NUCLEAR OPERATING PROPOSED RELIEF REQUEST IN ACCORDANCE WI H 10 CFR SO.SSa(g)(S)(iii)
Fourth Interval RR-01, Version 1.0 =--C 4 2 c J I -II :+ I J - . [ ] -.LU ,.V Sketch of obstructions for Hatch 1 RPV longitudinal weld C-4-C (as viewed from vessel inside diameter)
Figure RR-01-09 Page 13 of 13