View source for NL-08-1798, Edwin I. Hatch, Unit 1 - Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-01

{{Adams
| number = ML083570437
| issue date = 12/19/2008
| title = Edwin I. Hatch, Unit 1 - Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-01
| author name = Ajluni M J
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000321
| license number = DPR-057
| contact person = 
| case reference number = NL-08-1798
| document type = Inservice/Preservice Inspection and Test Report, Letter type:NL
| page count = 15
| project = 
| stage = Other
}}

=Text=
{{#Wiki_filter: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 
-
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}}