Letter Sequence RAI |
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TAC:MD2587, (Open) TAC:MD2588, (Open) TAC:MD2589, (Open) TAC:MD2590, (Open) TAC:MD2591, (Open) TAC:MD2597, (Open) TAC:MD2609, (Open) TAC:MD2610, (Open) TAC:MD2611, (Open) TAC:MD2613, (Open) |
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MONTHYEARML0704001462007-02-27027 February 2007 RAI for the Third 10-Year Interval Inservice Inspection Program, Relief Nos. RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, and RR-62 (TAC Nos. MD2587 Through MD2591, MD2597 and MD2609, MD2610 and MD2611) Project stage: RAI ML0713602972007-06-0505 June 2007 Relief, Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Request to Relief Nos. RR-42 Through RR-45, RR- 51, RR-58, RR-59, RR-60, & RR-62 Project stage: Other 2007-02-27
[Table View] |
RAI for the Third 10-Year Interval Inservice Inspection Program, Relief Nos. RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, and RR-62 (TAC Nos. MD2587 Through MD2591, MD2597 and MD2609, MD2610 and MD2611)ML070400146 |
Person / Time |
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Site: |
Hatch ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
02/27/2007 |
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From: |
Martin R NRC/NRR/ADRO/DORL/LPLII-1 |
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To: |
Madison D Southern Nuclear Operating Co |
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Martin R, NRR/DORL, 415-1493 |
References |
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TAC MD2587, TAC MD2588, TAC MD2589, TAC MD2590, TAC MD2591, TAC MD2597, TAC MD2609, TAC MD2610, TAC MD2611, TAC MD2613 |
Download: ML070400146 (7) |
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Text
February 27, 2007Mr. Dennis R. MadisonVice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, REQUEST FORADDITIONAL INFORMATION (RAI) FOR THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF NOS.
RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, AND RR-62 (TAC NOS. MD2587, MD2588, MD2589, MD2590, MD2591, MD2597, MD2609, MD2610, MD2611, AND MD2613)
Dear Mr. Madison:
The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated theinformation provided by Southern Nuclear Operating Company, Inc (the licensee), in its letter dated July 10, 2006, which proposed its Third 10-year Interval Inservice Inspection Program Plan Requests for Relief Nos. RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, and RR-62 for Edwin I. Hatch Nuclear Plant, Units 1 and 2. To maintain the schedule for our review, it is requested that additional information, as described in the enclosure, be provided by April 13, 2007. Please contact me if you have any questions regarding this correspondence. Sincerely,/RA/Robert E. Martin, Senior Project ManagerPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-321 and 50-366
Enclosure:
RAI cc w/encl: See next page February 27, 2007Mr. Dennis R. MadisonVice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, REQUEST FORADDITIONAL INFORMATION (RAI) FOR THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF NOS.
RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, AND RR-62 (TAC NOS. MD2587, MD2588, MD2589, MD2590, MD2591, MD2597, MD2609, MD2610, MD2611, AND MD2613)
Dear Mr. Madison:
The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated theinformation provided by Southern Nuclear Operating Company, Inc (the licensee), in its letter dated July 10, 2006, which proposed its Third 10-year Interval Inservice Inspection Program Plan Requests for Relief Nos. RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60, and RR-62 for Edwin I. Hatch Nuclear Plant, Units 1 and 2. To maintain the schedule for our review, it is requested that additional information, as described in the enclosure, be provided by April 13, 2007. Please contact me if you have any questions regarding this correspondence. Sincerely,/RA/Robert E. Martin, Senior Project ManagerPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-321 and 50-366 cc w/encl: See next pageDistribution:Public PD2-1 R/F RidsNrrDorlLpl2-1(EMarinos)RidsNrrLAO'BrienRidsNrrPMRMartinRidsOgcRp RidsAcrsMailCenterRidsRgn2MailCenter(SShaeffer)
RidsNrrDciCvib(TMcLellan)RidsNrrDciCvib(MMitchell)Accession No.: ML0704200146 OFFICENRR/LPL2-1/PMNRR/LPL2-1/LANRR/LPL2-1/BCNAMERMartin:nc MO'BrienEMarinos DATE 2/26/07 2/26/07 2/27/07OFFICIAL RECORD COPY EnclosureREQUEST FOR ADDITIONAL INFORMATIONREGARDING THIRD 10-YEAR INSERVICE INSPECTION INTERVALREQUEST FOR RELIEF NOS. RR-42, RR-43, RR-44, RR-45, RR-51,RR-58, RR-59, RR-60, AND RR-62EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2SOUTHERN NUCLEAR OPERATING COMPANY, INCDOCKET NOS. 50-321 AND 50-366Requests for Relief (RR) Nos. RR-42, RR-43, RR-44, RR-45, RR-51, RR-58, RR-59, RR-60,and RR-62 are for the third 10-year inservice inspection (ISI) interval, in which Edwin I. Hatch Nuclear Plant (Hatch), Units 1 and 2, adopted the 1989 edition with no addenda of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code)
,Section XI, as the ASME Code of record. In its letter dated July 10, 2006, Southern Nuclear Operating Company, Inc. (the licensee), requested relief from certain ASME Code,Section XI requirements.RR-42 and RR-43For RR-42, the licensee requested relief from the volumetric examination requirements inASME Code,Section XI, Category B-A, Item B1.21 and Item B1.22 for Hatch Unit 1 reactor pressure vessel (RPV) bottom head meridional welds BHD-A through F and circumferential weld C. For RR-43, the licensee requested relief from the volumetric examination requirements inASME Code,Section XI, Category B-A, Item B1.21 and Item B1.22 for Hatch Unit 2 RPV bottom head dome meridional welds 2BHD-A through D and bottom head torus meridional welds 2BHT-A through G. The ASME Code,Section XI, Table IWB-2500-1, Category B-A, Item B1.21 and B1.22 requiresa volumetric examination of essentially 100 percent of the accessible length of all welds on thesubject RPV bottom head. According to the information provided by the licensee in its letter dated July 10, 2006, thelicensee was unable to obtain any volumetric coverage on Hatch Unit 1 RPV bottom head dome meridional welds 2BHD-A through D and circumferential weld C due to the RPV support skirt causing the subject welds to be inaccessible for examination. For Hatch Unit 1, the licensee examined bottom head meridional welds BHT-A, BHT-B, BHT-C, BHT-D, BHT-E, BHT-F, BHT-G, and BHT-H, and bottom head circumferential weld C-7 in 2006 and the licensee obtained 100-percent coverage for each weld. The licensee detected no indications during these examinations. For Hatch Unit 2, the licensee found the examinations to be limited for bottom head domemeridional welds 2BHD-A through D and bottom head torus meridional welds 2BHT-A through G due to the control rod drives that penetrate the bottom head near the welds and the RPV support skirt interfering with the examinations. The licensee obtained 27 percent to 28 percent of the length of welds bottom head dome meridional welds 2BHD-A through D. In addition, the 1.Tables RR-44-1, RR-44-2, and RR-51-1 are not included in this request for additional information and canbe found in the licensee's letter dated July 10, 2006.licensee obtained 88 percent of the length of each weld for the bottom head torus meridionalwelds 2BHT-A through G. The licensee detected no indications during these examinations.
For this particular ASME Code,Section XI, Examination Category B-A and Item Numbers B1.21 and B1.22, the ASME Code specifically states examination is of the accessible weldlength. Therefore, the licensee should consider reassessing the ASME Code requirements in that if the licensee actually obtained essentially 100 percent of the accessible weld length, thenrelief may not be required. RR-44The licensee requested relief from the volumetric examination requirements in ASME Code,Section XI, Table IWB-2500-1, Category B-D, Item B3.90 for nozzle-to-vessel welds listed in the licensee's Tables RR-44-1 1 and RR-44-2 1 for Hatch Units 1 and 2, respectively.1.Provide drawings or sketches of the ASME Code,Section XI, Category B-D componentslisted in Tables RR-44-1 and RR-44-2 for Hatch Units 1 and 2, respectively. Drawings or sketches of every component are not required. An example of one each type of similar component will satisfy this request. 2.For the nozzles listed in Tables RR-44-1 and RR-44-2, identify which nozzle belongs towhich vessel.3.Clarify if the examinations of the nozzles listed in Tables RR-44-1 and RR-44-2 wereperformed from the inside or the outside of the nozzles.4.Clarify which ASME Code edition and addenda was used regarding the PerformanceDemonstration Initiative examination techniques. 5.Describe the plant's leakage and radiation monitor systems with regard identifyingleakage from the subject welds. Also, describe when VT-2 visual examinations were last performed on the subject welds.RR-45The licensee requested relief from the surface examination requirements in ASME Code,Section XI, Code Case N-509, Category B-K, Item B10.10 for Hatch Unit 2 RPV stabilizer brackets SB1 through SB6.Provide drawings of the RPV stabilizer brackets.
RR-51The licensee requested relief from the volumetric examination requirements in ASME Code,Section XI, IWB-2500-1, Category B-A, Item B1.12 for RPV longitudinal welds, shown in the licensee's Table RR-51-1 1 for Hatch Unit 1. 1.Provide drawings or sketches of the ASME Code,Section XI, Category B-A, Item B1.12 components listed in Table RR-51-1 for Hatch Unit 1. 2.Describe the plant's leakage and radiation monitor systems with regard to identifyingleakage from the subject welds. Also, describe when VT-2 visual examinations were last performed on the subject welds. 3. For weld C-4-B, has the licensee considered VT-1 visual examination by remote cameraor any other type of visual examinations of the subject weld as an alternative to the ASME Code volumetric examinations if they can not be performed in February 2008?4.Has the licensee considered examining weld C-4-B from the inside of the RPV if at anytime there is a core off load and dismantling of internal components for Hatch Unit 1?5.In RR-51 the licensee erroneously stated that the ASME Code requirements for ASMECode,Section XI, Table IWB-2500-1, Examination Category B-A, Item B1.12 requires that 100 percent of the accessible length of each weld be examined. Note 2 of theASME Code,Section XI, Table IWB-2500-1, Examination Category B-A, Item B1.12 requires that essentially 100 percent of the weld length is to be examined, not the
accessible length. Please correct this error in RR-51.RR-58, RR-59, RR-60, and RR-62 In RR-58 for Hatch Unit 1, the licensee requested relief from the volumetric examinationrequirements in ASME Code,Section XI, IWC-2500-1, Category C-B, Item C2.21 for residual heat removal (RHR) exchanger weld 1E11-2HX-B-O. In RR-59 for Hatch Unit 1, the licensee requested relief from the volumetric examinationrequirements in ASME Code,Section XI, IWC-2500-1, Category C-B, Item C2.21 for RHR heat exchanger weld 2E11-2HX-A-O.In RR-60 for Hatch Unit 2, the licensee requested relief from the volumetric examinationrequirements in ASME Code,Section XI, IWC-2500-1, Category C-A, Item C1.20 for RHR heat exchanger weld 2E11-2HX-A-3. In RR-62 for Hatch Unit 2, the licensee requested relief from the volumetric examinationrequirements in ASME Code,Section XI, IWB-IWC-2500-1, Category C-A, Item C1.10 for RHR heat exchanger weld 2E11-2HX-A-2.RR-58, RR-59, RR-60, and RR-62
- 1.Provide drawings or sketches of the RHR heat exchanger welds for Hatch Units 1 and 2. 2.Identify the materials (both base material and weld material) by material specificationassociated with the welds in these RRs. Discus how the materials properties and/or nozzle geometry hindered the volumetric examinations. 3.Describe the plant's leakage and radiation monitor systems with respect to identifyingleakage from the welds. Also, describe when VT-2 visual examinations were last performed on the subject welds.4.For ASME Code,Section XI, Category C-B, Item Number C2.21 where both avolumetric and surface examination are required, please provide the coverage obtained for the surface examinations.
Edwin I. Hatch Nuclear Plant, Unit Nos. 1 & 2 cc:
Laurence BergenOglethorpe Power Corporation 2100 E. Exchange Place P.O. Box 1349 Tucker, GA 30085-1349Mr. R. D. BakerManager - Licensing Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295Resident InspectorPlant Hatch 11030 Hatch Parkway N.
Baxley, GA 31531Harold Reheis, DirectorDepartment of Natural Resources 205 Butler Street, SE., Suite 1252 Atlanta, GA 30334Steven M. JacksonSenior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684Mr. Reece McAlisterExecutive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334Arthur H. Domby, Esq.Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216ChairmanAppling County Commissioners County Courthouse Baxley, GA 31513Mr. Jeffrey T. GasserExecutive Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295Mr. K. RosanskiResident Manager Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant P.O. Box 2010 Baxley, GA 31515