View source for HL-1778, Forwards Owners Data Rept (NIS-1) for Inservice Insp, Ei Hatch Nuclear Plant Unit 2,Dec 1989-June 1991. No Reportable Indications Detected in Seven Welds in nonsafety- Related RWCU Sys,Per Generic Ltr 88-01

{{Adams
| number = ML20082L943
| issue date = 08/30/1991
| title = Forwards Owners Data Rept (NIS-1) for Inservice Insp, Ei Hatch Nuclear Plant Unit 2,Dec 1989-June 1991. No Reportable Indications Detected in Seven Welds in nonsafety- Related RWCU Sys,Per Generic Ltr 88-01
| author name = Beckham J
| author affiliation = GEORGIA POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000366
| license number = 
| contact person = 
| document report number = GL-88-01, GL-88-1, HL-1778, NUDOCS 9109040480
| package number = ML20082L947
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 3
}}

=Text=
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Mi!'.7" '',. m                                                           l'C"'gia IWer s .s:        t HL-1778 002060 August 30, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 205$5 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 INSERVICE INSPECTION ASSOCIATED WITH THE SPRING 192LtB1NTENANCE/REFULLING OUTAE Gentlemen:
Pursuant to the requirements of Article IWA-6000 of the ASHE Code, Section XI, enclosed for your review is the Owner's Data Report for Inservice Inspection (form NIS-1) for the inservice inspection activities conducted            at    Plant    Hatch   Unit   2    during   the    Spring     1991 maintenance / refueling outage.
Georgia Power Company has also aerformed ultrasonic examinations of austenitic steel piping welds in tie primary coolant pressure boundary per Generic Letter 88-01               and NUREG 0313,     Revision 2. Results are presented in Enclosure 1              under " Class 1 Components." As a result of these inspections,            one 12" feedwater weld was determined to contain reportable indications. A detailed report of the flaw evaluation and weld overlay design was provided to the NRC in Reference 1, and the NRC acceptance of the weld repair was provided in Reference 2.
Based on commitments to the NRC related to Generic Letter 88-01, seven (7) welds in the non-safety reiated portion of the reactor water cleanup (RWCU) system were ultrasonically examined.                    No reportable indications were detected in these welds. Georgia Power Company also submitted a temporary relief request from ASME Section XI, IWA-5250 related to minor leakage in the primary containment coolers in Unit 2.
This relief was granted by the NRC in Reference 3.
Georgia Power Company performs many augmented inspections which are not specifically required by the ASME Section XI Code.                 The results of these inspections are described in the NIS-1 report. In addition to the IGSCC inspections (primary pressure boundary and non-safety RWCU piping) discussed above, GPC performed the following:
9109040480 9i0930 PDR Q
ADOCK 05000366 PDR                                                                 \

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( scolgia l'0Wel U.S. Nuclear Regulatory Commission Au r,u s t 30, 1991 Page lwo l
o    The core spray sparger and associated piping was visually examined per Bulletin 80-13. No reportable indications were detected, o Ultrasonic thickness measurements were performed on selected components in the extraction steam and condensate /feedwater system pighg per GPC's ongoing erosion / corrosion program, o Eddy current examinations were performed on several feedwater heaters, main generator stator water coolers, one reactor building chiller,     two turbine building chillers, three emergency diesel generator jacket water coolers, lube oil coolers, and air coolers, if you have any questions in this regard, please contact this office at any time.
l                                                                                        Sincerely, Q-y/ LIE,x:
[/J.T.Beckham,Jr
{               GKM/cr 002060

==Enclosure:==

Owner's Data Report for Inservice inspection -
Edwin 1. Hatch Nuclear Plant Unit 2 February 1991 - June 1991

==References:==
: 1. Letter, J. T. Beckham to NRC, "lGSCC Flaw Evaluations and Weld Overlay Design - Unit 2 Spring 1991 Maintenance / Refueling Outage," HL-1636 dated May 20, 1991.
: 2. Letter, K. N. Jabbour to W. G. Hairston, III,
                              " Evaluation of Indications in Feedwater Weld 2B21-lFW-12AA Hatch Nuclear Plant Unit 2,"
dated May 24, 1991.
: 3. Letter, D. B. Mathews to W. G. Hairston, 111
                              " Requested Relief from ASME Boiler and Pressure Vessel Code Requirement - Containment Cooling Units' Leakage," dated May 24, 1991.
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U.S. Nuclear Regulatory Commission August 30, 1991 Page Three cc: GC.Drg10 Power _lpf_ RAM Mr. H. L. Sumner, General Manager - Nuclear Plant NORMS NgIJrgr Requlatory Commissigh_ h shinoton. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch V.S. Nuc1 ear _J[tgulA12rX_f9m iSJ h n Mr. S. D. Lbneter, Regional Administrator Mr. L. D. Wert, Senior Resident - Hatch l
l HL-1778 700775
_ _ . _ _ , _ . _}}