ML20132C519
| ML20132C519 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/17/1985 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20132C522 | List: |
| References | |
| 2113N, 55236, NED-85-664, TAC-55236, NUDOCS 8509270078 | |
| Download: ML20132C519 (2) | |
Text
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Gecno<a Po^er Cerrpany 333 Pedmcrt Avenue At'.inta. Georg.a 30308 TeW.hcre 404 506 0526 M Mg Akim".
Post GM ce Po 4545 A!'arta G9g:a 30%2 L
Georgia Power L.T.Gucwa
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Mrager tu c u Erg.reer:ng it'd (.J eef I4UCIWI f ny COff NED-85-664 2113N September 17, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FINAL DESIGN REPORT - RECIRCULATION AND RHR SYSTEMS ANALYSES AND REPAIRS Gentlemen:
By letter dated December 10, 1984, Georgia Power Company submitted l
information regarding thE. analyses and repairs of Recirculation (Recirc)
System and Residual Heat Removal (RHR) System piping welds which were inspected during the 1984 Hatch Unit 1 maintenance / refueling outage and found to have unacceptable flaw indications.
Included as Enclosure 2 to that submittal was Revision A of NUTECH report no. XGP-09-106, " Design Report For Evaluation And Disposition Of IGSCC Flaws At Plant E.
I.
Hatch Unit 1."
The subject NUTECH repor t was provided in preliminary draft form as discussed in the aforementioned letter.
Since our submittal of December 10, 1984, NUTECH has issued the final design report.
Enclosed herein are ten (10) copies of Revision 0 of NUTECH report no.
XGP-09-106.
The enclosed NUTECH report supercedes the preliminary draft version submitted as Enclosure 2 to our December 10, 1984 letter.
Some of the major differences between Revision 0 of the NUTECH design report and the preliminary draft version include:
1 Weld overlay as-built dimensions (Table 2.1).
o Weld overlay configuration drawings provided for new and existing o
overlays (Figures 2.1 through 2.7).
Code stress results (Tables 5.1 though 5.5).
o 8509270078 050917 PDR ADOCK 05000321 p
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e Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 September 17, 1985 Page Two o
Weld stress information for 1984 analyses (Table 5.6).
o Weld overlay induced shrinkage stresses (Table 5.7).
o Low toughness material concerns discussion.
The overall conclusions of the adequacy of the repairs, etc. reached in your letters dated January 3, 1985 and February 14, 1985 relative to the inspections of Recirc and RHR piping and resultant corrective actions taken during the 1984 Hatch Unit 1 maintenance / refueling outage are not changed as a result of the enclosed final NUTECH design report.
Submittal of the enclosed final design report should complete all necessary submittals to NRC relative to piping inspections and repairs during the subject outage.
By copy of this letter, a copy of the final NUTECH design report is being supplied to NRC Region II for their review.
Should you have any questions in this regard, please contact this office.
Sincerely yours, L. T. Gucwa JAE/mb Enclosures (10) xc:
(All w/l encl.)
J. T. Beckham, Jr.
I H. C. Nix, Jr.
J. N. Grace (NRC Region II)
Senior Resident Inspector 3
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