ML17053D400
| ML17053D400 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/27/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8301030377 | |
| Download: ML17053D400 (4) | |
Text
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Docket No. 50-220 DEC 3 7 198?
Mr.
G.
K. Rhode Niagara Mohawk Power Corpora;tion 300 Eric Boulevard West
- Syracuse, New York 13202
Dear tlr. Rhode:
0 RIBUTION
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R ORB¹2 reading file c+P/Z. W. Hazelton yp]~~ lcv+ BDLiaw 3 Re,lkeo + deal> RHermann w<wgWn S. Norris his, ~c ~~Ky'/0 I Begs-l~ RE: NINE MILE POINT NUCLEAR STATION, UNIT NO. 1, NUMBER 15 NOZZLE SAFE END REPAIR On June 21, 1982 Niagara Mohawk notified the NRC staff that a miscut had occurred in the removal of recirculation safe end 15. The miscut had resulted in the removal of a portion of the Inconel buttering from the nozzle, requiring a repair prior to reinstallation of the new safe end by the methods approved previously by NRC. Yaur letter of November 18, 1982 and the supplementary information provided by a telecon on December 20, 1982, described your intended repair procedure for the number 15,,recircula00 tion nozzle. The repair procedure, in essence, is as follows: (1) Blend the miscut in the Inconel buttering. (2) Preheat the nozzle in accordance with your approved welding procedure and subsequently repair the weld in accordance with your procedure (ASHE BSPV Code,Section III, Div. 1, Article NB-2549, 1980 ed. thru Winter 1980 Addenda). (3) Maintain preheat and subsequently stress relieve in accordance with your procedure (ASHE BSPV Code,Section III, Div. 1, Article NB-4640, 1980 ed. thru Winter 1980 Addenda). (4) Machine the buttering following the heat treatment. We understand that the buttering will receive a surface examination and subsequently be radiographed prior to reinstallation of the new safe end.
- Further, we understand that the thermally induced stresses measured in the mock up test will be compared to those calculated by analysis to ensure they are within the envelope developed by jo'dr stress analysis.
From our review of the information described
- above, we find the repair procedure acceptable.
Following the completion of the repair, please provide the appropr iate documentation of the repair activity including a description and sketch of the repair, measured preheat and stress relief 830i030377 821227 PDR ADGCK 05000220 P PDR OFF1CEI SURNAME/ DATE$ NRC FORM 318 u0-80) NRCM 0240 ~ 00 ~ 0 ~ 0 ~ 0 ~ OttO ~ 0 ~ 00 ~ 0 ~ ~ ~ 0 OFFICIAL RECORD COPY ~ 0 ~ 0 ~ 0 ~ 000 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 00 ~ ~ 0 ~ 00 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 00 USCPO: 1981~960,, 0 ~c BSA fQJ .8,*'ffsiasYO ~ 1~. ':) i" >1 f4 44 fi ,t 'I ~, ~ 'r.,G. K. Rhode temperatures, a comparison of the stress results from the mock up, with those limits established by your stress analysis and a summary of diametral changes that occurred in the,'n'ozzie. Sincerely, ORIGIl/ATgszG@ZD BT Domeni c Yassal 1 o, Chi ef Operating Reactors Branch ¹2 Division of Licensing Distribution: Docket 50-220 NRC PDR. Local PDR ORB 2 Rdg D. Eisenhut OELD E. L. Jordan R. Hermann S. Norris B.D. Liau NSIC J. M. Taylor ACRS (10) OFFICE tI SURNAME/ DATE Q LA-0 B¹2:D ...RH.rr.is........ ...'j.2/>1 /82..... ORB¹2-DLQ-C-ORB¹2:DL ..P Va.as.a3.3.p.... ~.3.2/..3/A2...... ..AP.LA e.......... ..1.2/. /BR...... 4 ~ ~ ~ ~ NRG FORM 318 (10-80) NRCM 0240 OFFIClAL RECORD COPY US0 PO: 1981-999-960 t~ I