ML20155G778

Forwards Rev 2 to SIR-86-002, Evaluation of IGSCC Flaw Indications & Weld Overlay Designs for Ei Hatch Unit 1-Fall 1985/86 Maint/Refueling Outage, Final Design Rept for Stainless Steel Piping & Components

ML20155G778
Person / Time
Site:	Hatch
Issue date:	05/02/1986
From:	Gucwa L GEORGIA POWER CO.
To:	Muller D Office of Nuclear Reactor Regulation
Shared Package
ML20155G784	List: ML20155G778 ML20155G798
References
03694, 3694, SL-569, NUDOCS 8605070126
Download: ML20155G778 (3)

Text

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Georg a Fbwer Comreny

. 333 P+ecmont Avenue * *

- AUanta, Georgia 30308 '

Telephone 404 526-6526 Maang Ack2 rest Pbst Office Bex 4545 Attanta, Georga 30302 GeorgiaPower

' ""**W^"

uaIa"g7deciear sa.ety SL-569 ano ucens,ng 0369H May 2, 1986 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project' Directorate No. 2

• Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Comission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REPORT CLARIFICATION AND SUBMITTAL OF REVISED DESIGN REPORT FOR CLASS 1 STAINLESS STEEL PIPING AND COMPONENT 5 - 1985 MAINTENANCE / REFUELING OUTAGE Gentlemen:

Enclosed herein for NRC review is Revision 2 to the Structural Integrity Associates (SIA)-prepared report SIR-86-002 originally submitted by Georgia Power Company (GPC) letter SL-461, dated March 10, 1986. Revision 2 of the SIA report supercedes Revision 0 provided in the aforementioned submittal and constitutes the final design report for repairs and analyses of stainless steel piping and components conducted during the Hatch Unit 1 1985 maintenance / refueling outage. A revision (i.e., Revision 1) to the SIA report was issued to GPC for review and comments after Revision 0 of the SIA report was submitted to the NRC.

Revision 1 of the SIA report was not submitted to the NRC, since it was an intermediate version of the report and did not constitute the final design report. The conclusions reached in our -

submittal of March 10, 1986, remain unchanged as a result of Revision 2 of the SIA report. While the revision of the design report was issued primarily to incorporate editorial changes, the SIA report was also revised to address items not previously discussed in Revision 0 of the SIA design report; for example, the IHSI of the 28" Recircul6 tion System safe end-to-nozzle welds and disposition of welding flaws observed in the weld overlay for RHR piping weld IEll-lRHR-24B-R-12. These items were discussed in our meeting with NRC staff at your offices in Bethesda, Maryland, on Tuesday, March 18, 1986. Revised sections of the design report are noted in the " Revision Control Sheet" included therein.

8605070126 860502 .

PDR ADOCK 05000321'

• k P pon if

Georgia Power b Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 May 2,.1986 Page Two In addition to the submittal of Revision 2 of the SIA design report, enclosed is revised Figure 7.1 which supercedes the subject figure included in our March 10, 1986, submittal. Figure 7.1 depicts the "A" loop of the Recirculation and RHR systems. The notation for weld number 2 on Recirculation riser 12AR-J was inadvertently omitted from the subject figure-in the aforementioned submittal. Please be advised that weld 12AR-J-2 was treated with IHSI during the outage. The post-IHSI ultrasonic examination indicated that the weld was free of reportable indications.

We wish to clarify a note in the legend for Figure 7.3 in the March 10, 1986, submittal. The subject figure depicts the Class 1 .RWCU- System stainless steel piping. The note under the legend for that particular figure indicates that piping welds not denoted by a symbol were treated with IHSI. While weld numbers 158 and 15C are specifically noted in Figure 7.3 as being inaccessible, the note in the legend implies that these welds were treated with IHSI, since they were not denoted by one of the symbols shown therein. Welds 158 and 15C were not treated with IHSI, since they are inaccessible due to their location within RWCU piping penetration ' X-14.

These welds were addressed in the aforementioned meeting with NRC staff, and it was specifically indicated that welds ISB and 15C were not treated with IHSI due to their inaccessibility. We apologize for any confusion that the note in Figure 7.3 may have caused relative to RWCU piping welds 158 and 15C.

Seven copies of this letter and enclosures are provided for your convenience.

Should you have any questions in this regard, please contact this office at any time.

Sincerely yours,

/7~ & :

L. T. Gucwa JAE/ht Enclosures

.: Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.

Mr. H. C. Nix, Jr.

Dr. J. N. Grace (NRC-Region II) (4 copies)

Senior Resident Inspector GO-NORMS 700775

~

' FIGURE 7,1 ,

"A" Ioop - Recirculation & N Attached Systems g '

.i J 11 F {

K 3 3 5 5 f c

ft M$ h~?? h 2 ifb  ?

Y (Typ.-5 places) h h h 1 3BC-1 ,

[

1BC-2m _, ,

+ 1B31-1RC-28A (-[ t -

~ " > ,

b I

f i-,y I 2f l

i

~

v ,_

' ' J .

16 __r 1g11_

[ -- +SA A F060A 22R{ 15 f '

12 14 if *

[j,8 -1 Ell-1RHR-24A-R g e, g 4A-10A' 7

pgp / 12CEO 1B31- 14 _.... .

C001A 4A-1A Weld overlays from urevious outages 1 14BC Welds renaired by DISI dur-

, , , F031A N/ , ing 1985 outage

+ #

-( ' Weld overlays apolied dur-1B31

[

\'

F023A q j~ *  :' 11BC h

- 13 ing 1985 outage'due to re-pairs or to facilitate in-

j 12 _

spection i = j'

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Note:' Welds not denoted by one of 7

8 1 9j the above symbols were treated by IHSI

-