ML20079L528
| ML20079L528 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/29/1991 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20079L534 | List: |
| References | |
| NUDOCS 9111060369 | |
| Download: ML20079L528 (2) | |
Text
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l satmma pom Umsnv fs).l Md fM tr ( f'It'Pl IW W A 1)
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t,en er Vu e P'et Oe't Alill)dllli]l\\)Wer u w ce,m October 19, 1991
,3 10 CfR 50.90 Docket No.
50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Joseph H. farley Nuclear Plant - Unit 1 Sleam Generator Tube Leaktqn_ItcAnical specifica11an Gentlemen:
Inspections of the steam generators at farley Nuclear Plant (INP) Unit I have revealed the presence of circumferential1y oriented indications in the expansion transition in tubes within the sludge pile region and the U-bend region of row 1 tubes in steam generators A, B, and C.
All tubes with indications of circumferential cracks have been plugged.
- However, continued operation of Unit 1 after the discovery of the circumferential cracks is based on the implementation of a reduced steam generator primary-to-secondary limit. A conservative 140 gallons per day per steam generator leakage rate administrative limit was established for Unit 1.
Currently, Technical Specification 3.4.7.2.c allows up to 500 gallons per day through any one steam generator.
This amendment request reduces the technical specification primary-to-!econdary leakage litrit to 140 gallons per day per steam generator, or 420 g:111ons per day through all three steam generators.
The proposed changed pages to Unit 1 Technical Specifications are provided in Attachment 1.
It should be noted that these changed pages are based on the current technical specifications and not the proposed changes to implement the stean, generrtor tube support plate alternate plugging criteria which were forwarded by letter dated February 26, 1991.
Alabama Power Company has determined the proposed changes do not involve a significant hazards consideration.
In accordance with 10 CFR 50.92, a significant hazards evaluation is provided in Attachment 2.
Alabama Power Company's Plant Operations Review Committee has reviewed the proposed changes and Nuclear Operation Resiew Board will review the changes at a future meeting. A copy of this proposed change is being 'ent to Dr.
C. E. Fox, the Alabama State Designee, in accordance with 10 CFR 50.91(b)(1).
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4 U. S. Nuclear Regulatory Commission Page 2 If there are any questions, please advise.
Respectfully submitted.
ALABAMA POWER COMPAllY
. $a hd th W. G. llairston, Ill WGH, lil/ REM: map 0758 SWORil TO Af10 SUBSCRIBED BEFORE ME Attachments THI519hDAYOF[g/glga_,1991 cc:
Mr. S. D. El' noter hjs[/
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'it Hr. G. f. Maxwell
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u Dr. C. E. Fox My Commission Expires:
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