ML20205T217
| ML20205T217 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/09/1986 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205T219 | List: |
| References | |
| NUDOCS 8606130077 | |
| Download: ML20205T217 (4) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (ass)ess. sono
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June 9, 1986
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Docket No. 50-278 Mr. Daniel R. Muller, Director BWR Project Directorate #2 Division of Bolling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Peach Bottom Atomic Power Station - Unit 3 Plans for Mid-Cycle Examination of Five Welds References (1) Letter, S. L. Daltroff, PECo, to J. F.cStolz, USNRC, Dated January 7, 1986 (2) Letter, D. R. Muller, USNRC, to E. G. Bauer, PECo, Dated March 20, 1986 (Confirmatory Orders)
Dear Mr,
Muller:
In the reference (1) letter, Philadelphia Electric Company (PECo) proposed to submit, within 90 days of returning Unit 3 to service, plans for a mid-cycle examination of certain safe ends and pipe welds.
This proposal was found acceptable to NRC as indicated in the Confirmatory Orders transmitted to PECo its the reference (2) letter.
This letter fulfills our commitment and conforms to the Confirmacory Orders.
The following welds are scheduled for ultrasonic examination during the Unit 3 mid-cycle inspection outage:
O W r.t._D DESCRIPTION
,gg S8' 2-AS-8
'A' Recirculation Suction Line - Elbow to Valve og 2-BD-12
'B' Recirculation Discharge Line - Pipe to Valve
$a 10-0-3 RHR Shutdown Cooling Suction Line - Elbow to Pipe 2-AHP-TS Recirculation Inlet Nozzle Safe End gu 2-AHJ-TS Recirculation Inlet Nozzle Safe End c0 C4 (Refer to Attachments 1 and 2 for weld locations)
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Mr. D2niG1 R. MullGr June 9, 1986 Page 2 The acceptance flaw sizes (in terms of percent of wall thickness) for continued operation without further evaluation or repair are defined in the table below and are associated with inspections performed after a nine month period.
The flaw sizes are based on conservative crack growth predictions.
The limits ensure that the required structural margins are maintained for the remainder of the Unit 3 operating cycle.
MID - CYCLE LIMITS ON DEPTHS PELD AVERAGE MAXIMUM 2-AS-8 30%
50%
2-BD-12 30%
45%
10-0-3 42%
42%
2-AHP-TS 24%
46%
2-AHJ-TS 27%
50%
If the mid-cycle UT flaw sizes exceed the above limits, a detailed evaluation will be performed and submitted to the NRC for review prior to reactor startup.
If the mid-cycle UT flaw sizes do not exceed the above limits, it is proposed that Unit 3 be permitted to return to service for the remainder of its fuel cycle.
Technical justification for these flaw size acceptance limits is provided in the attached document (Attachment 3),
developed by General Electric Company, titled " Acceptance Criteria for the Mid-Cycle Inspection of the Peach Bottom 3 Recirculation Inlet Safe Ends and Piping".
The results of the mid-cycle inspections will be provided to the NRC for staff review within 30 days of completion of the examinations.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, M 'W 4
cc:
Dr. T. E. Murley, Administrator, Region I, USNRC T. P. Johnson, Resident Site Inspector
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