ML20205F156
| ML20205F156 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/08/1986 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 1964K, NUDOCS 8608190104 | |
| Download: ML20205F156 (2) | |
Text
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Commonweetth Edison 4
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Chicago, Illinois 60690 - 0767 August 8, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC.
20555
Subject:
Braidwood Station Unit 1 Preservice Inspection NRC Docket No. 50-456
Reference:
(a)
July 17, 1985 A.D. Miosi letter to H.R. Denton (b)
July 31, 1986 A.D. Miosi letter to H.R. Denton
Dear Mr. Denton:
This letter provides information regarding the Braidwood Unit 1 Preservice Inspection.
The PSI Program for Braidwood Unit 1 consists of a tabular listing of Class 1, 2,
and 3 components requiring inspection in a manner consistent with the Section XI examination tables, a series of notes and relief requests, and a listing of exempted components.
The Braidwood Unit 1 PSI Program was submitted to the NRC, Reference (a).
Only the differences between the Braidwood Unit 1 and Byron Unit 1 Programs are included in this submittal.
The scope and requirements of the Braidwood Unit 1 PSI Program are identical to that of Byron Unit 1.
Inspections were performed to the requirements of ASME Code Section XI 1977 Edition with addenda through the Summer, 1978 Addenda, inclusive.
In addition to the Code required inspections, augmented inspections were performed on high energy lines and reactor coolant pump flywheels.
Volumetric, surface, and visual examinations were performed on Braidwood Unit 1 components per Code or augmented requirements by Commonwealth Edison or other personnel.
The automated ultrasonic examination of the Braidwood Unit 1 reactor vessel was performed by Combustion Engineering to the requirements of NRC Regulatory Guide 1.150.
The eddy current examination of the Braidwood steam generator tubing was performed by Conam Inspection.
100% of the tubes in the four steam generator received examination.
In June 1984, Commonwealth Edison received approval to utilize ASME Code Case N-401 which allowed the use of the ZETEC Model MIZ-18 instrument (records digitized data on magnetic tape).
The Byron Unit 1 steam generator tubing was examined by Ebasco with MIZ-12 equipment.
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t o Ultrasonic examinations of the cast stainless steel elbow and component welds in the Braidwood Unit 1 reactor coolant system have recently been completed.
By performing tests on calibration standards and weld samples, Commonwealth Edison has demonstrated that these examinations are capable of detecting large flaws in the cast material.
Ultrasonic scans on the non-cast sides of the Braidwood reactor coolant system were also performed.
Only the non-cast sides of the Byron Unit 1 reactor coolant system welds were examined.
Six (6) notes and fifteen (15) relief requests are included in the Program.
The discussion between these items and the Byron notes and relief requests were discussed in the submittal per reference (b).
Relief Requests 1NR-2, INR-5, INR-6, and 1NR-7 address the cast stainless steel examinations and are scheduled to be submitted by September 1, 1986.
Braidwood Unit 1 components exempted from preservice examinations per Section XI paragraphs IWB-1220 and IWC-1220 and Table IWD-2500-1 correspond directly to the Byron Unit 1 exempted components.
Please direct any questions you or your staff may have regarding this matter to this office.
One signed original and fifteen copies of this transmittal and the attachments are provided for NRC review.
Very truly yours, A. D. Miosi Nuclear Licensing Administrator
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cc:
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