ML20044G918
| ML20044G918 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/24/1993 |
| From: | Chandu Patel Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| GL-88-01, GL-88-1, TAC-M86334, NUDOCS 9306070032 | |
| Download: ML20044G918 (3) | |
Text
May 24, 1993 o
m Docket No. 50-265 DISTRIBUTION:
- Docket File:
NRC & Local PDRs PDIII-2 r/f Mr. D. L. Farrar
,J.LRue "
J. Zwolinski Manager, Nuclear Regulatory Services J. Dyer C. Moore Commonwealth Edison Company C. Patel OGC Executive Towers West III, Suite 500 ACRS (10)
B. Clayton RIII 1400 OPUS P1 ace Downers Grove, Illinois 60515
Dear Mr. Farrar:
SUBJECT:
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) WELD DVERLAY REPAIR OF A RECIRCULATION SYSTEM RISER FOR QUAD CITIES STATION, UNIT 2 (TAC NO. M86334)
Your letter dated April 30, 1993, provided the results of the ultrasonic examinations performed during the current refueling outage (Q2RI2) for Quad Cities Station, Unit 2.
Your letter also provided design and evaluation criteria for the weld overlay repairs which were applied, and requested the staff's approval for the weld overlay repair on IGSCC flaw in a twelve-inch recirculation system riser weld 02C-F7 in accordance with Generic Letter (GL) 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping."
Based on the preliminary review of your submittal, the staff has determined that the weld overlay repairs meet the guidelines in GL 88-01. On the basis of this review, the staff has concluded that Quad Cities Station, Unit 2 can be safely returned to operation for at least one fuel cycle with assurance that the integrity of the reactor coolant pressure boundary will be maintained. Our detailed safety evaluation will be provided under separate cover.
You should report the effect of shrinkage on the piping system, including pipe supports and whip restraints, and evaluate the increase of deadweight and stiffness resulting frem the overlay to be in conformance with the supplement to the GL.
You should also report the as-built thickness and the delta ferrite content of the overlay.
You are requested to provide this information within 90 days after the completion of the current Quad Cities Unit 2 outage.
Sincerely, Olijnd Sierd By:
Chandu P. Patel, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc:
See next page
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NAME lCt400RE lCFATEL lJDYER lJSTROSt@ER l
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DATE j f /,2g9g g g l 5 7,2493 iS 1
9306070032 930524
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s' May 24, 1993.
l i
Docket No. 50-265 DISTRIBUTION:
Docket File NRC & Local PDRs PDIII-2 r/f l
Mr. D. L. Farrar J. Roe J. Zwolinski Manager, Nuclear Regulatory Services J. Dyer:
-C. Moore Commonwealth Edison Company C. Patel OGC Executive Towers West-III, Suite 500 ACRS (10)
B. Clayton RIII I400 OPUS P1 ace Downers Grove, Illinois 605I5, i
Dear Mr. Farrar:
5
SUBJECT:
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) WELD'0VERLAY REPAIR OF A RECIRCULATION SYSTEM RISER FOR QUAD CITIES STATION, UNIT 2 (TAC NO. M86334)
Your letter dated April 30, 1993, provided the results of the ultrasonic examinations performed during the current refueling outage (Q2RI2) for Quad Cities Station, Unit 2.
Your letter also provided design and evaluation.
criteria for the weld overlay repairs which were applied, and requested the i
staff's approval for the weld overlay repair on IGSCC flaw in a twelve-inch recirculation system riser weld 02C-F7 in accordance with Generic letter (GL) 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel' Piping."
Based on the preliminary review of your submittal, the staff has determined-that the weld overlay repairs meet the guidelines in GL 88-01. On the basis.
of this review, the staff has concluded that Quad Cities Station, Unit _2 can be safely returned to operation for at least one fuel cycle.with~ assurance that the integrity of the reactor coolant pressure boundary will be maintained. Our detailed safety ' evaluation will be 'provided under separate 3
- cover, i
You should report the effect of shrinkage on the' piping system, including pipe j
supports and whip restraints, and evaluate the increase _ of deadweight and stiffness resulting from the overlay to be in conformance with the supplement l
to the GL.
You should also report the as-built thickness and the delta ferrite content of the overlay.
You are requested to provide this.information within 90 days after the completion of the current Quad Cities Unit'2 outage.
Sincerely, i
On p -' e ---l;,.
Chandu P. Patef, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc:
See next page
-n 0FC lLA:PDIII-2 lPM:PDIII-2 lD:PDII -2 lBC:EMCB ((/f l
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~"i>J t NAME_ lCM00RE lCPATEL lJDYER lJSTROSypER l
DATE j f /24/93 l 5~7 2493 l 5 /893 l g/y4 /93 l
4 l
Mr. D. L. Farrar Quad Cities Nuclear Power Station Commonwealth Edison Company Unit Nos. I and 2 CC:
l Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and j
Electric Company P. O. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza l
Chicago, Illinois 60690 Mr. Richard Bax l
Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Illinois Department of Nuclear Safety l
Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 l
Glen Ellyn, Illinois 60137
)
Robert Neumann l
Office of Public Counsel L
State of Illinois Center l
100 W. Randolph Suite 11-300 Chicago, Illinois 60601 l