ML20134P480
| ML20134P480 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/30/1985 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Farrar B COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8509060327 | |
| Download: ML20134P480 (4) | |
Text
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Docket No.: STN 50-454 AUG 3 01985 Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
Subject:
Emergency Relief Request Safety Injection System Class 2 Welds -
Byron Station, Unit 1 By letter dated August 29, 1985, Commonwealth Edison Company requested an emergency relief from Section 11 of the ASME Code concerning preservice inspection requirements. Relief was requested from performing the required volumetric and surface examinations for two Class 2 circumferential welds in the Safety Injection System (weld number C-1; line numbers ISIO6BA-24" and 1SI0608-24").
The evaluation and justification provided in your submittal has been reviewed and found acceptable. This letter confirms the verbal granting of a temporary waiver of compliance with the ASME Code preservice inspection requirements which was given at 9:00 p.m. on August 29, 1985. This waiver of compliance is in effect until 9:00 p.m. on September 3,1985, by which time the NRC will complete the processing of your emergency relief request.
Sincerely, MGDiA.L SIGIO BY:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing
Enclosure:
nMTRIBUTION:
CECO Emergency Relief Request (Docket File 3 L01shan NHL,PDR OELD cc: See next page LPDR ACRS (16)
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Mr. Dennis L. Farrar Byron Station AUG 3 0 1985 Commonwealth Edison Company Units 1 and 2 cc:
Mr. William Kortier Ms. Diane Chavez Atomic Power Distribution 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III U. S. Nuclear Regulatory Connission Michael Miller 799 Roosevelt Road Isham, Lincoln & Beale Glen Ellyn, Illinois 60137 One First National Plaza 42nd Floor Joseph Gallo, Esq.
Chicago, Illinois 60603 Isham, Lincoln & Beale Suite 840 Mrs. Phillip B. Johnson 1120 Connecticut Avenue, N.W.
1907 Stratford Lane Washington, D. C.
20036 Rockford, Illinois 61107 Douglass Cassel, Esq.
Dr. Bruce von Zellen 109 N. Dearborn Strcet Department of Biological Sciences Suite 1300 Northern Illinois University Chicago, Illinois 60602 DeKalb, Illinois 61107 Ms. Pat Morrison Mr. Edward R. Crass 5568 Thunderidge Drive Nuclear Safeguards & Licensing Rockford, Illinois 61107 Sargent & Lundy Engineers 55 East Monroe Street Ms. Lorraine Creek Chicago, Illinois 60603 Rt. 1, Box 182 Manteno Illinois 60950 Mr. Julian Hinds U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Offices 4448 German Church Road Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive Springfield, Illinois 62704
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/ Ch;eago, lilinois 60890 8/29/85 To: Jan Stevens NRC Byron Unit 1 Relief Request
, Examination Category C-F, Class 2 Welds in the Safety Injection Systems Line Number Weld Number 1 SIO6BA-24" C-1 1 SIO6BB-24" C-1 Code Reauirements: The subject Class 2 circumferential welds at structural discontinuities require volumetric and surface exaninations in accordance with TABLE IWC-2500-1 (Category C-F) Items C5.21.
Code Relief Request: Relief is requested from performing the required vomeuac ano surTace examination on inaccessible welds.
Reason for Request: The above listed welds are inaccessible for volumetric ano surface examinations due to the Iccation of the valve containment assemblies covering the pressure retaining pipe welas. The welds were to be examined per code requirements as part of the preservice inspection program. However, the Applicant inadvertently performed the required examination with acceptable results on the non-pressure-retaining welc between the closure plete of containment assembly and the pipe.
Examination of the pressure retaining weld requires removal of the valve containment assembly without a significant increase in the level of safety. The Applicant will commit to performing volumetric and surface examinations on the pressure-retaining pipe weld upon the initial removal of the valve containment assemblies.
Justification:
1.
The pressure-retaining pipe circumferential welds received radiographic volumetric examination in accordance with ASME Code Section III, Class 2 requirements during fabrication.
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The required Section X1 examinations are impossible without removal the valve containment asseeblies. Removal of the containment assetrblies would result in hardship or unusual difficulties including plant shutdown without a compensating increase in the level of quality and safety since the radiography performed during construction on the pipe welds verify the preservice structural integrity.
3.
Leakage from' the valve containment assemblies is continually monitored by a leak detection device measuring water level inside the assemblies. Hiti Water level is annunciated in tne resin control room assuring prompt operator action in the I
event of an abnormal condition. Leakage from the asse.tlies l
2 is piped to the Auxiliary Building floor drain sump to avoid l
1eakage to the plant environment.
4.
During normal plant operation the subject safety injection lines are not required to operate or perform a safety function but remains flooded under static conditions.
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N.
K. A. Ainger Comonwealth Edison Ici
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