ML20204G467
| ML20204G467 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/15/1983 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8305020500 | |
| Download: ML20204G467 (2) | |
Text
{{#Wiki_filter:.' F P.O. BOX 5000 - CLEVELAND. OHlo 44101 - TELEPHONE (216) 622-9800 - (LLUMINATING BLDG - 55 PUBLIC SoUARE i Sening The Best Location in the Nation MURRAY R. EDELMAN VICE M4ESIDENT April 15, 1983 NUC LE A R Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Pipe Whip Restraint Bracket Welds for B21/B33 Systems [RDC 64(83)]
Dear Mr. Keppler:
This letter serves as the second interim report pursuant to 10CFR50.55(e) on the significant deficiency concerning problems with the bracket welds for the Main Steam and Recirculation System Pipe Whip Restraints. This problem was identified to Mr. Pelke of the NRC Region III Office of Inspection and Enforcement on December 28, 1982, by Mr. E. Parker for The Cleveland Electric Illuminating Company (CEI) and formally reported in our first interim report, dated January 26, 1983. This report contains a description of the deficiency, an evaluation of the deficiency, and the corrective action to be implemented. Description of Deficiency Visual and Magnetic Particle inspection of the completed welds connecting the pipe whip restraint brackets to the drywell structural steel noted three welds with linear indications. Subsequent investigation into the cause of the indications identified that the bracket material was not compatible with the welding code and the pre-qualified procedure that was fallowed. The pipe whip restraint brackets were supplied by the General Electric Company, San Jose (CE NEBO) with the applicable welding code (AWS) specified in their Installation Specification 22A2598. The brackets were installed by General Electric Installation and Service Engineering (now Apparatus and Engineering Services or GE A&ES) in accordance with their welding procedure, WPS 1.1.8.1, Rev. 3. This procedure is a pre-qualified AWS procedure, however, it is not acceptable for use on the welding oE the brackets due to the dif ference it. the thickness of the bracket material and the thickness of material that the procedure was qualified for. Additionally, material verification of the bracket identified that the material is ASTM-A105 which is not a pre-approved material by the AWS Code. All forty-eight Recirculation System and thirty-six Main Steam System Pipe Whip Restraint Brackets for a total of eighty-four were installed prior to the identification of this deficiency. Installation of the four remaining Main Steam restraints had been stopped pending final evaluation. Please note, the ,- g k 1 j number installed has been corrected. .] ' (2005020500 830415 l PDR ADOCK 05000440 ApR 2 1 G"M; S PDR
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- Mr. James G. Keppler April 15, 1983 l
l Evaluation of Deficiency As -identified in the first interim report, GE NEB 0 and GE A&ES were to perform extensive metallographic testing on the bracket welds. The testing concentrated on the brackets from heat J-02159, as all failures identified to date related to brackets from this heat. In addition, CEI contracted a local testing lab to perform independent metallographic tests to determine the cause of the weld problem and substantiate the results obtained by GE. The results of the various tests revealed the presence of underbead cracking in the weld heat affected zones of the brackets from heat J-02159. The brackets which are not from heat J-02159 have been evaluated using a UT procedure developed by GE NEB 0 to detect the presence of underbead cracking. Most of the welds for these brackets exhibit UT results similar to those from heat J-02159. Further metallographic testing will be performed on the welds to confirm the UT reports and to determine the corrective action for the non-J-02159 heat brackets. Corrective Action A total of 84 brackets may have this weld deficiency. Forty-three (43) brackets are from heat J-02159. These will be removed and the structural steel they were welded to reworked to its original condition. New brackets will then be installed using approved welding procedures which include require-ments to alleviate the underbead cracking previously encountered. Based on the UT results the 41 brackets which are not from heat J-02159 will undergo further metallographic tests, with the final corrective action to be performed on them dependent on the results of these tests. The repair status of the brackets from heat J-02159 and the test results and corrective action for the remaining 41 brackets will be described in our next report, which will be submitted by July 1,1983. Please call if there are additional questions. Sincerely, ' -{- 8 ' ,E Y f p Murray R. Edelman Vice President l Nuclear Group l MRE:pab l cc: Mr. M. L. Gildner NRC Site Office i Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 L}}