ML20002B633: Difference between revisions

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              .          .J PUBLIC SERVICE                                                                                             7 INDIANA S. W. Shields 4        Senior Vice Presdent -
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Nuc4 ear osson                                                           December 10, 1980
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Mr. James G. Keppler, Director                                                 Docket Nos.:         STN 50-546 3
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U. S. Nuclear Regulatory Commission                                                                 STN 50-547 Region III                                                                     Construction Permit Nos.:
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799 Roosevelt Road                                                                                   CPPR - 170 Glen Ellyn, Illinois 60137                                                                           CPPR - 171 Marble Hill Nuclear Generating Station - Units 1 and 2
.J PUBLIC SERVICE 7
INDIANA S. W. Shields Senior Vice Presdent -
4 Nuc4 ear osson December 10, 1980
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Mr. James G. Keppler, Director Docket Nos.:
STN 50-546 3
U. S. Nuclear Regulatory Commission STN 50-547 Region III Construction Permit Nos.:
799 Roosevelt Road CPPR - 170 Glen Ellyn, Illinois 60137 CPPR - 171 Marble Hill Nuclear Generating Station - Units 1 and 2


==Dear Mr. Keppler:==
==Dear Mr. Keppler:==
 
On July 17, 1980, Mr. T. D. Geib of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55 (e). The support steel supplier for the Nuclear Steam Supply System, Lakeside Bridge and Steel Company, notified PSI that certain radiographs of the steam generator upper lateral support embedments did not meet the density requirements of Section V of the ASME B&PV Code.
On July 17, 1980, Mr. T. D. Geib of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55 (e) . The support steel supplier for the Nuclear Steam Supply System, Lakeside Bridge and Steel Company, notified PSI that certain radiographs of the steam generator upper lateral support embedments did not meet the density requirements of Section V of the ASME B&PV Code.
In the interim report of October 20, 1980, PSI identified additional embedments and pipe restraints which required reexamination. This reexaminatien has been performed but the results are presently under review by PSI's i
In the interim report of October 20, 1980, PSI identified additional embedments and pipe restraints which required reexamination. This reexaminatien has been performed but the results are presently under review by PSI's i     architect-engineer and have not yet been accepted. PSI anticipates the results of this examination will be available on or before January 15, 1981.                                   If you have any questions on this matter, please feel free to contact me.
architect-engineer and have not yet been accepted. PSI anticipates the results of this examination will be available on or before January 15, 1981.
Sincerely, h             !
If you have any questions on this matter, please feel free to contact me.
S. W. Shield TDG/cg cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.         20555 E. R. Schweibins, P. E.
Sincerely, h
J. J. Harrison 6         3 8012220                   r 222                                          3 P.O. Box 190, New Washington, Indiana 47162                           812. 293.4441
S. W. Shield TDG/cg cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
  .__                                            . - - . . . _ _ , - . . . _ . . .                  . . _ -          .}}
20555 E. R. Schweibins, P. E.
J. J. Harrison 6
3 8012220 3
r222 P.O. Box 190, New Washington, Indiana 47162 812. 293.4441
.}}

Latest revision as of 15:49, 23 December 2024

Interim Deficiency Rept Re Radiographs of Steam Generator Upper Lateral Support Embedments Not Meeting Density Requirements,Initially Reported on 800717.Re-examination Has Been Performed.Results Will Be Available by 810115
ML20002B633
Person / Time
Site: Marble Hill
Issue date: 12/10/1980
From: Shields S
PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8012220228
Download: ML20002B633 (1)


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.J PUBLIC SERVICE 7

INDIANA S. W. Shields Senior Vice Presdent -

4 Nuc4 ear osson December 10, 1980

~

Mr. James G. Keppler, Director Docket Nos.:

STN 50-546 3

U. S. Nuclear Regulatory Commission STN 50-547 Region III Construction Permit Nos.:

799 Roosevelt Road CPPR - 170 Glen Ellyn, Illinois 60137 CPPR - 171 Marble Hill Nuclear Generating Station - Units 1 and 2

Dear Mr. Keppler:

On July 17, 1980, Mr. T. D. Geib of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55 (e). The support steel supplier for the Nuclear Steam Supply System, Lakeside Bridge and Steel Company, notified PSI that certain radiographs of the steam generator upper lateral support embedments did not meet the density requirements of Section V of the ASME B&PV Code.

In the interim report of October 20, 1980, PSI identified additional embedments and pipe restraints which required reexamination. This reexaminatien has been performed but the results are presently under review by PSI's i

architect-engineer and have not yet been accepted. PSI anticipates the results of this examination will be available on or before January 15, 1981.

If you have any questions on this matter, please feel free to contact me.

Sincerely, h

S. W. Shield TDG/cg cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 E. R. Schweibins, P. E.

J. J. Harrison 6

3 8012220 3

r222 P.O. Box 190, New Washington, Indiana 47162 812. 293.4441

.