ML19323D178
| ML19323D178 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/08/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8005210213 | |
| Download: ML19323D178 (1) | |
Text
0 UNITED STATES
/'sv 5' 0,o, NUCLEAR REGULATORY COMM.!SSION NSIC V
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R ectoN IV CENTRAL FILES
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611 RY AN PLAZA DRIVE, SulTE 1000 pg -
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ARLINGTON, TEX AS 76012 3g Af'f ss May 8, 1980 In Reply Refer To:
RIV Docket No.
STN 50-482/I2 Bulletin No. 80-11 Kansas Gas & Electric Co.
Attn:
Mr. Glenn L. Koester Vice President-Operations Post Office Box 208 Wichita, Kansas 67201 Gentlemen:
Enclosed is IE Eulletin No. 80-11 which is forwarded to you for information.
No written response is required.
Should you have any questions regarding this matter, please contact this office.
Sincerely, Q
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Karl V. Seyfrit Director
Enclosures:
1.
List of Recently Issued IE Bulletins o
cc: w/ enclosures Messrs. Nicholas A. Petrick, SNUPPS D. T. McPhee, Kansas City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company J
B00ssa g1t3
ENCLOSURE 1 SSINS No.:
6820 Accession No.:
UNITED STATES 7912190695 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555
_ IE Bulletin No. 80-11 Date:
May 8, 1980 Page 1 of 4 MASONRY WALL DESIGN Description of Circumstances:
In the course of conducting inspections pursuant to IE Bulletin Nos. 79-02 and 79-14 at the Trojan Nuclear Plant, Portland General Electric Co. (PGE) identi-fied a problem with the structural integrity of concrete masonry walls with Seismic Category I piping attached to them.
This problem was briefly addressed in IE Information Notice No. 79-28, which was sent to all Construction Permit and Operating License holders on November 16, 1979 (Attachment 1).
The problem was that some walls were found which did not have adequate structural strength to sustain the required piping system support reactions.
These structural deficiencies were at that time reported to be attributable to two deficiencies:
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1)
Apparent lack of a final check of certain pipe support locations and reactions to ensure that the supporting elements possessed adequate structural integrity to sustain the required loads.
2)
Non-conservative design criteria for the reactions from supports anchored into the face of concrete masonry walls; e.g., relying on the combined strength of double block walls without substantial positive connection between the two walls by means other than the bond provided by a layer of mortar, grout or concrete between them.
Continued investigations into the deficiencies identified at the Trojan Nuclear Plant, engineered by Bechtel, confirmed the deficiencies to be attributable to arror in engineering judgment, lack of procedures and procedural detail, and inadequate design criteria (details are in Trojan Nuclear Plant's LER No.
79-15, and supplements).
Because of this and the generic implications of similar deficiencies with other operating facilities, we have concerns with regard to the adequacy of design criteria used for the design of masonry walls and an apparent lack of design coordination between the structural and piping /
equipment design groups.
IE Bulletin 79-02, Revision 2 issu pipe supports attached to masonry DUPLICATE DOCUMENT most pipe supports in this catego by bolting through the wall or the Entire docturent previously Supports that are bolted through a entered into system under:
the review for this Bulletin.
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ANO N o. of pages:
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l SSINS No.:
6870 UNITED STATES AccessionNo.h NUCLEAR REGULATORY C0!!! FISSION 7910250475 0FFICE OF INSPECTION AND ENFORCElfENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-28 Date: November 16, 1979 Page 1 of 1 OVERLOADING OF STRUCTURAL ELErfENTS DUE TO PIPE SUFSORT LOADS Description of Circumstances:
Recently, the NRC was informed that, in the course of the inspections pursuant to IE Bulletin No. 79-02 and 79-14 by the Portland General Electric Co.
(PGE) at the Trojan Nuclear Plant, some walls were found which did not have adequate
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structural strength to sustain the required support reactions.
Bechtel Corporation was the Architect Engineer for the plant.
These structural inadequacies were reported to be attributable to two deficiencies:
1)
Apparent lack of a final check of certain pipe support locations and reactions to ensure that the supporting structural elements possessed adequate structural integrity to sustain the required loads.
2)
Inadequate design criteria for the reactions from supports anchored into the face of concrete block walls; e.g., relying on the combined strength j
of double concrete block walls without positive connection between the j
two walls by means other than the bond provided by layer of grout between them.
1 The NRC is currently pursuing these issues in detail for the Trojan Nuclear Plant to determine the extent of these deficiencies and the generic implications for other Bechtel facilities.
This Information Notice is provided as an early notification of a possible signif-icant matter.
It is expected that recipients will review the information for possible applicability to their facilities and the actir.ns being perforaed under IE Bulletin No. 79-02.
Specific action is being reque?',co relating to the adequacy of attachments to concrete block walls under IE Bulletin No. 79-02, Revision 2, item 5.c.
No specific actions are requested in response to this Information Notice.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
No written response to this IE Information Notice is required.
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IE Bulletin No. 80-11 May 8, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-06 Engineered Safety Feature 3/13/80 All power reactor facilities (ESF) Reset Controls with an Operating License (OL)79-03A Longitudinal Weld Defects 4/4/80 All power reactor facilities In ASME SA-312 Type 304 with an Operating License Stainless Steel Pipe (OL) or Construction Permit (CP) 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and BWR-4 Failure facilities with an Operating License (OL) 80-08 Examination of Containment 4/7/80 All power reactors with a Liner Penetration Welds Construction Permit and/or Operating License (OL) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficien::ies operating facilities and holders of power reactor construction permits (cps) 80-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for Operating License (OL)
Unmonitored, Uncontrolled or Construction Permit Release to Environment (CP)
Enclosure
.