ML19323D154
| ML19323D154 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/08/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8005210171 | |
| Download: ML19323D154 (1) | |
Text
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o UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION C
e REGION I O,
631 PARK AVENUE O
d KING OF PRUSslA, PENNSYLVANIA 19408 May 8, 1980 Docket No. 50-213 Connecticut Yankee Atomic Power Company ATTN:
Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Gentlemen:
The enclosed IE Bulletin No. 80-11, " Masonry Wall Design," is forwarded to you for action.
A written response is required.
If you desire additional infor-mation regarding this matter, please contact this office.
Sincerely, d
h Boyce H. Grier
' Director Eliclosures:
1.
IE Bulletin No. 80-11 with Attachment 2.
List of Recently Issued IE Bulletins CONTACT:
S. D. Ebneter (215-337-5288) cc w/encls:
R. Graves, Plant Superintendent D. G. Diedrick, Manager of Quality Assurance J. R. Himmelwright, Licensing Safeguards Engineer I
8005210 / 7/
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 tent 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:
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 load'..
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 error 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 document 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:
Attachment to IE Bulletin No. 80-11 SSINS No.:
6870 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 7910250475 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555
}/
I November 16, 1979 15 Information Notice No. 79-28 OVERLOADING OF STRUCTURAL ELEMENTS DUE TO PIPE SUPPORT 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 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 of double concrete block walls without positive connection between the two walls by means other than the bond provided by layer of grout between them.
The NRC is currently pursuing these issues in detail for the Trojan Nuclear Plant to determine the extnet of thase deficiencies and the generic impli-cations for other Bechtel facilities.
This Information Notice is provided as an early notification of a possible significant matter.
It is expected that recipients will review the infor-mation for possible applicability to their facilities and the actins being performed under IE Bulletin No. 79-02.
Specific action is being requested i
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 i
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 appro-priate NRC Regional Office.
No written response to this IE Information Notice is required.
1 i
i
ENCLOSURE 2 IE Bulletin No. 80-11 Date: May 8, 1980 Page 1 of 1 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-05 Vacuum Conditions 3/10/80 All PWR Power Resultingin Damage to Reactor Facili-Chemical Volume Control ties with an System (CVCS) Holdup Operating License Tanks (OL) or Construc-tion Permit (CP) 80-06 Engineered Safety 3/13/80 All Power Reactor Feature (ESF) Reset Facilities with an Controls OL (For Action)
All Power Reactor Facilities with a CP (For Informat:en)79-03A Longitudinal Weld 4/4/80 All Power Reactoe Defects in ASME Facilities with an SA-312, Type 304 OL or CP Stainless Steel Pipe 80-07 BWR Jet Pump Assembly 4/4/80 BWR 3 & 4's with OL Failure (For Action)
BWR's with CP (For Information) 80-08 Examination of Con-4/7/80 All Power Reactor tainment Liner Facilities with Penetration Welds an OL or CP 80-09 Hydromotor Actuator 4/17/80 All Power Reactor Deficiencies Facilities with an OL or CP 80-10 Contamination of 5/6/80 All Power Reac-Nonradioactive tors with OL System and Resulting (for action),'
Potential for Unmoni-with CP (for tored, Uncontrolled information)
Release to Environment l
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