ML19323G668
| ML19323G668 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/08/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8006060439 | |
| Download: ML19323G668 (2) | |
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'e UNITED STATES 77 NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N W., SUITE 3100 o g* O 4 8 ATLANTA, G EORGI A 30303 In Reply Refer To:
MAY 8 1980 RII.;JPO _
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Mississippi Power and Light Company Attn:
N. L. Stampley Vice President of Production P. O. Box 1640 Jackson, MS 39205 Gentlemen:
Enclosed is IE Bulletin No. 80-11 which is forwarded to you for infor-l mation. No written response is required. Should you have any questions regarding this matter, please contact this office.
Sincerely, James P. O'Re Director
Enclosures:
1.
List of Recently Issued IE Bulletins r
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SSINS No.:
6820 Accession No.:
UNITED STATES 7912190695 NUCLEAk REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT WASHINGTON, D.C.
20555 May 8, 1980 IE Bulletin No. 80-11 MASONRY WALL DESIGN Description of Circumstances:
i 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:
1)
Apparent lack of a final check of certain pipe support locations and j
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 pos.tive connection between the two walls by means other than the bond provided by a layer of mortar, grout or concrete between them.
Continaed 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, deficiencies with other operating facilities, we have concerns with regard to and supplements). Because of this and the generic implications of similar 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.
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- IE Bulletin 79-02, Revision 2 issued r pipe supports attached to masonry walV' pipe supports in this category, the e DUPLICATE DOCUMENT bolting through the wall or the suppo Supports that are bolted through maso Entire document previously review for this Bulletin.
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of Pages:
SSINS No.:
6870 UNITED STATES Accession No.:
NUCLEAR REGULATORY CO.T!ISSION 7910250475 0FFICE OF INSEECT10N AND ENFORCEMENT WASHINGTON, D.C.
20555 r
November 16, 1979 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.
i The NRC is currently pursuing these issues in detail for the Trojan Nuclear Plant to determine the extnet 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 raview the information for j
possible applicability to their facilities and the actins being performed under IE Bulletin No. 79-02.
Specific action is being requested 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.
4 IE Bulletin No. 80-11 Enclosure May 8, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-11 Masonry Wall Design 5/8/80 All power reactor facilities with an OL or CP 80-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for OL or CP Unmonitored, Uncontrolled Release to Environment 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits 80-08 Examination of Containment 4/7/80 All power reactors with Liner Penetration Welds a CP and/or OL no later than April 7, 1980 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an OL 80-06 Engineered Safety Feature 3/13/80 All power reactor (ESF) Reset Controls facilities with an OL 80-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor In Damage To Chemical Volume facilities holding Control System (CVCS) Holdup OLs and to those with Tanks a CP 79-01B Environmental Qualification 2/29/80 All power reactor of Class IE Equipment facilities with an OL 4
80-04 Analysis of a PWR Main 2/8/80 All PWR reactor facilities Steam Line Break With holding OLs and to those Continued Feedwater nearing licensing Addition 80-03 Loss of Charcoal From 2/6/80
.All holders of Power Standard Type II,'2 Inch,
- Reactor OLs and cps Tray Adsorber Cells 80-02 Inadequate Quality 1/21/80 All BWR licenses with Assurance for Nuclear a CP or OL 80-01 Operability of ADS Valve 1/11/80 All BWR power reactor Pneumatic Supply facilities with and OL
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