ML19323G719
| ML19323G719 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/08/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8006060535 | |
| Download: ML19323G719 (2) | |
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UNITED STATES
! y,,,7f-1 NUCLEAR REGULATORY COMMISSION
$.3 s,t,f ' 3 E REGION 11 o, gj a[gf 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, G EORGIA 30303 MAY 8 1980 In Reply Refer To:
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/$0-302(3 N6 Florida Power Corporation Attn:
J. A. Hancock, Director Nuclear Operations P. O. Box 14042, Mail Stop C-4 St. Petersburg, FL 33733 Gentlemen:
Enclosed is IE Bulletin No. 80-11 which requires actL.n by you.
A written response is required. Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
(
James P. O'Reill Director
Enclosures:
1.
List of Recently Issued IE Bulletins
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e SSINS No.:
6820 Accession No.:
UNITED STATES 7912190695 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 May 8, 1980 IE Bulletin No. 80-11 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:
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 error in engineering judgment, lack of procedures aad 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 issued or MW pipe supports attached to masonry wall" pipe supports in this category, the e bolting through the wall or the suppor DUPLICATE DOCUMENT Supports that are bolted through mason review for this Bulletin.
Entire dccument previously entered into system under:
7 h/k ANO No. of pages:
SSINS No.: 6870 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 7910250475 0FFICE OF INSPECTION AND ENFORCEMEhT WASHINGTON, D.C.
20555 November 16, 1979 IE 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) 2 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 ossessed adequate structural integrity to sustain the required loads.
l 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 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 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 Regiona. Office.
No written response to this IE Information Notice is required.
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e 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-IC 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 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 ~
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80-02 Inadequate Quality 1/21/80 All BWR licenses with Assurance for Nuclear a CP or OL i
r 80-01 Operability'of ADS Valve 1/11/80 All BWR power reactor Pnenmatic Supply facilities with and l
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