ML20004E549
| ML20004E549 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 06/08/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8106120327 | |
| Download: ML20004E549 (1) | |
Text
i UNITED STATES
/pa atoog'o, NUCLEAR REGULATORY COMMISSION
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June 8 98
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y MEMORANDUM FOR: Those Listed Below
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FROM:
G. L. Madsen, Chief, Reactor Projects Branch, RIV
SUBJECT:
IE CIRCULAR NO. 81-08 Subject IE Circular has been sent to the following listed licensees. A copy of the IE Circular is attached for your infonnation.
Arkansas Power & Light Company Gulf States Utilities ANO-1 & 2 (50-313; 50-368)
River Bend (50-458; 50-459)
Nebraska Public Power District Houston Lighting & Power Company Cooper Nuclear SMtion (50-298)
South Texas (50-498; 50-499)
Omaha Public Power District Kansas Gas & Electric Company Ft. Calhoun (50-285)
Wolf Creek (STN 50-482)
Public Service Company of Colorado Louisiana Power & Light Company Fort St. Vrain (50-267)
Waterford-3(50-382)
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l Texas Utilities Generating Company ComanchePeak(50-445;50-446) i W6 G. L., Madsen, Chief, Reactor Projects Branch
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SSINS No.: 6830 Accession No.:
8103300374 IEC 81-08 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20S55 IE Circular No. 81-08 May 29, 1981 Page 1 of 3 FOUNDATION MATERIALS Description of Circumstances:
Insufficient compaction of foundation and backfill materials during the con-struction of nuclear plants has resulted in excessive settlement of plant structures at a number of sites.
At the Midland Plant, Units 1 and 2, insufficiently compacted backfill was discovered as a result of excessive settlement of the diesel generator build-ing. The results of extensive subsurface investigations subsequent to settle-ment of the diesel generator building identified that fill materials beneath portions of the auxiliary building, feedwater isolation valve pits, essential service water intake structure, borated water storage tanks, and plant area utilities were not compacted to specification requirements.
Other specific nuclear power plant sites and identified problems are listed to illustrate the extent of the problem.
Service water pumphouse settlement North Anna Service water pumphouse settlement Indequate moisture control in fill material Summer Shearon Harris Inadequate field density control and soils tests Cherokee Inadequate QC procedures and fill placement Inadequate compaction, groundwater, and soil erosion Hatch Vogtle controls Inadequate QC procedures and inspection documentation South Texas The above problees necessitated extensive remedial work; for example, remova of large quantities of fill material, underpinning structures, surcharging foundation materials, project delays, extensive reanalysis, and, in some cases technical specification requirements pertaining to settlement monitoring during plant operation.
The causes of insufficient compaction were investigated by NRC, licensees / co Based struction permit holders, contractors and architect-engineering firms.
on these investigations, the various contributing causes wera found to include the following:
IE Circular No. 81-08 Page 2 of 3 d
Soil selection, fill, and compaction activities were not accompli under the direction of a qualified geotechnical engineer.
1.
i Compaction equipment was not qualified to achieve the req t l equipment using the material specified, lift thickness, solsture con ro,
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speed, or number of equipment passes.
t Procedures for control of soil testing were not adequate to a l
l of soil identification, selection of laboratory standards, and contro 3.
field density tests.
the Relative density and percent compaction test results fell outsid i
f laboratory theoretir.al limits, indicating an unrealistic comparison o 4.
and field density tests.
Soils inspections did not verify cuatrols specified in constru 5.
specifications.
Quality assurance audits did not identify the procedura the cause of repetitive nonconforming conditions.
6.
i pecifi-Design requirements were not properly translated into cons 7.
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cations.
tion Design change notices were not issued to reflect changes 8.
specification requirements.
l intensity, Settlement calculations based on actual de formed.
j 9.
Recommended Action for Construction permit Hold rs:
ht For those facilities with ongoing soils work activities, verify including procedures, quality assurance and quality control measures implemented to assure 1.
test results, inspection personnel and audits aretha ils work in progress or planned.
have a For those facilities with completed soils wo red settle-2.
ment values are within the projected values.
ded that an settlement values exceed projected values, it is recommen In those cases, an investigation to determine the cause be initiated.
evaluation which includes soil borings may be in order.
do not For those facilities with completed sofis work activities tha t the quality have an ongoing settlement monitoring program, verify tha item 1 above were 3.
assurance and quality control measures described in in effect during construction.
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s IE Circular No. 81-08 Page 3 of 3 Although no specific response is required by this circular, soil compaction construction deficiencies identified and corrective actions initiated as a i
result of tne actions recommended may be reportable in accordance with the requirements of 10 CFR 50.55(e).
If you need additional information regarding this matter,-contact the Director of f.he appropriate Regional office.
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O IE Circular No. 81-08 May 29, 1981 RECENTLY ISSUED IE CIRCULARS Date Issued To Circular Subject Issued No.
80-24 AECL Teletherapy Unit 12/2/80 All teletherapy licensees Malfunction 81-01 Design Problems Involving 1/23/81 All power reactor facilities with an Indicating Pushbutton Switches Manufactured by Operating Licenses (OL) or Construction Permit (CP)
Honeywell Incorporated 81-02 Performance of NRC-
-2/9/81 All power reactor facilities (research and test) with an Licensed Individuals Operating License (OL) or While on Outy Construction Permit (CP) 81-03 Inoperable Seismic 3/2/81 All power reactor facilities (reasearch and test) with an Monitoring Instru-Operating License (OL) or mentation Construction Permit (CP) 81-05 Self-AligningRoddnd 3/31/81 All power reactor facilities with an Operating Licenses Bushings for Pipe (OL) or Construction Permit Supports (CP) 81-06 Potential Deficiency 4/14/81 All power reactor facilities with an Operating License Affecting Certain (OL) or Construction Permit Foxboro 10 to 50 (CP)
Mil 11 ampere Transmitters 81-04 The Role of Shift Tech-4/30/81 All power reactor facilities with an Operating Licenses (OL) nical Advisors and Impor-or near-term Operating Licenses (OL) tance if Licensee Event Reports 81-07 Control of P.adioactively 5/14/81 All power reactor facilities with an Contaminated Material Operating License (OL) or Construction Permit (CP)
Enclosure
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