ML18046A846
| ML18046A846 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/30/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-81-07-092, LSO5-81-7-92, NUDOCS 8108050308 | |
| Download: ML18046A846 (5) | |
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July 30, 1981 Docket No. 50-255 LS05-81-07-092 Mr. David P. Hoffman Nucl~ar Licensing Administrator
.Consumers Power Company 1945 W *. Parna 11 Road,.,
Jackson, Michigan 4g~1
Dear Mr. Hoffman:
SUBJECT:
SYSTEMATIC EVALUATION *PROGRAM TOPIC llI-7D, 11CONTAINMENT STRUCTURAL INTEGRITY TEST" Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic IIl-7D.
The evaluation concludes that the structural integrity test and test procedures performed at Palisades compare favorably to current criteria.
You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying errors and supplying the corrected information.
We encourage you to supply any other material that might affect the staff'.s eval uatfon of these topics" or be significant fn the integrated assessment of your facility.
Your response is requested withtn 30days of receipt of this letter. If no response 1s received within that time, we will assume that you have no conunents or corrections.
Enclosure:
As stated Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
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ENCLOSURE PALI SADES PLANT DOCKET NO. 50-255 SEP TOPIC III-7.D.
ASSESSMENT OF CONTAINMENT STRUCTURAL INTEGRITY TEST I.
INTRODUCTION
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The structural integrity test procedure and test results for the Palisades containment were evaluated against current criteria for such tests. The purpose of the evaluation was to verify that the containment structural integrity test was in compliance with the current requirements of 10CFR50 and thus provide assurance that the structure would perfonn its intended. safety function.
I I.
REVIEW CRITERIA
References:
A.
NRC Standard Review Plan Section 3.8.l C.
ASME Boiler and Pressure Vessel Code,Section III, Division 2, Article CC-6000 D.
NRC Regulatory Guide 1.18 E.
Letter from Cons~mers Power Co. dated becember 14, 1970 which forwarded containment Building Structural Integrity Test Program_ to NRC F.
FSAR Palisades Plant, Section 5 and Appendices A through I G.
Letter from Consumers Power Co. dated December 4, 1980
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Page 2 of Enclosure Ref~rences A through D outline current criteria for conducting and evaluating containment structural integrity tests.
References E through G describe the containment tests actually conducted at the Palisades Plant.
III.
RELATED TOPICS AND INTERFACES SEP Topic VI-3 "Containment Pressure and Heat Removal Capability" will provide an assessment of.the adequacy of the original design pressure for the containment.
The evaluation described herein is based on the original design and test pressure loading of the containment as presented in references E through G above.
IV.
REVIEW GUIDELINES The test procedure and results were compared with current NRC criteria for such tests in order to determine if any significant deviations existed.
V.
EVALUATION The Palisades containment is a prestressed concrete, steel lined PWR containment with a sphere-segment dome.
Inside diameter is 116 feet; inside height is 190.5 feet; the concrete wall is
. 3.S_feet thick; the dome is 3 feet thick; and the liner'.plate thickness is 1/4 inch.
Page 3 of Enclosure
' **The containment was pressurized to 63.3 psig (1.15 times design pressure of 55 psig) over an eight day period in March, 1970.
Approximately 450 sensors were used to obtain liner strains, concrete strains, reinforcing steel strains, concrete temperatures, and overall displacements.
As part of the test procedure, twelve load cells were used to continuously monitor tendon forces.
The tendon anchorages were instrumented and evaluated for cracking.
Invar wire extensometers were *placed inside the containment to measure overall deformatioys of the containment and the equipment hatch.
The pressure loading was consistent with current standards and the instrumentation was extensive by current criteria. Overall, the actual strain deformations were reported to be about 5/ 6 f
(83%) of predicted values.
This is within the currently allowed limit of 30% variation required in reference C.
Deflection recovery, as reported in the test data, was very close to total recovery.
Concrete cracking was mapped at nine locations on the containment.
Most crack widths were between 0.001.and 0.005 inches~ Two short cracks (4~6") in the range of 0.02 t6 0.025 inches were observed although these existing prior to the start of the test 9nd no indication was given in the test".report.that these.
cracks "grew."
~.~it ~j Page 4 of Enclosure VI CONCLUSION Based on the review of the original structural integrity test in comparison to current test criteria it is considered that the test was satisfactory and thus demonstrated that the'structure is capable of perfonning its intended safety function.