IR 05000456/1986022
| ML20211D820 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/05/1986 |
| From: | Danielson D, Norton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20211D800 | List: |
| References | |
| 50-456-86-22, NUDOCS 8606130160 | |
| Download: ML20211D820 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-456/86022(DRS)
Docket No. 50-456 Construction Permit No. CPPR-132
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Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood Station, Unit 1 Inspection At: Braidwood Site, Braidwood IL Inspection Conducted: May 14, 22 and June 2, 1986 3-4 tedk.
Inspector:
J. F. Norton w/ 5/8(,
DTte Approved By:
D. H. Danielson, Chief
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Materials and Processes Section Da'te '
Inspection Summary l
InspectiononMay14,22,andJune_2_,19861ReportNo.
Areas Inslected: UnannounceCaf"etylEspection of"tFe~st'rIIcturil liit'egr50-456/860 test of~tle Unit 1 containment structure.
Results: No violations or deviations were identified.
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8606130160 860605 PDR ADOCK 05000456 G
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DETAILS 1.
Person Contacted
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CommonwealthEdisonCompanyjCECo).
- D. Shamblin, Project Construction Superintendent
- B. Tanouye, Structural Engineer
- P. Barnes, Regulatory Assurance Supervisor C. Gray, Structural Engineer
- D. Hoffer, Quality Assurance Supervisor M. Poland, Field Engineer Wiss, Janney, Elstner Associates, Incorpora_ted (WJ_El
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G. Hudine, Test Engineer D. Heidbrink, Project Engineer D. Nixon, Project Technician T. Brown, Project Manager Sargent and Lundy Engineers (S&L)
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S. Schacht, Senior Structural Engineering Specialist S. Putman, Structural Engineering Supervisor U.S. Nuclear Regulatory, Commission _ (NRCl R
- T. Tongue, Senior Resident Inspector
- Denotes those attending the exit meeting.
2.
_ Structural _ Integri_ty_ _Tes_t (SIT)_o_f Unit 1 Containment Structure a.
Procedures and Directives
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The NRC inspector verified that the test specifications, procedures, and reference documents were in accordance with NRC
requirements and licensee conmitments, and that authorized
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personnel had approved the program documents.
b.
Test Equipment Test equipment included three 1800 cfm and one 7000 cfm Ingersoll
Rand air compressors with individual dryers, 34 Sensitive l
Extensometers, a Hewlett Packard 3497 data logger and computer system, thermocouples, digital voltmeters, and other associated i
equipment.
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c.
Calibration The NRC inspector assured that all test equipment (except the compressors) was verified to be properly calibrated over the full range of their anticipated use prior to and following testing.
Sensitive Extensometers were calibrated in accordance with WJE Procedure OP-65 " Procedure Manual for Calibration of Sensitive Extensometers".
d.
Test Objectives The purpose of the test was to:
(1) Measure and record the structural response of the primary containment structure under design pressure loading conditions.
(2) Verify that the measured response was within predicated design limitations and tolerances.
(3) Demonstrate that the structural integrity of the primary containment structure could be maintained under 1.15 times
design internal pressure load, e.
Test Pressurization of the containment structure was started May 21, 1986, l
at 1412. Pressurization and depressurization was incrementally accomplished (10; 20; 30; 40; 50; 57.5 psig.) in accordance with test procedures.
Full pressurization was attained May 22, 1986, at 1925,
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and depressurization was completed at 1427 on May 24,1986. The NRC inspector witnessed a portion of this pressure test to assure compliance with test procedures.
f.
Crack Mapping At atmospheric pressure and at each stage of pressurization and
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depressurization, (after the pressure had stabilized for one hour),
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j the structural response was recorded. Ten areas were marked with black marker grid lines 7' by 7' with 1 square foot grids. These grid areas were reproduced on data sheets. The area locations are documented on S&L Drawing S-1052. All cracks over 0.01" wide and 6"
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long in the designated areas were mapped. Also, twenty four hours
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after containment pressure was returned to atmospheric, the containment response was monitored for cracks. After recovery, the structure was inspected inside and outside for indications of damage
or permanent deformation of liner or concrete. After recovery, the i
NRC inspector examined several areas both inside and outside containment and observed no damage.
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g.
Test Results The NRC inspector's review of test records and data readouts revealed all structural movements, cracking and elastic recovery to be within acceptable limits. Maximum movement was 0.521" vertical at the center of the containment dome (Extensometer V-9).
Structural recovery from maximum deflection was calculated to be 98%.
t No violations or deviations were identified.
3.
Exit Meeting The NRC inspector met with licensee representative (denoted under
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Paragraph 1) at the conclusion of the inspection on June 2,1986. The
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inspector summarized the purpose and findings of the inspection. The licensee acknowledged this information. The inspector also discussed the
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likely informational content of the inspection report with regard to documents or processes reviewed during the inspection. The licensee did
not identify any documents / processes as proprietary.
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