IR 05000389/1978012

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IE Insp Rept 50-389/78-12 on 781128-1201.Noncompliance Noted:Failure to Test Concrete for Air,Slump & Temp at Prescribed Frequency
ML17206A685
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 12/22/1978
From: Bryant J, Harris J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17206A681 List:
References
50-389-78-12, NUDOCS 7903190288
Download: ML17206A685 (4)


Text

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Cy UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30303 Report Nos.:

50-389/78-12 Docket No.:

50-389 License No.:

CPPR-144 Category:

A2 Licensee:

Florida Power and Light Company P. 0. Box 013100 Miami, Florida 33101 Facility Name:

St. Lucie 2 Inspection at:

Hutchinson Island, Florida Inspection conducted:

November 28 - December 1, 1978 Inspector:

J. R. Harris Reviewed by:

J.

. Bryant, C ief Engineering Support Section No.

Reactor Construction and Engineering Support Branch 1'z ~ 7g Da e

Ins ection Summa Ins ection on November 28 - December

1978 (Re ort No. 50-389/78-12)

Q"

"'reparation and backfill in Unit 2 reactor auxiliary building; construction status; Class I storage facilities; preventative maintenance program for Class I equipment.

The inspection involved 26 inspector-hours on site by one NRC inspector.

Results:

Of four areas inspected, no apparent items of noncompliance or deviations were identified in three areas; one apparent item of noncompliance was identified in one area (Deficiency:

failure to test concrete for air, slump and temperature at the prescribed frequency - Details I, Paragraph 5).

7903 z90288'

I RII Report No. 50-389/78-12 DETAILS I Prepared by:

12 )p J. R. Harris Civil ngineer Geoligist at Engr.neerxng Support Section No.

Reactor Construction and Engineering Support Branch Dates of Inspection:

November 28 - December 1, 1978 Reviewed by:

J.

C. Bryant, hief Engineering Support Section No.

Reactor Construction and Engineering Support Branch

~~ iz 7E ate 1.

Persons Contacted a.

Florida Power and Li ht Com an (FPM,)

"B. J. Escue, Site Manager

&. M. Hayward, QA Construction Supervisor

  • J. I. Parker, Project Quality Control Supervisor

<K. V. Oeveren, QA Record Custodian

  • E. W. Sherman, QA Engineer-J. J. Capizza, Site Resident Engineer Office J. Baysinger, Process Control Specialist C. Carlos, Civil QC Supervisor L, T. Page, QA Engineer O. J. Karch, QA Engineer b.

Contractor Or anization Ebasco Services Inc.

(Ebasco)

-K. Flanagan, Construction Superintendent

+Denotes those present at the exit interview.

2.

Licensee Actions on Previous Ins ection Findin s

This item was not inspected.

3.

Unresolved Items No unresolved items resulted from this inspectio RII Report No. 50-389/78-12 I-2 4.

Inde endent Ins ection The inspector examined the following areas:

a.

Overall construction status b.

Storage facilities for A, B, C and D storage areas c.

Preventive maintenance program on heat exchangers and heaters requiring purge with a neutral gas d.

Concrete batch plant e.

Installation of reinforcing steel in the reactor auxiliary building f.

Calibration controls on soils and concrete testing equipment g.

Prepour preparation for pour numbers 9A and 12A in the reactor control building.

No deviations or items of noncompliance were identified in the areas examined.

5.

Foundation - Review of ualit Records Unit 2 The inspector examined quality records on foundation preparation, backfill and concrete basemat for areas 19AA, 20AA, 21AA and 22AA of the reactor auxiliary building.

Acceptance criteria examined by the inspector appear in the following documents:

a.

PSAR; Sections 2.5-29, 2.5-30, 2.5.4.5 and Appendix 2B b.

gl, 7.1, 10.2-10.7, 10,10, 10.11, 10.70, 10.71, 10.72, 10.76 and 10.77 c.

FL0-2998.473, Ebasco Specification Concrete d.

FL0-2998,471, Excavation and Backfill e.

CSP-25, Excavation and Backfill f.

Drawing number 2998-G-555, RAB Base Slab, Sections and Details.

Concrete records examined included:

Inspection reports for concrete batching, concrete conveying equipment, concrete placement and consoli-dation, post placement curing, in-process testing, concrete cylinder break strengths, placing reinforcing steel, embed items, frost placement and concrete materials receiving repor V RII Report No. 50-389/78-12 I-3 Foundation preparation and backfill records examined included inspection reports on compaction at elevation-9.42 prior to placement of mudmats and inspection reports of backfill operations between elevations-7.5 to +5.0.

These reports included data on grain size distribution, moisture density relationships, field densities and backfill and compaction operations.

Examination of records on the concrete basemat in areas 21 and 22 of the reactor auxiliary building disclosed that concrete was not sampled and tested for air, temperature and slump at the interval specified in QI 10.71.

Procedure QI 10.71 requires that the first batch produced each day and every 50 cubic yards per mix type be sampled and tested for air, temperature and slump.

Records for concrete placement in areas

and 22 of the reactor auxiliary building basemat show that five of the 23 required sampling intervals varied from 60-80 cubic yards.

Because the correct number of samples were taken and test results were within specified tolerances, and cylinder data showed concrete strengths exceeded design requirements, this was identified to the licensee as Deficiency 389-78-12-01 instead of an Infraction.

6.

Exit Interview The inspector met with the licensee representatives (denoted in para-graph 1) at the conclusion of the inspection.

The inspector summarized the scope and findings of his examination of QA-QC controls on structural concrete, foundations and Category 1 storage facilities'ollowing the exit interview, the licensee was notified of the one item of noncompliance (described in paragraph 5) by phone conversation with the QA construction supervisor on December 5, 1978 'he licensee acknowledged the one item of noncompliance.