IR 05000389/1980008
| ML17208A969 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/20/1980 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17208A967 | List: |
| References | |
| 50-389-80-08, 50-389-80-8, NUDOCS 8009100149 | |
| Download: ML17208A969 (7) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-389/80-08 Licensee:
Florida Power 6 Light Company 9250 Vest Flagler Street Miami, FL 33101 Facility Name:
St.
tucie Docket No. 50-389 License No.
CPPR-144 Inspection at St.
Inspector:
L Af J.
R.
H Iucie site near Ft. Pierce, Florida rris Date Signed Approved by:
T.
Co ion, Section Chic
,
RCES Branch ate igned SUHHARY Inspection on June 4-6, 1980 Areas Inspected This routine, unannounced inspection involved 19 inspector-hours on site in the areas of structural concrete, foundations and previously identified items.
Results Of the three areas inspected, no items of noncompliance or deviations were identi-fied in two areas; one item of noncompliance was found in one area (Infraction-Inadequate procedural controls on sand-cement fill-paragraph 5).
,8009100
DETAILS Persons Contacted Licensee Employees
- J V.
wE MO C.
d J S.
Thompson, Assistant Site Manager Hayward, QA Construction Supervisor Sherman, QA Engineer Karch, QA Engineer Carlos, Civil QC Supervisor Parker, Project'Quality Control Supervisor Piney, Coating Engineer Other licensee employees contacted included two construction craftsmen, four techni'cians,'nd two office personnel.
Other Organizations
- V. J. Gerley, ESSE Civil Design Supervisor, EBASCO
>P. Gaboury, Resident Engineer Field, EBASCO
"=Attended exit interview Exit Interview The inspection scope and findings were summarized on June 6,
1980 with those persons indicated in Paragraph 1 above.,
Licensee Action on Previous Inspection Findings (Open)
Unresolved Item (389/79-18-01)
Use of expansion joint filler inside containment not qualified.to DBA conditions.
Florida Power and Light Company has contacted Ameron and requested the technical basis for use of Nukem 750 as a qualified caulk.
Submittal of this information is anticipated by July 30, 1980.
This item remains open pending NRC review of the data submitted by Ameron.
(Closed) Infraction (389/79-18-02) Failure to follow procedure in procure-ment of protective coatings.
The inspector reviewed the licensees response and implementation of that response presented in the licensees letters dated November 21, 1979, December 20, 1979" and March 4, 1980.
Painting materials are now handled in accordance with SQP-3.
Central receiving now retains all protective coating materials identified as safety-related in the warehouse until QC performs receipt inspection.
This item is closed.
(Closed) Infraction (389/79-18-03) Failure to place discrepant material in hold areas.
The inspector reviewed the licensees response and implementa-tion of that response presented in the licensees letters dated November 21, 1979, December 20, 1979, and March 4, 1980.
Nonconformance report 869R was initiated October 12, 1979 to assure protective coating materials would be
handled in the same manner as other safety-related material and not delivered to the paint storage facility. Protective coating materials are now segre-gated until receipt inspection approval.
When painting materials are received, they are placed in a QC hold area and pending inspection labels are attached.
NRC has no further questions.
Unresolved Items Unresolved items were not identified during this 'inspection.
Independent Inspection The inspector examined the following areas:
a
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b.
c ~
d.
Construction status Concrete and soils testing laboratory Backfill operations behind the retaining wall of the intake structure Sand-cement fillin the diesel generator building Examination of sand-cement filloperations in the diesel generator building disclosed the following noncompliance.
Paragraph TQR 5.1 of the Topical (}uality Assurance Report states,
"Activities affecting quality of nuclear safety-related structures, systems and components shall be prescribed by documented instructions, procedures or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instruc-tions procedures or drawings".
These documents shall include appropriate quantitative criteria such as dimensions tolerances and operating limits and qualitative criteria such as comparative workmanship samples to assure that the quality assurance activity has been satisfactorily accomplished".
Examination of sand-cement backfill activities disclosed that drawings and instructions are not clear as to whether or not the specified 1-20 ratio of sand to cement is by volume or weight, that water and compaction requirements are not specific, that amounts of ingredients in the mix are not documented and that test data verifying design requirements are being met was not available.
This was identified to the licensee as Infraction 389/80-08-01,
"Inadequate procedural controls on Sand-cement Fill".
Containment (Structural Concrete II) - Observation of Work and Work Activities The inspector performed a followup inspection of structural concrete activi-ties.
Concrete placements observed were pour number NRW 25 in the intake structure retaining wall and pour number CCB 55, west wall of the component cooling building.
Acceptance criteria examined by the inspector appear in the following documents:
a.
PSAR, section 3.8.1 and 3.8.3 b.
gI's 10.3,10.7,'0.70 and 10.71 c.
Flo-2998.473, EBASCO Specification Concrete
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Forms were tight, clean and level, rebar was properly installed and clean.
Placement activities pertaining to delivery time, free fall, flow distance, layer thickness and consolidation conformed to specifications.
Inprocess tests for slump, air content, unit weight and cylinder molding were performed in accordance with procedure requirements.
Batch tickets indicated the specified design mix was being delivered.
Activities were continuously monitored by gC personnel.
An examination of the batch plant indicated materials were being controlled and accurate batch records were being generated.
No deviations or items of noncompliance were identifie o t f
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