IR 05000389/1979005
| ML17206A860 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/11/1979 |
| From: | Bryant J, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A858 | List: |
| References | |
| 50-389-79-05, 50-389-79-5, NUDOCS 7906200364 | |
| Download: ML17206A860 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No. 50-389/79-05 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name: St. Lucie 2 Docket No. 50-389 License No.
CPPR-144 Inspection at St. Lucie Site near Fort Pierce, Florida Inspector:
L. Modenos Approved by:, g, J.
C. Bryant Sect on Chief, RCSES Branch 4(d 7g Date Signed ate Signed Accompanying Personnel:
T. E. Conlon SUMMARY Inspection on March 27-29, 1979 This routine unannounced inspection involved 20 inspector hours onsite in the areas of containment steel structures, safety related components, and safety related structures outside containment.,
Results Of the three areas inspected, no apparent items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted Licensee Em lo ees
- B. J.
Escue, Site Manager
"W. Hayward, QA Site Supervisor-J.
W. Adams, QA Engineer
"B. M. Parks, QA Engineer-E.
Sherman, QA Engineer Other licensee employees contacted included construction craftsmen, QC inspectors and QA personnel.
Other Or anizations J. Baysinger, Process Control Specialist, Ebasco L. Shapiro, Lead Mechanical Engineer, Ebasco R. Martin, Lead Support and Stress Engineer, Ebasco-Attended Exit Interview 2.
Exit Interview The inspection scope and findings were summarized on March 29, 1979, with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Ins ection Findin s
Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inde endent Ins ection This effort included inspection of the progress of the containment, the progress of installation of mechanical components in'he auxiliary
"building, containment penetration storage and miscellaneous pipe supports storage area.
The inspector reviewed the following documents, and discussed with Ebasco personnel their methods used for analyzing 2 inch diameter pipe and smaller for class 2 6 3 and non-nuclear system J'
-2" a.
Ebasco's
"Seismic Protection of Class "I" Piping Systems" dated 11-20-78 b.
Ebasco's
"2 Inch 6 Under Piping - Scope of Analysis 6 Documents" dated 11-2-78 The inspector reviewed the following procedures on expansion anchor bolts.
a.
FPL Procedure No.
CSP-3 Rev.
0 Draft, "Installation of Expansion Anchor Bolts!'.
Ebasco Specification No. FL0-2998.469,
"Drilled In Expansion Type Anchors in Concrete" It was noted that the procedures were in draft form and the inspector commented that a
more clear and better control of QC inspection on installation of expansion anchors was required.
The FPL QA personnel acknowledged these comments.
No items of noncompliance or deviations were identified.
6.
Safet Related Com onents - Review of ualit Assurance Im lementin of Work and Work Activities Specific activities associated with safety related components in particular, receipt inspections, storage, surveillance during storage, cleanliness preservation and identification were reviewed to assure that these activities meet applicable requirements.
The following documents were reviewed:
a.
FPL Administrative Site Procedure ASP-17, Rev.
1, titled "Preventive Maintenance" b.
FPL Quality Instruction Manual QI 7.1, Rev. 2, titled "Instructions for Receiving Inspection of Seismic or Safety Related Material" C.
FPL Administrative Site Procedure ASP-3, Rev.
2, titled "Material Control" d.
Material Receiving Report (MRR) and Receipt Inspection Report (RIR)
for:
(1)
Shutdown Cooling Heat Exchanger RIR R-77-419 MRR 04200
-3" (2)
Reactor Drain Pump RIR R-78-531 MRR 08812 (3)
Safety Injection Pumps 2A and 2B RIR No. R-78-669 MRR 09876 RIR R-78-504 MRR 09496 No items of noncompliance or deviations were identified.
7.
Safet Related Structures (Structural Steel 6 Su orts) - Review of ualit Assurance Im lementin Procedures and Observation of Work and Work Activities The following procedures and drawings were examined and used to evaluate receipt inspection, installation, location and use of specified materials for the main steam trestle structure, a safety related structure outside the reactor coolant pressure boundary:
a
~
b.
C.
d.
e.f.
FPL Procedure gl 7.1 (referenced earlier)
Ebasco Drawing 2998-G-489, Rev.
Ebasco Drawing 2998-G-838, Rev.
Lakeside Bridge & Steel Company 9132-4B, Rev.
Lakeside Bridge 6 Steel Company 9132-905, Rev.
MRR-1908 6 RIR No. R-78-824 No items oi noncompliance or deviations were identified.
8.
Containment (Steel Structure and Su orts) - Observation of Work and Work Activities and Review of ualit Records The containment skin plates Sll, S17 and S19 were inspected in their storage locations.
Material test reports and receiving inspection reports were reviewed for conformance with approved procedures and were observed to be adequate.
The heating and ventilating support embeds P3-1, P3-3 and P6-2 in the reactor primary shield and refueling cavity were verified for proper location by Ebasco Drawing Nos.
2998-G-529 and 2998-G-530.
Material test reports and receiving inspection reports were reviewed for confor-mance with approved procedures and were observed to be adequate.
No items of noncompliance or deviations were identified.