IR 05000389/1979003
| ML17206A757 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/15/1979 |
| From: | Ang W, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A756 | List: |
| References | |
| 50-384-79-03, 50-384-79-3, NUDOCS 7905010243 | |
| Download: ML17206A757 (5) | |
Text
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA,GEORGIA 30303 Report No. 50-389/79-03 Licensee:
Florida Power and Light Company P. 0.
Box 529100 Miami, Florida 33152 Facility Name:
St. 'Lucie Nuclear Plant Unit 2 Docket No.
50-389 License No.
CPPR-144 Inspection at St. Lucie Site, near Ft. Pierce, Florida Inspector:
. P.
Ang Da e
igned Approved by:J.
C.
ryant, ection ief, RCES Branch at Signed SUMMARY Inspection on February 13-15, 1979 I
This routine unannounced inspection involved 22 inspector hours on site in the areas of reactor vessel internals procedures, work observation and quality records; NSSS equipment storage; concrete testing laboratory facilities and work activities; concrete batch plant facilities; gA records storage facilities.
Results Of the 8 areas inspected, no apparent items of noncompliance or deviations were identifie I S
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DETAILS 1.
Persons Contacted Licensee Em lo ees
- B. J. Escue, Site Manager W. T.
Weems, QAC Assistant Manager
+W. M. Hayward, QAC Supervisor-J. I. Parker, Project QC Supervisor Other Or anizations
+R. A. Garramore, Ebasco
+R. E. Havner, Combustion Engineering
+Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 15, 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 Effort The storage yard for NSSS equipment was inspected and the storage condition of the steam generators, pressurizer and the reactor vessel were also inspected.
Protective coatings, dunnage, purge (where required)
and internal atmospheric condition (where required)
were observed.
An inspection of the concrete testing laboratory was performed.
Calibration and condition of equipment were inspected.
Compression tests of two concrete cylinders were observed.
An inspection of the concrete batch plant was performed.
Condition and calibration of equipment were inspected.
An inspection of the QA records storage area wasperformed.
Compliance with QA Instruction QI
QUAD 4 Rev.
1 (Instructions for the collection, storage and maintenace of PSL-2 Quality Assurance Records)
was inspected.
Within the areas inspected, no items of noncompliance or deviations were identifie.
Reactor Vessel Internals " Review of ualit Assurance Im lementin Procedures An inspection was performed to determine whether appropriate and adequate procedures are included or referenced in the QA manual to assure that activities associated with reactor vessel internalsare controlled and performed in accordance with NRC requirements and SAR commitments.
Construction QC Quality Instruction Manual QI 7.1, Rev.
provides instructions for receiving inspection of seismic or safety related material including the reactor vessel internals.
Administrative Site Procedure ASP-17 Rev.l provides for storage and preventative maintenance of safety related equipment including the reactor vessel internals.
Combustion Engineering Procedure CEND 353, Rev.
6 provides instructions for field handling, maintenance and storage requirements for Combustion Engineering furnished equipment.
Contractor Operating Procedures 5-1, 5-7, 5-8, and 5-9 provide proce-dures for testing off-loading equipment, off-loading, and handling of the reactor vessel internals.
The above noted procedures were reviewed for compliance with SAR commitments and NRC requirements.
No items of noncompliance or deviations were identified.
7.
Reactor Vessel Internals - Observation or Work and Work Activities The reactor vessel internals were inspected to ascertain compliance with applicable licensee storage, protection and preservation proce-dures.
The internals were still enclosed in canvas type wrappings installed by the vendor prior to shipment.
In addition the internals were being enclosed in building type structures and had been placed on wood blocks.
No items of noncompliance or deviations were identified.
8.
Reactor Vessel Internals - Review or ualit Records Receipt Inspection Report No. R-79-155 for the reactor vessel internals was examined to determine if licensee requirements and commitments were complied with.
The storage inspection records for the reactor vessel internals were reviewed for compliance with Procedure ASP-17.
No items of noncompliance or deviations were identified.