IR 05000389/1980016
| ML17209A591 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/15/1980 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17209A590 | List: |
| References | |
| 50-389-80-16, NUDOCS 8101290369 | |
| Download: ML17209A591 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-389/80-16 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33101 Facility Name:
St. Lucie
Docket No. 50-389 Inspection at St. Lucie site near Ft. Pierce, Florida Inspector:
C.
R.
Mc arland Approved by:
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J'c C. Bryant~-Section Chief, RCSES Branch SUMMARY lZ-rd-7u Date Signed Date Signed Inspection on November 18-20, 1980 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours on site in the areas of inspector followup items; licensee identified items and inspection and enforcement bulletins, circulars and information notices.
Results Of the areas inspected, no items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted Licensee Employees
- B. J.
Escue, Site Manager N. T. Weems, Assistant Manager, gA Construction
- W. M. Hayward, gA Supervising Engineer
- E. W. Sherman, gA Engineer
- J. L. Par ker, gC Supervisor
- T. C. Grozan, Licensing Engineer
- G. Crowell, Engineering Power Plant Site Representative Other Organizations Ebasco Services Incorporated (EBASCO)
R.
A. Garramore, Senior Resident Engineer
- L. V. Pelosi, Site Project Engineer
- G. H. Krauss, Site Project Engineer (designate)
NRC Resident Inspector S.
A. Elrod
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 20, 1980 with those persons indicated in paragraph
above.
The inspector discussed the importance of the licensee's review of IEB's, IEC's and IN's.
The site manager agreed to add the Ebasco senior resident engineer to the routine distribution of these NRC: IE documents.
3.
Licensee Action on Previous Inspection Findings a.
(Closed)
Unresolved Item 389/79-18-01, Use of Expansion Joint Filler Inside Containment Not gualified to DBA Conditions.
The NRC has accepted the limited use of NVKEM 750 as an expansion joint filler material as specified by Ebasco for St. Lucie 2 (reference NRR letter to FPL dated November 7, 1980).
b.
(Open) Infractions 389/80-15 Welding Problems The inspector reviewed the status of the corrective action program for the infractions cited in IE report 50-389/80-15.
Corrective action plans have been initiated, but none have been completed to dat.
Unresol ved Items There were no new unresolved items identified during this inspection.
5.
Independent Inspection The inspector observed wor k inside the reactor building and the auxiliary buildings, and talked to various craft personnel.
The inspector observed that the welding on top of the containment dome was limited to the welding of attachments to structural support steel (not to the containment vessel).
These attachments will support the steel forms for the containment dome concrete work.
These attachments will be removed after the dome concrete work is completed, hence they are not safety related items.
The inspector discussed document control program for design manuals with the Ebasco senior resident engineer.
The need to review the IEB's, IEC's and IN's and the general construction work on the discharge canal was also discussed.
6.
IE Bulletins (IEB)
The inspector reviewed the status of IEB's 80-20, 80-09, 79-24, 79-23 and 79-15.
Discussions with representatives of the licensee and Ebasco indicate that each of the above (except IEB 80-20) will remain open pending more information.
lt (Closed)
IEB 80-20, Failure of Westinghouse Type W-2 Spring Return 'to Nuetral Control Switches.
The inspector reviewed documentation that verifies the licensee's conclusion that IEB 80-20 is not applicable to Unit 2.
As stated in the licensee's response to Region II dated November 13, 1980 only one vendor uses the subject switches in safety related circuits and that vendor, Westinghouse, does not wire the neutral position contact, that is of concern in the Bulletin, to any circuit.
7.
s.
. Inspection and Enforcement Circulars (IEC)
and Information Notices (IEIN)
The inspector held discussions with responsible site personnel to ensure that the applicable following circulars and information notices were received, reviewed, and appropriate action was being taken:
a.
IEC's 80-09 through 80-23 b.
IEIN's 80-15 through 80-41 Licensee Identified Items (LII)
a.
(Open) LII 389/80-12-08 Reactor Coolant Pump Weld Prep Deficiency.
The inspector reviewed the licensee's letters to Region II dated
N
October 15, 1980 and.November 17, 1980.
The November 17, 1980, letter concludes that the item is not reportable per their evaluation.
Either of the two designs used by the Byron Jackson Pump Company is acceptable to the licensee.
The inspector needs to evaluate further the specifications and work procedures applicable to this item.
Motor. Control Center Mountings.
The inspector reviewed the licensee's letter. to Region II dated October 22, 1980 and the EBASCO evaluation of the seismic load factors used for the deSign of the mountings for. motor control centers.
The licensee deems the incident nonreportable, on the basis that if left uncorrected it would not have adversely affected the safety of operation of the equipment.
The inspector has no further questions regarding this matte ~ r>>