IR 05000389/1978009
| ML17206A553 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/22/1978 |
| From: | Bryant J, Modenos L, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A550 | List: |
| References | |
| 50-389-78-09, 50-389-78-9, NUDOCS 7812060362 | |
| Download: ML17206A553 (9) | |
Text
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~v UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No.:
50-389/78-09 Docket No.:
50-389 License No.:
CPPR-144 Category:
A2 Licensee:
Florida Power and Light Company P.
O.
Box 013100 9250 West Flagler Street Miami, Florida 33101 Facility Name:
St. Lucie Plant Unit 2 Inspection at:
Hutchinson Island, Florida Inspection Conducted:
October 17-19, 1978 Inspectors:
E. J. Vallish L. Modenos J.
C. Bryant Reviewed by:
J.
C. Bryant, Chief Engineering Support Section No.
Reactor Construction and Engineering Support Branch
/
Ins ection Summar
/~
Dat Ins ection on October 17-19 1978 (Re ort No. 50-389/78-09)
records associated with the storage of the reactor vessel and safety-related components; progress of erection of containment shell and auxiliary building; safety-related pipe lay-down areas.
This inspection involved
inspector-hours on site by three NRC inspectors.
Results:
No items of noncompliance or deviations were identifie r~p" r
~
ht
RII Rpt.
No. 50-389/78-09 DETAILS I Prepared by:
E.
. Vallish, Mechanical Engineer Engineering Support Section No.
Reactor Construction and Engineering Support Branch L. Modenos, eactor Ins ector Engineering Support Sec ion No.
Reactor Construction and Engineering Support Branch l< (5 7/~
Da e
Dates of Inspection:
October 17-19, 1978 Reviewed by:
'b ~
J.
C. Bryant, hief Engineering Support Section No.
Reactor Construction and Engineering Support Branch
'4 j
7k Persons Contacted a.
Florida Power and Li ht Co
~
(FPL)
- B. J.
Escue, Site Manager
+N. T. gems, Assistant QA Manager
- B. M. Parks, QA Engineer - Mechanical
- J.
W. Adams, QA Engineer
- Mechanical
- K. Van Oeveren, QA Engineering Records Custodian 0. J.
Karsh, QA Auditor b.
Contractor Or anization Ebasco Services Inco orated (EBASCO)
- H. Powers, Process Control Engineer J.
Baysinger, Process Control Specialist 2.
- Denotes those present at the exit interview.
Licensee Action on Previous Ins ection Findin s
Licensee actions on previous inspection findings were not reviewed during this inspectio RII Rpt.
No. 50-389/78-09 I-2 3.
Unresolved Items No unresolved items were identified during this inspection.
4.
Inde endent Ins ection Effort This effort included inspection of the progress of erection of the containment vessel, the safety-related pipe storage areas, the progres's of installation of mechanical components in the auxiliary building and the Bigge Power Corporations handling equipment storage area.
No items of noncompliance were identified.
Reactor Vessel Installation - Review of A I lementin Procedures The following documents were reviewed which assure that activities associated with reactor vessel storage, handling and installation are controlled and also conform to the applicable requirements concerning receipt inspections, special protection requirements during storage, inspection and recordkeeping requirements and crane and rigging tests to be performed prior to vessel lifting:
Combustion Engineering (CE) Engineering Procedure 71172-3 RO, titled,
"Field Receiving, Handling, Interim Storage and Installation of Reactor Vessel Assembly".
FPL Procedure AQR 13.0 R2 titled,
"Handling, Storage and Preservation Control."
c.
Bigge Company's Procedure F-DF-2 titled,
"Load Testing of the Bigge Barge Offloading Facility -
Special Design Handling Equipment per Section 7.3 ANSI N45.2.2."
d.
"Receipt Inspection of Nuclear Safety-Related Materials, Parts and Components for Plants Under Construction."
e.
FPL Procedure QP 10.2 titled, "Inspection of Plant Construction."
f.
FPL Procedure QP 13.1 titled, "Handling Storage and Shipping of Material, Parts and Components at the Site During Construction."
RII Rpt.
No. 50-389/78-09 I-3 g.
CE Instruction Manual titled, "React. or Vessel Assembly."
No items of noncompliance were identified.
6.
Reactor Vessel Installation - Observation of Work The reactor vessel and its closure head were inspected in their storage locations.
The units were enclosed in chain link fencing with a
padlocked gate.
The storage area is away from the routine construction vehicle traffic and adequate. protection was observed.
The supporting dunnage, protective seals and protective coating conformed to the approved procedures and were observed to be adequate.
No items of noncompliance were identified.
7.
Reactor Vessel Installation - gualit Record Review Records of the gC inspections performed on the reactor vessel and closure head, from (receipt on site)
March 1978 thru October 3, 1978, were reviewed.
The inspections were conducted weekly as required and indicated that protection requirements were maintained.
No items of noncompliance were identified.
8.
Safet -Related Com onents
- Review of gA Im lementin Procedures The following documents were reviewed which assure that the specific activities associated with safety-related mechanical components are cont, rolled and performed in accordance with the applicable requirements.
a.
CE Engineering Procedure No. 71272-3 RO titled, "Requirements f'r Field Receiving, Handling, Interim Storage and Installation of Steam Generator with Strippable Coating."
b.
CE Engineering Procedure ho. 71372-2 RO titled, "Requirements for Field Receiving, Handling, Interim Storage and Installation of Pressurizer Protected with Strippable Coating."
c.
CF. Instruction Manual titled, "Pressurizer St.
I.uric Plant ho.
2."
RII Rpt.
No. 50-389/78-09 I-4 d.
CE Instruction Manual titled, "Steam Generators St. Lucie No. 2."
e.
FPL Procedure QP 7.2 (referenced earlier)
f.
FPL Procedure QP 10.2 (referenced earlier)
g.
FPL Procedure QP )3.0 (referenced earlier)
h.
FPL Procedure QP 13.1 (referenced earlier)
These procedures include requirements for receipt inspections and reports; special requirements for environment control; installation, testing and inspection activities using qualified personnel; and the establishment of crane testing and component lifting procedures prior to lifting the safety-related component.
No items of noncompliance were identified.
9.
Safet -Related Corn onents I - Work Observation The steam generators and the pressurizer were selected as two representative components wi thin the reactor coolant pressure boundary.
These components were inspected on site, in their storage locations.
These units were enclosed in a chain link fence with padlocked gate.
The storage area was observed to be away from the heavy routine construction traffic and adequate protection was observed.
The supporting dunnage and protective sealing devices were in acceptable condition.
The steam generators internals were provided with a nitrogen atmosphere and all the components were externally protected by a heavy plastic. polymer coating.
No signs of mishandling could be detected and the units were identified adequately.
Weekly in-storage inspections are made by the licensee of these units.
No items of noncompliance were identified.
10.
Safet -Related Com onents I -
ualit Record Review The QC inspection records of the steam generators and the pressurizer were reviewed.
Records indicated weekly QC inspections in accordance with the approved procedures, from receipt on site in April 1978 thru October 13, 1978, for the steam generators and biweekly inspections on the pressurizer from receipt in April 1978 thru October 13, 1978.
Inspection of the records indicated that the required storage conditions were maintaine RII Rpt.
No. 50-389/78-09 I-5 Also reviewed were the licensee's procurement package of records for these components.
Included were receiving inspection reports, material physical and chemical certifications and certifications of compliance with procurement requirements.
Records correlated the identification and description of the components.
The licensee's representative stated that their procurement office audits the vendors certification process to assure that the certifications are valid.
Deviations from the original contract requirements were documented and included in the records.
Certifications of their completeness were also reviewed.
The following recent QA audits relating to these safety-related components, were reviewed.
Records indicated that the audits were performed as scheduled and the deficiencies were recorded as dispositioned in a timely manner.
a.
QAC-PSL-78-3,
"Materials Handling - Lift Equipment Operational Safeguards Operation and Maintenance of LiftEquipment."
b.
QAC-PSL 2-78-28, "Material Control",
c.
QAC-PSL 2-78-l6, "Offload Transport and Placement into Storage of Steam Generator and Pressurizer Vessel",
d.
QAC-PSL 2-78-17, "Records - Bigge Power Corp."
A random selection and review was made of the audit, personnel's training and qualification records.
All reviewed were trained and qualified in the requirements for the work they perform.
The quality records reviewed of the components described above, reflected the conditions observed during the physical inspection of these components as described earlier in this report.
No items of noncompliance were identified.
ll.
Exit Interview At the end of this inspection a meeting was held with the licensee's representatives denoted in paragraph
and others, to discuss the results of this inspection.
Items discussed included the reactor vessel and other safety-related components, QA implementing procedures, work observation and quality records; progress of erection of the containment shell and auxiliary building; and the safety-related pipe storage area RII Rpt.
No. 50-389/78"09 I-6 The licensee was informed that no items of noncompliance or new unresolved items were identified.
The licensee's representative acknowledged these findings.