IR 05000395/1978018
| ML20062E263 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/16/1978 |
| From: | Ang W, Bryant J, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062E252 | List: |
| References | |
| 50-395-78-18, NUDOCS 7812060035 | |
| Download: ML20062E263 (6) | |
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jo NUCLEAR REGULATORY COMMISSION
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REGION 11
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Report No.: 50-395/78-18 Docket No.: 50-395
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License No.: CPPR-94
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Licensee:
South Carolina Electric and Gas Company
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P. O. Box 764 Columbia, South Carolina 29202 Facility Name: Virgil C. Summer Nuclear Station, Unit No. 1
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Inspection at: Fairfield County, South Carolina Inspection conducted: September 5-8, 1978 Inspectors:
W. P. Ang L. Modenos
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J. C. Bryant, (hief Q
Engineering Support Section No. 1
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Reactor Construction and Engineering Support Branch
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Inspection Summary
~l Inspection on September 5-8, 1978 (Report No. 50-395/78-18)
t Areas Inspected: Work activities associated with the installation of the Q,
reactor vessel; work activities and records associated with safety-related components; work activities associated with ultrasonic testing of safety-i related piping. The inspection involved 48 inspector-hours on site by two i
~l NRC inspectors.
Results:
Of the four areas inspected, no items of noncospliance or deviations were found in three areas; one apparent item of noncompliance was found in one area (Infraction - failure to follow procedures in the area of housekeeping for the reactor vessel internal surfaces, Details I, paragraph 5 (78-18-01)).
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RII Rpt. No. 50-395/78-18 I-1 A-k DETAILS I Prepared by:_
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W. P. Ang, Mechanical Ehgineer 29 ffr
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Engineering Support Section No. 1 Date
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Reactor Construction and Engineering Suppor Branc
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L. Modenos, Reactor InspefEor
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Engineering Support Section No.
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Reactor Construction and Engineering
Support Branch Dates of Inspection: September 5-8, 1978 i
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Reviewed by
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J. C. Bryant, ChtEf
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Reactor Construction and Engineering
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Support Branch
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Persons Contacted I
South Carolina Electric and Gas Company (SCE&G)
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- D. A. Nauman, QA Manager
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- H. I. Donnelly,. Site QA Coordinator i
M. W. Clonts, Mechanical QC Supervisor
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J. Bocock, Mechanical QA Supervisor
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Daniel Construction Company (DCC)
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- R. D. Gunderson, Project Manager
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- W. L. West, Project QA Manager
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- G. R. Curtis, QC Supervisor l
W. Wais, Supervisory Mechanical Engineer
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Westinghouse Electric Company (W)
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D. D. Wieland, Site Manager
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Nuclear Energy Services, Conam Inspection Division E
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,2 RII Rpt. No. 50-395/73-18 I-2
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C. A. Talbott, Supervisory Inspector
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Licensee Action on Previous Inspection Findings nR9 gg This area was not inspected.
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Unresolved Items
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Independent Inspection Effort
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Q The inspector made a walk-through inspection of the reactor plant. The
inspector observed general work activities, cleanliness (housekeeping), storage conditions, protection, and maintenance of
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safety-related equipment. The inspector observed ultrasonic testing for wall thickness determination being performed on a safety-related pipe. The inspector discussed the test procedure (Daniel Construction Procedure WE-I-03 Rev.
- Ultrasonic Inspection)
with the
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nondestructive test inspector.
The nondestructive test inspector's qualification records were
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examined.
No items of noncompliance or deviations were identified.
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5.
Reactor Vessel Installation - Review of Quality Records
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n Pertinent quality related work and inspection records relevant to the V
installed reactor vessel (RV), were examined.
The following records i
for housekeeping inspections, QA audits and QC inspections were examined.
QC Storage Inspection Form MS-2-1 for 3-28-78 and 5-16-78 a.
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QA Surveillance Report #10-3-77 PC on Transporting and Setting of the RV l
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QC Form FQCP 6.2.2 - Inspection of Installation of Equipment -
For the Reactor Vessel - 12-14-77
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QC Housekeeping Inspection Forms FQCP 6.7.1-1 for the Reactor
- i Building
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housekeeping area. SCEG Procedure FQCP 3.5.0 prohibits the use of food
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or tobacco in Zone IV areas.
The inspector noted several cigarette
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butts and an empty cigarette wrapper at the inside bottom of the RV underneath the work platform. Also noted at the bottom were several
loose bolts, a rag with what appeared to be liquid penetrant dye on it
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and loose pieces of plastic tubing. This noncompliance was identified to the licensee as an Infraction, No. 395/78-18-01.
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Safety-Related Components I - Observation of Work and Work Activities i
Components selected from within the reactor coolant pressure boundary
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n were the charging-safety injection pumps A, B & C.
The partially (./
installed pumps were inspected for location, grouting, supports and
maintenance of inspection records. The following procedures were used to verify the installation of these pumps.
SCE&G FQC Procedure 6.2.2 DCC WP-III-06 DCC WP-VI-03
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Alignment of pumps to motors and pipe had not yet been done. SCE&G FQC procedure 6.2.1 provides instructions for alignment. Alignment is to be accomplished at a later date.
No items of noncompliance or deviations were identified.
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Safety-Related Components I - Review of Quality Records h
rertinent quality related work and inspection records of partially installed component cooling system valve XVG-9605-CC, records for receipt inspection, material and fabrication certifications / test reports, storage, installation, and QA audits were examined.
The following records and procedures relevant to valve XVG-9605-CC were examined:
a.
SCEG Field QC Procedure 3.2.0 Rev. 12 - Storage, Handling and Issuing j
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SCEG QC Procedure VII-05 - Iaspection of Cleaning and Storage of j
Fabricated Piping Subassemblies.
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SCEG QC Form MS-2-1 for 2/24/77 to 8/30/78 - In Place Storage
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SCEG QC Form MS-3-1 for 6/24/78, 3/29/78, 12/29/78, 9/28/77, 7/7/77 and 3/30/77 - Inspection of Valves in Storage.
SCEG Material Reviewing Report No. SR-4748 dated 1-24-78
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Daniel Receiving Inspection Report No. 2241
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Gilbert Certificate of Inspection dated 1-6-78
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SCEG Warehouse Receiving Inspection dated 1-17-78
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Anchor Darling Valve Co. Certificate of Compliance for Purchase v
Order No. SN-10109 SR dated 1-4-78 j.
SCEG Surveillance Reports from 1-4-78 to 8-26-78 k.
Anchor Darling Drawing 3319-3 Rev. C-8" 150# Gate Valve 1.
SCEG QA Procedure 12.20 Rev. 4 - Surveillance of Site Activities
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SCEG QA Group Administrative Procedure #1 dated 9/10/76 m.
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Qualifications for Two SCEG Mechanical QA Auditors o.
Daniel QA Audit Report No. 31 for July,1978 p.
Daniel QA Audit Report No. 32 for August,1978 h
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Daniel Certificates for Two Daniel QA Auditors j
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Daniel Work Packet SE-CC-47 s.
Daniel Work Packet SE-CC-37 No items of noncompliance or deviations were identified.
A review of the quality related work and inspection (QC) records of a component within the reactor coolant pressure boundary was done on safety injection pump XPP-43C-CS. Inspection of FQC Form No. 6.2.2-1
" Inspection of Installation of Equipment" confirmed that specifications and installation procedures were met. SCEG Deficiency i
Notice DN-1268M on Anchor Bolts that did not have double auto were i.
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reviewed. SCEG Field Quality Control Procedure 6.2.2 was followed and
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No items of noncompliance or deviations were identified.
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Exit Interview m
The inspector met with licensee representatives at the conclusion of the inspection. The inspector summarized the scope and findings of the
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inspection of the reactor plant, safety-related components and reactor
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vessel.
The licensee was informed that one apparent item of noncompliance was identified.
This concerned the presence of
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cigarette butts and a cigarette wrapper in the bottom of the reactor vessel. No dissenting comments were received from the licensee.
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