IR 05000369/1982023
| ML20062J541 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 07/16/1982 |
| From: | Economos N, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062J310 | List: |
| References | |
| 50-369-82-23, 50-370-82-15, NUDOCS 8208160396 | |
| Download: ML20062J541 (7) | |
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RUCLEAR REGULATORY COMMISSION
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g c 101 MARIETTA STREET.N.W.
ATLANTA, GEORGIA 30303 o
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Report Nos. 50-369/82-23 and 50-370/82-15 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and CPPR-84 Inspection at McGuir si e near Charlotte, NC Inspector:_. P. K.einsorge
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ate Signed n --- ___
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M 7 ///82_.
Approved by:
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N. Econom
- cting Sekion Chief Date' Signed
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Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on June 22-25, 1982 Areas Inspected This routine, unannounced inspection involved 32 inspector-hours on site in the areas of construction progress (Unit 2), spent fuel sturage racks (Unit 2),
safety-related components (Unit 2), reactor vessel installation (Unit 2), and licensee action on previous inspection findings.
Results No violations or deviations were identified.
8200160396 820722 DR ADOCK 05000369 PDR
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- M. S. Starnes, Senior Construction Engineer
- J. W. Willis, Project QA Engineer
- E. B. Miller, Senior QA Engineer
- G. B. Robinson, QA Engineer
- G. T. Ford, QA Projects
- R. M. Williams, QA Technician Other licensee employees contacted included construction craftsmen, tech-nicians and office personnel.
- Attended exit interview L
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2.
Exit Interview
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The inspection scope and findings were summarized on June 25, 1982, with
those persons indicated in paragraph I above. The inspector described the i
areas inspected and discussed the results of the inspection findings listed below. No dissenting comments were received from the licensee.
(0 pen) Unresolved Item 369/82-23-01: " Undercut on Pipe Hanger" paragraph
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3.
Licensee Action on Previous Inspection Findings
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r (Closed) Unresolved Item 370/82-08-01:
" Inspection of Concrete Expansion Anchors on Pipe Supports" This item concerned a pipe support with two i
i loose concrete expansion anchors.
The licensee performed a survey and
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determined that the above was an isolated case.
The condition has been
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corrected. This item is closed.
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4.
Unresolved Items
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l Unresolved items are matters about which more information is required to i
determine whether they are acceptable or may involve violations or devia-
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tions. New unresolved items identified during this inspection are discussed
in paragraph 5.
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5.
Independent Inspection Effort r
Construction Progress The inspector conducted a general inspection of the Unit 2 fuel, auxiliary
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and containment buildings to observe activities such as material handling
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and control, housekeeping and storage.
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With regard to the inspection abo've, on June 24, 1982, the inspector noted undercut adjacent-to a weld on ground-water drainage system nuclear
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safety-related pipe hanger No. MC-1683-WZ-05-R26.
At the time of this
j inspection, it could not be determined whether the undercut exceeded accept-
able limits. The licensee indicated that they would look further into the
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matter. The inspector stated that the above would be identified as unre-i
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solved item 369/82-23-01: " Undercut on Pipe Hanger".
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J Within the areas examined, no violations or deviations were identified.
I 6.
Spent Fuel Storage Racks (Unit 2)
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The inspector reviewed procedures, made a physical inspection'of the Unit 2
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installed spent fuel storage racks and reviewed quality records, to ascer-
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tain whether field activities, pertaining to the installation of spent fuel racks, were accomplished in accordance with NRC requirements, applicable
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j codes, standards and commitments.
a.
Review of Procedures
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The inspector reviewed the below listed documents to ascertain whether
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specifications, drawings, work instructions, and inspection procedures I
had been established to assure technical adequacy for the following
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activities, as they pertain to spent fuel storage racks.
(1) Procurement (2) Receipt Inspection
(3) Storage l
(4)
Installation
Document Title
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MC-1220-120R5 & MC-1200-121R6
" Spent Fuel Pool Fuel Storage Racks" MC-120-49R4
" Fuel Storage Cell Closed
Design" l
j QAP E-3 R16
" Field Procurement of Items l
and Construction Services"
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QAP P-1 R21
" Receiving Inspection" l
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QAP P-3 R13
" Storage Inspection"
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" Housekeeping Requirements" j
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QAP M-18 R8
" Inspection of Structural
Steel Erection"
i QAP M-28 R5
" Inspection of Housekeeping
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Requirements" i
QAP M-30 R8
" Documentation of
Miscellaneous NDE" r
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CP 395 R11
" Identification Marking and Issuing of Miscellaneous Stock for QA Condition Uses" CP 188 R-1
" Installation of Spent Fuel Racks" MCS-1117.00-5 R9
" Specification for Field Fabrication and Erection of Structural Steel, Miscellaneous Steel, and Other Steel Construction for Nuclear Safety-Related Structures" TP/2/A/1500/03J
" Spent Fuel Pool Storage Vault Drag Load Test" TP/2/A/1500/03K
"Index of Spent Fuel Pool Manipulated Crane" b.
Observation of Work and Work Activities The inspector examined installed spent fuel storage racks and reviewed related records to verify that procedural requirements had been met in the following areas:
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Appearance and size of welds (on a sampling basis)
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Cleanliness
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Configuration of the spent fuel racks relative to the assembly drawings
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Defects such as cracks, dents and missing parts
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Identification
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Proper location and orientation
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Seismic restraints in place and gapped
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Damage to the racks or spent fuel pool during installation
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Work performed in accordance with approved procedures
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Adequate QC inspection coverage c.
Review of Quality Records The inspector reviewed receiving inspection records, material certifi-cation documentation, fabrication records, installati n records, NCI(s)
and audits to verify that procurement, receipt inspection and installa-tion of the spent fuel storage racks were consistent with NRC require-ments, applicable codes, standards and commitments.
Within the areas examined no violations or deviations were identified.
7.
Safety Related Components (Unit 2)
The inspector reviewed procedures, made physical inspections, and reviewed quality records to ascertain whether procedures, field activities and records pertaining to the installation of safety-related components were
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consistent with NRC requirements, applicable codes, standards, anc commit-ments.
a.
Review of Quality Implementing Procedures The inspector reviewcd the below listed documents relative to the components indicated below to assure conformance with applicable requirements for receipt inspection; installation testing and inspec-tion; crane testing ana component lifting; and post-installation cleaning, preservation, and inspection.
Document Title QAP E-3 R16
" Field Procurement of Items and Construction Services" QAP P-1 R21
" Receiving Inspection" QAP P-3 R13
" Storage Inspection" QAP L-72 R3
" Housekeeping Requirements" QAP L-73 R4
" Control of Hoisting Equipment" QAP M4 R10
" Visual Inspection and NDE of Welds (ASME III)"
QAP M-5 R8
" Inspection of Structural Grouting" QAP M9 R15
" Mechanical Equipment Installation Inspection".
QAP M10 R16
" Process Control and
.i Inspection of the Application of Torque or Tension to Bolts and i
Studs"
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QAP M-18 R8
" Inspection of Structural-
Steel Erection"
QAP M-21 R12
" Inspection of Field
Welding of Structural Steel, Miscellaneous
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i Steel and Other Steel Construction for Nuclear Structures"
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QAP M-24 R7
" Piping System Cleanliness Inspection"
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j QAP M-28 R5
" Inspection of House-
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i keeping Requirements"
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QAP M-30 R8
" Documentation of
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Miscellaneous NDE"
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MCS-1117.00-5 R9
" Specification for Field Fabrication and Erection of Structural Steel,
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Miscellaneous Steel,and l
other Steel Construction
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for Nuclear Safety Related Structures"
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CP 62 R2
" Receiving Storage and T
Installation of NSSS Vessels" CP 155 R2
" Installation of Steam i
Generator Support i
Columns"
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CP 193 R7
" Cleanliness Procedure for Primary Loop Erection" i
CP 302 R2
" Rigging and Hoisting
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Procedure" CP 395 R11
" Identification Marking
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and Issuing of
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Miscellaneous Stock for
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QA Condition Uses".
Components Name Serial No.
Steam Generater 2C 1483 Accumulator 2A 41618-72-1 Reactor Coolant Pump 2C 6-114E841G02 b.
Observation of Work and Work Activities The inspector made a physical inspection of the above components and reviewed the documents indicated in paragraph 7a and their associated records, for the installed safety related components indicated above,
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to determine whether the requirements of the applicable specifications,
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work procedures and inspection procedures were met in the areas of:
storage, handling and protection; installation; protection after installation; nonconforming items or activities; utilization of QA and inspection (QC) personnel.
c.
Review of Quality Records t
(1) The inspector reviewed pertine..t quality related work and inspec-tion (QC) records, relative to the safety related components indicated above, to ascertain whether the records were in con-formance with established procedures and, whether they reflected
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work accomplishment consistent with applicable requirements in the areas of storage inspection; installation inspection; material and F
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fabrication certification test reports; and nonconformance reports.
(2) The inspector reviewed the six most recent quarterly audits indi-cated below in the areas of scope, frequency, corrective action, and arditor qualification.
Title
" Material and Equipment Receiving and Storage Inspection"
" Mechanical Equipment Installation, Alignment, Disassembly &
Reassembly, and Valve Disassembly and Reassembly"
" Structural Steel Erection and Inspection".
Within the areas examined, no violations or deviations were identified.
8.
Reactor Vessel Installation (Unit 2)
The inspector reviewed procedures and quality records to ascertain whether procedures, field activities and records pertaining to the installation of the reactor vessel were consistent with NRC requirements, applicable codes, standards and commitments.
Review of Quality Records a.
The inspector reviewed the " Equipment Storage Maintenance Inspection Records" P-3A, for the reactor vessel from October 1, 1974 to January 18, 1982, in the areas of adequate access control and main-tenance of cleanliness.
b.
The inspector reviewed the six most recent quarterly audits indicated
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below in the areas of scope, frequency, corrective action, and auditor qualification.
l Title I
" Material and Equipment Receiving and Storage Inspection"
" Mechanical Equipment Installation, Alignment, Disassembly &
Reassembly, and Valve Disassembly and Reassembly".
Within the areas examined, no violations or deviations were identified.
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