IR 05000424/1986130
| ML20210D132 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/30/1986 |
| From: | Belisle G, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210D081 | List: |
| References | |
| 50-424-86-130, 50-425-86-60, NUDOCS 8702100022 | |
| Download: ML20210D132 (6) | |
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UNITED STATES
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o NUCLEAR REGULATORY COMMISSION
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j 101 MARIETTA STREET, N.W.
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Report Nos.: 50-424/86-130 and 50-425/86-60 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.:
50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conducted:
De ember 8-12, 1986 Inspector:
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R. W. Wright
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Approved by:
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G. A. Belisle, Secttsn Chief f ate / Signed D
Quality Assurance Program Section Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of verification of as-built construction conditions'.
Results: One violation was identified. This violation is applicable to Unit 2
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only.
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8702100022 870113 DR ADOCK 05000424 PDR
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REPORT DETAILS 1.
Persons Contacted Licensee Employees D. Callaway, Civil Quality Control (QC) Inspector S. D. Chapman, Civil Field Engineer D. Dalenberg, Civ11' Quality Assurance (QA) Inspector (Lead)
- E. D. Groover, QA Site Manager (QASM) - Construction
- C. W. Hayes, Vogtle QA Manager (VQAM)-
- G. A. McCarley, Project Compliance Coordinator
- D. Smith, Construction Engineer, Oglethorpe Power Company Other licensee employees contacted included engineers, technicians, and office personnel.
Other Organizations Vogtle Structural Analysis Mobile Unit (V-SAMU)
Pullman Power Products (PPP)
R. Chandler, QC Inspector B. Kearse, QA Technical Support Group J. Miller, QA Manager H. L. Smith, QC Supervisor W. Wilke, QC Inspector Bechtel Project Field Engineering (PFE)
R. Platoni, Civil / Structural Engineering Group Supervisor i
NRC Resident Inspector
- H. Livermore, Senior Resident Inspector - Construction
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on December 12, 1986, with those persons indicated in paragraph 1 above.
The inspector described the
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areas inspected and discussed in detail the inspection findings.
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dissenting comments were received from the licensee.
Violation, Auxiliary Building Structural Steel Platform Connection (Beam to Column) Not Erected in Accordance with Current Approved As-Built Drawings, paragraph 5.b(1).
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The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
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Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Unresolved Items Unresolved items were not identified during the inspection.
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Verification of As-Builts (Module 37051)
This inspection was conducted to verify by sampling that current design and construction drawings / specifications correctly reflect the as-built condition of the plant, that changes from original design were properly reviewed and approved, and that plant seismic and other stress calculations are based on as-built conditions.
Supplemental review in this inspection area was conducted by other Region II based inspectors (NRC Inspection Report Nos. 50-424/86-18, 86-44, 86-78, 86-87) who inspected various selected piping, electrical and structural systems to assure that the Vogtle Unit I as-built facility is as described in the Final Safety Analysis Report (FSAR).
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Governing Procedures The following Vogtle Electric Generating Plant (VEGP) manuals and procedures were reviewed during this inspection to verify that the licensee had adequate controls over drawings and change requests, and for assuring that the seismic and other stress calculations were based on the as-built plant condition:
Plant Vogtle Field Procedure Manual CD-T-16, R0, Structural Steel and Q-Decking DC-A-01, R14, Drawing Control i
DC-A-03, R15, Change Requests and Notices QC-T-05, Visual Inspection i
VEGP Project Reference Manual, Appendix 2, Engineering Field Procedure Section 3, Code Authorization, Inspection, and Code Stamping Section 5, N-5 Data Report Processing Section 7, Field Control of Transferred Piping Isometrics and Field-Generator Pipe Drawings Section 8, Field Control of Pipe Support Assembly Drawings Section 10, Project Field Engineering Handling of Piping and Tubing Systems, Field Change Requests and Deviation Reports Secti.n 17, Final Design Verification for Safety-Related Piping
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Systems
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VEGP Finalization /As-Built Program Manual FP-7, Piping Reconciliation 75% and 100% (N-STAMP) Finalization Program FP-9,LoadTracking(STRIVE):
Structural Steel and Slab / Walls FP-12, N-STAMP Plating, Certification, and Documentation Appendix 1, N STAMP Program Bechtel QA Manual - ASME Section III - 1980 Edition Section 3, Design Control Section 6, Document Control The inspector conducted discussions with persons responsible for the design and final evaluation of the as-built condition for Plant Vogtle's ASME Class I piping and support systems, and for Seismic Category I structures. Based on these discussions and review of the above control procedures, the inspector concluded the licensee has developed an adequate program to assure that current drawings reflect the as-built status of the plant, b.
Review of As-Builts (1) Structures FSAR, Section 3.8.2, Concrete and Steel Internal Structures of Concrete Containment, and Section 3.8.4, Other Category I Structures, describe applicable codes, standards and specifica-tions for the design, materials, fabrication, construction, inspection and testing of these structures.
The inspector randomly selected the following listed structural steel connections located inside Unit l's containment building and inside Unit 1 and 2's auxiliary building for inspection.
The inspector also examined a low level waste monorail structure located inside the auxiliary building.
The structural steel connections and the monorail structure were inspected to verify that their erection was accomplished in accordance with the latest approved applicable drawings and changes. In general, the subject j
connections and monorail were examined for proper member sizes, joint location, orientation, material, bolting and welding of these assemblies to confirm that these structures were acceptable.
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Beam to Column Connection Nos.. 354, 355, Containment
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356, 357 Bracing Connection Nos.- 245, 246, 247, Unit 1
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248 Drawings:
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1X2048F101, R12; DCN #12; C-FCRB20345
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1X2D48F112, R9
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1X2048F133, R0; DCN #1; DCN #2 1X2D48F131 R2 Beam to Column Connection, Detail 7 Auxiliary
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Building Drawings:
Units 1 and 2
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AX2D08G024,R4;'C-FCRB-8095(Unit 2 only); C-FCRB-17823, DCN #7
' Monorail Structure for Low Level Waste Auxiliary
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Building Drawings
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Unit 1
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AX2008G017, R3; DCN #3; C-FCRB-19740; i
C-FCRB-19798
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Problems were not identified with the Unit 1 ' structural steel as-built inspection program.
However, while examining the
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construction vault inspection records for Unit l's auxiliary
building platform steel erection, a field change request (C-FCRB-8095) which only applies to Unit 2 (Room RB131) was found
in this Unit 1 documentation package.
Subsequent NRC inspection
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of the subject Unit 2 FCR work indicated that the specified 8 x 6 x 1/2 x 16 inch angle was not installed although block 18 of-the FCR had been signed by a field operations engineer on i
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January 4, 1984, indicating this work was completed.
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discrepancy was identified as violation 50-425/86-60-01, Auxiliary Building structural steel platform connection (beam to column) not
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erected in accordance with current approved as-built drawings.
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This discrepancy is applicable to Unit 2 only.
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(2) Piping Systems l
Discussions with responsible V-SAMU and PPP personnel revealed l
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that all Unit 1 ASME Class I piping systems had been N-STAMPED and all Unit 1 ASME Class I, II and III piping systems had been 100%
reconciled (analyzed to their latest as-built condition).
All Unit 1 ASME Class I piping systems and their pertinent hangers
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were found to be wrapped with thermal insulation.
The inspector walked down the Class I portion of the insulated pressurizer
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safety and relief valve piping, and the pressurizer surge line which tied into loop 4 and verified the piping general configura-l tion and hanger locations.
Isometric drawings IX4DL4020, R7 and
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IX4L4A17, R20 were utilized for this walkdown.
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The design bases, design description, inspection and testing requirements for the pressurizer safety and relief valve piping, and the pressurizer surge line (Part of the Reactor Coolant System No. 1201) are discussed in detail in VEGP-FSAR Section 5.4.
The N-5 Code Data Report for this pressurizer piping (system identification 1-1201-W-A) on partial N-5's 1-1201-P-02 and 1-1201-H-03 were examined. Supporting inspection documentation to include weld process sheets, pipe support. installation process sheets, NDE inspection, weld rod requests, hanger package index status reports were given a cursory review for the pressurizer piping portion of the reactor coolant system (RCS). Examination of the stress certification for the subject N-5 Code Data Report indicated the stress analyses and support design for this portion of the RCS had been reconciled with the latest applicable revisions of the as-built /as-installed drawings.
(Although revision'7 is current for drawing 1X4DL4D20 and revision 5 of this drawing was used for the 100 piping reconciliation analyses, the subsequent drawing changes have no effect on the as-built or N-5 status of the system).
Within the areas inspected, one violation was identified for a Unit 2 auxiliary building structural steel platform connection (beam to column) that was not erected in accordance with current approved as-built drawings.
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