ML20205N966
| ML20205N966 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/17/1986 |
| From: | Livermore H, Rogge J, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205N947 | List: |
| References | |
| 50-424-86-09, 50-424-86-9, 50-425-86-04, 50-425-86-4, NUDOCS 8605210030 | |
| Download: ML20205N966 (26) | |
See also: IR 05000424/1986009
Text
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UNITED STATES
[pKfooq'o,
NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA STREET.N.W.
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ATLANTA. GEORGI A 30323
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Report Nos.:
50-424/86-09 and 50-425/86-04
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:
February 1 - March 31,1986
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Inspectors: _
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H. H. Livermore, Senior Resident. Inspector
Date Signed
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Construction
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pn J. F. Rogge, Senior Resident lyspector, Operations
Date Signed
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fet R. J. 'Schepens, R sident Inspector, Construction
Date Signed
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Approved by:
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M. V. Sinkule, Section Chief
Date Signed
Division of Reactor Projects
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SUMMARY
Scope: This routine, unannounced inspection entailed 457 Resident inspection-
hours on site (133 hours0.00154 days <br />0.0369 hours <br />2.199074e-4 weeks <br />5.06065e-5 months <br /> were on backshifts) inspecting: containment and safety
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related structures, piping systems and supports, safety related components,
auxiliary systems, electrical equipment and cables, instrumentation, preopera-
tional test program, quality programs and administrative controls affecting
quality, and follow-up on previous inspection identified items.
The second
corporate management meeting was conducted during this period and the Atomic
Safety and Licensing Board hearings were attended.
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Results: One violation was identified
" Failure to Perform an Adequate System
Walkdown During the Turnover of Safety-Related Systems" - Paragraph 11.
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8605210030 860418
ADOCK 05000424
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DETAILS
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1.
Persons Contacted
Licensee Employees
R. E. Conway, Senior Vice-President, Vogtle Project Director
D. O. Foster, Vice-President, Project Support
- R. H. Pinson, Vice-President, Project Construction
P. D. Rice, Vice-President, Engineering
W. T. Nickerson, Assistant to the Project Director
W. C. Ramsey, Readiness Review Manager
R. W. McManus, Readiness Review
"M. H. Googe, Project Construction Manager
- G. Bockhold, Jr., General Manager Nuclear Operations
- H. P. Walker, Manager, Unit Operations
C. W. Hayes, Vogtle Quality Assurance Manager
- C. E. Belflower, Quality Assurance Site Manager - Operations
- E. D. Groover, Quality Assurance Site Manager - Construction
S. D. Haltom, Quality Assurance Engineering Support Supervisor
W. E. Mundy, Quality Assurance" Audit Supervisor
D. M. Fiquett, Project Construction Manager - Unit 2
- B. C. Harbin, Manager Quality Control
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G. A. McCarley, Project Compliance Coordinator
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"W. C. Gabbard, Regulatory Specialist
,
W. F. Kitchens, Operations Superintendent
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T. Dannemiller, Senior QA Engineer
- J. F. D' Amico, Regulatory Compliance Superintendent
C. L. Coursey, Maintenance Superintendent
M. A. Griffis, Superintendent-Maintenance
N. R. Harris, Quality Control Assistant Manager
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W. R. Duncan, Readiness Review
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R. M. Bellamy, Initial Test Manager
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Other licensee employees contacted included craftsmen, technicians, super '
vision, engineers, inspectors, and office personnel.
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Other Organizations
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- F. B. Marsh, Project Engineering Manager - Bechtel
H. M. Handfinger, Preoperational Test Superintendent - Bechtel
B. F. Hurless, QA Surveillance Specialist - Bechtel
G. F. Trudeau, Readiness Review - Bechtel
W. F. Hindle, Engineer - Bechtel
- Attended Exit Interview
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2.
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Exit Interview (30703C)
The inspection scope and findings were summarized on March 31, 1986, with
those persons indicated in paragraph 1 above.
The inspector described the
areas inspected and discussed in detail the inspection finding listed below.
No dissentirg comments were received from the licensee.
The licensee did
'
not identify as proprietary any of the materials provided to or reviewed by
the inspector during this inspection.
(0 pen) Violation, 50-424/86-09-01 " Failure to Perform an Adequate System
Walkdown During the Turnover of Safety Related Systems" - Paragraph Ell.
(0 pen) Inspector Followup Item, 50-424/86-09-02 " Review Licensee Action
Pertaining to the Restoration of Safety Related Equipment" -Paragraph 11.
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(0 pen) Inspector Followup Item, 50-424/86-09-03 " Review Licensee Resolution
,
of Instrumentation Documentation Forwarding to the Vault During Turnover" -
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Paragraph 11.
)
(0 pen) Inspector Followup Item, 50-424/86-09-04 " Review Projects Revised
]
Response to Quality Concern No. 85V0582" - Paragraph 5.
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(0 pen) Inspector Followup Item, 50-424/86-09-05 "Reviev Licensee Action to
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Resolve HVAC Handswitch Nomenclature" - Paragraph 11.
(0 pen) CDR 86-93 "Procass and Root Valvac" - Paragraph 4
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(Closed) Violation, 50-424/85-37-01 " Failure to- Prescribe Appropriate
Procedures to Control Area Cleanliness" - Paragraph 3.
(Closed) C0R 86-92 and Inspector Followup Item, 50-424/85-63-01 "Trans-
america Delaval
Inc.
(TDI) Diesel
Generator Jacket Water Pump" -
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Paragraph 4.
(Closed) Unresolved Item, 50-424/84-32-01 " Evaluation of Failure to Report a
Potential Significant Deficiency" - Paragraph 4.
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The following NRC exit interviews were attended during the inspection period
by a resident inspector:
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Date
Name
February 14
G. A. Schnebli, L. E. Nicholson
J. R. Harris, J. J. Lenahan
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F. R. McCoy, W. K. Poertner
S. J. Vias
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G. A. Hallstrom
February 28
G. R. Wiseman
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E. H. Girard
T. D. Gibbons
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Date
Name
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(Continued)
March 5
F. R. McCoy
March 17
G. A. Schnebli
March 21
S. J. Vias
W. Kleinsorge
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R. W. Newsome
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M. D. Hunt
T. F. McElhinney
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A. L. Cunningham, et. al.
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March 27
R. W. Wright, R. A. Moore
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L. H. Jackson, J. H. Moorman
March 28
L. E. Nicholson
3.
Licensee Action on Previous Enforcement Matters (92702)
(Closed) Violation 50-424/85-37-01, " Failure to Prescribe Appropriate
Procedures to Control Area Cleanliness". The Inspector has reviewed Georgia
]
Power Company's (GPC) response dated October 23, 1985, and the revised GPC
'
Field Procedure GD-T-17 which incorporated the zone designation requirements
of ANSI N45.2.3.
In addition, since the initial occurrence, the Inspector
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has observed the implementation of zone cleanliness by GPC in various areas.
1
Based on the above reviews and field observation of controlled zone
postings, the inspector has determined that the corrective actions have been
acceptably addressed and are complete.
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4.
Followup on Previous Inspection Items (92701)
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(Closed) CDR 86-92 and Inspector Followup Item 50-424/85-63-01.
Trans-
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america Delaval, Inc. (TDI) Diesel Generator Jacket Water Pump.
The
licensee's evaluation and corrective action as documented in letters dated
February 14, 1986 and March 10, 1986, was reviewed.
The TDI letter dated
,
January 22, 1986, to the NRC was also reviewed.
During this inspection
period the Resident Inspector notified the NRC Vendor Branch that only two
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of the three faulty pump - impellers were onsite.
Followup by the Vendor
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Branch with TDI resulted in further vendor review and final location of the
third impeller in Saudi Arabia.
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(0 pen) CDR 86-93 Process and Root Valve.
The licensee informed the
residents on the progress toward resolution for this item. The licensee has
performed field walkdowns to determine if the hardware has been affected.
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The problem, with a few exceptions, was presented as being limited to the
Valve Designation List and the Quantity Tracking System data differences.
This item continues to remain open until final corrective action is
implemented.
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(Closed) ' Unresolved Item 50-424/84-32-01, "Fai' .re to Report a Potential
Significant Deficiency". This item was reviewed and the Inspector concluded
that the licensee had performed timely identification and reporting of the
Cable Separation issue.
5.
Construction Inspection - Units 1 & 2
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Periodic inspections were made throughout this reporting period in the form.
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of general type inspections in different areas of both facilities. The
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areas were selected on the basis of the scheduled activities and were varied
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to provide wide coverage. Observations were made of activities in progress
to note defective items or items of noncompliance with the required codes
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and regulatory requirements. On these inspections, particular note was made
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of the presence of quality control inspectors, supervisors, and quality
control evidence in the form of available process sheets, drawings, material
identification, material protection, performance of tests, and housekeeping.
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Interviews were made with craft personnel, supervisors, coordinators,
quality control inspectors, and others as they were available in the work
areas.
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The inspector reviewed nu'mbrous construction deviation reports to determine
if requirements were met in the areas of documentation, action to resolve,
justification, and approval signatures in accordance with GPC Field Proce-
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cure No. GO-T-01.
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The inspector cnnducted a review of the licensee's Quality Concern package
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identified as 85V0582.
During the review the inspector questioned the
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project's response in several areas and conducted a meeting on Monday,
March 17, 1986, with the licensee to address the Inspector's questions. The
e
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licensee committed to address the Inspector's questions via a revised
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project response. The inspector advised the licensee that, pending review
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of the project's revised response, this matter will be identified as
Inspector Followup Item 50-424/86-09-04, " Review Project's revised response
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to Quality Concern No. 85V0582.
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Readiness Review Module No.
7,
" Plant Operations and Support", and
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Appendix G, " Measuring and Test Equipment," were reviewed during this
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inspection period.
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No violations or deviations were identified.
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6.
Fire Prevention / Protection and Housekeeping Measures - Units 1 & 2 (42051C)
The inspector reviewed and examined portions of the following procedures
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pertaining to the fire prevention / protection measures and housekeeping
measures to determine whether they comply with applicable codes, standards,
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NRC Regulatory Guides and licensee commitments.
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- SD-T-05, Rev. 6 Fire-Protection Equipment Inspection and Testing
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GD-T-15, Rev. 5 Welding and Cutting
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GD-T-17, Rev. 4 Housekeeping
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The inspector observed fire prevention / protection measures in work areas
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containing safety related equipment during the inspection period to verify
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the following:
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Combustible waste material and rubbish was removed from the work areas
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as rapialy as practicable to avoid unnecessary accumulation of
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combustibles
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Flammable liquids are stored in appropriate containers and in
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designated areas throughout tSe plant
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Cutting and welding operations in progress have been authorized by an
appropriate permit, combustibles have been moved away or safely
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covered, and a fire watch and extinguisher was posted as required
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Fire protection / suppression equipment was provided and controlled in
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accordance with applicable requirements
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No violations or deviations were identified.
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7.
Structural Concrete - Unit 2 (47053C)
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Procedure and Document Review
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The inspector reviewed and examined portions of tFe following proce-
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dures pertaining to the placement of concrete to determine whether they
comply with applicable codes, standards, NRC Regulatory Guides and
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licensee commitments:
CD-T-02, Rev. 17
Concrete Quality Control
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- CD-T-06, Rev. 9
Rebar and Cadweld Quality Control
- CD-T-07, Rev. 8
Embed Installation and. Inspection
CD-T-EO, Rev. 6
Installation and Inspection of Trumpets,
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Rigid Extensions, and Duct Sheathing
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b.
Installation Activities
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- The inspector witnessed portions of the concrete placement indicated
below to verify the following:
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(1) Forms, Embedment, and Reinforcing Steel Installation
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Forms were properly placed, secure, leak tight and clean.
Rebar and other embedment installation was installed in
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accordance with construction specifications < and drawings,
secured, free of concrete and excessive . rust, specified
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distance from . forms, proper onsite rebar bending (where
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applicable) and clearances consistent with aggregate size.
(2) Delivery, Placement and Curing
)
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Preplacement inspection was completed and approved prior to
placement utilizing
a
Pour Card (Procedure
Exhibit
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CD-T-02*18).
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Construction joints were prepared as specified.
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Proper mix was specified and delivered.
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Temperatura control of the mix, mating surfaces,'and ambient
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were monitored.
Consolidation was performed correctly.
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Testing at placement location was properly performed in
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accordance with .the acceptance criteria and recorded on a
Concrete Placement Pour Log (Procedure Exhibit CD-T-02*20).
Adequate crew, equipment and techniques were utilized.
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Inspections during placements were conducted effectively by a
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sufficient number of qualified personnel.
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Curing methods and temperatures were monitored.
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(3) Installation of Tendon Sheaths for Containment Pours Only
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Tendon Sheaths were oriented properly, installed within
specified tolerances, clear and free of damage.
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Pour No.
Location
Inspection Activity
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2-072-001.002
Diesel Generator Building-
Placement
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Level 2 Slab
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2-301-001 A,
Condensate Storage Tanks-
Preplacement, Place-
B&C
Base Slab
ment & Curing
2-010-024A
Construction Opening-
Preplacement &
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Elevation 214'-7" to
Placement
224'-7"
2-051-005 A&B
NSCW Beam & Cross Wall
Preplacement &
Placement
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c.
Rebar Splici,ng
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The Inspector witnessed cadwelding operations for the cadwelds indi-
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cated below to verify the following:
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Inspections are performed during and after splicing by qualified
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QC inspection personnel,
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Each splice was defined by a unique number consisting of the bar
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size, splice type, the position, the operator's symbol, and a
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sequential number.
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Process and crews are qualified.
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The sequential number and the operator's symbol are marked on all
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completed cadwelds.
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Operator's Symbol /
,
Pour No.
Location
Sequential Number
2-010-024
Construction Opening
CR 329
2-010-024
Construction Opening
CR 330
.,
A-111-01B
Control Building Opening
EA 35
A-111-01B
Control Building Opening
EA 36
A-111-01B
Control Building Opening
EA 37
A-111-01B
Control Building Opening
EA 39
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The inspector also conducted random inspections of completed cadwelds
at the locations noted below to verify the following:
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Tap hole does not contain slag, blow out, or porous metal.
)
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Filler metal was visible at both ends of the splice sleeve and at
the tap hole in the center of the sleeve. No voids were detected
at the ends of the :leeves.
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The sequential number and the operator's symbol are marked on all
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completed cadwelds.
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Pour No.
Location
Inspection Activity
[
2-301-001 A,8&C
Condensate Storage Tanks
Anchor Cadwelds
2-01C-45
Reactor Vessel Pourback
Rebar Splice Cadwelds
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No violations or deviations were identified.
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8.
Containment (Prestressing) - Unit 1 (47063C)
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a.
Procedure end Document Review
4
The inspector reviewed and examined portions of the following speci-
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fication, procedure, and drawings pertaining to the installation of
vertical ter. dons, to determine whether they comply with applicable
codes, standards, NRC Regulatory Guides and licensee commitments.
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X2AF04
Technical Provisions for Containment
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Post-Tensioning System
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AX2AF04-100-12
Field Instruction Manual for Installation
of VSL E5-55 Post-Tensioning System Within
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Nuclear Containment Structures, Rev. 9.
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b.
Installation Activities
1
The inspector witnessed portions of the installation activities indi-
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cated below to verify the following:
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The latest i ssue (revision) of applicable drawings or procedures
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are available to the installers and were being used.
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Tendons were free of nicks, kinks, corrosion; were it. stalled in
designated locations; and that the installation sequence and
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technique was per specified requirements.
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Installation crew was properly trained and qualified.
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QC inspection was properly performed by qualified personnel in
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accordance with applicable requirements.
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Adequate protective measures were being taken to ensure. mechanical
and corrosion protection during storage, handling, installation,
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and post installation.
The following tendons were observed:
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Vertical
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Tendon No.
Length
Seq. No.
_ Activity
29-83*
557'
23
Tendon Installation
31-81*
549'
24
Tendon Installation
- Surveillance Tendon
No violations or deviations were identified.
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9.
Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)
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Periodic inspections were conducted to observe containment steel and support
installation activities in progress, to veri #y the following:
Components were being
properly
handled (included bending
or
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straightening).
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Specified clearances were being maintained.
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Edge finishes and hole sizes were within tolerances.
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Control, marking, protection and segregation were maintained during
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storage.
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Fit-up/ alignment meets the tolerances in the specifications and
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drawings.
Some of the more specific structural steel installation activities inspected
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were in the Unit 2 containment building area on A level (elevation 220') and
the pipe racks on C' level (elevation 143').
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No violations or deviations were identified.
10.
Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2
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(48063C)
1
Periodic inspections were conducted to observe construction activities of
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safety-related structures / equipment supports for major equipment outside the
containment to verify that:
4
Materials and components were being properly handled to prevent damage.
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Fit-up/ alignment were within tolerances in specifications and drawing
requirements.
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Bolting was in accordance with specifications and procedures.
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Specified clearances from adjacent components were being met.
One of the more specific safety-related structure installation activities
inspected was the Unit 2 refueling water storage tank liner plate erection
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to verify the following:
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Plate and other materials are controlled in accordance with specifi-
cations, codes, drawings, and procedures.
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Fitting and aligning are properly controlled as required.
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Welding is in accordance with approved procedures by qualified welders,
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Examination and testing are in accordance with the specification,
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codes, drawings, and procedures.
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No violations'or deviations were identified.
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11.
Reactor Coolant Pressure Boundary and Safety Related Pining - Observation of
Work and Work Activities - Unit 1 (49053C) (49063C) (37301)
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During the inspection period, pipe run walkdowns were performed to determine
whether the piping run was installed as shown on approved drawings and in
accordance with applicable construction specifications.
Specific pipe run
walkdowns included a walkdown of the following ASME B&PVC,Section III,
Class I, II & III Piping as listed below:
P&ID NO. REVISION
PIPE RUN INSPECTED
1X4DB122, Rev. 17
Residual Heat Removal (RHR) System Trains A&B
Suction and Discharge Piping in the Auxiliary
Building.
(Line No's. 003-12", 003-14", 028-14",.
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013-3", 039-12", 003-14", 005-8", 007-8", 012-2",
004-14", 027-14", 014-3", 040-12", 006-8",
008-2", 008-8", & 009-8").
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1X4DB133-1, Rev. 15
Nuclear Service Cooling Water (NSCW) System
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Train A Supply and Return Header' Piping in NSCW
Tower, and Supply and. Return Piping to the
Component Cooling Water Pump Motor Coolers.
(Line No's. 023-18", 031-18", 033-18", 004-24",
416-1/2", 417-1/2", 419-1/2", 418-1/2", 420-1/2",
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421-1/2", 045-3", 047-3", 007-12", 008-12",
009-12", 010-12", 181-24", 004-16", 471-2",
390-18", 049-3", 077-2", 063-2", 049-2", 079-2",
067-2", 053-2", 053-3", 005-1", 006-1", & 003-16").
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NSCW Train B Inlet and Outlet Piping to the
Auxiliary Component Cooling Water Heat Exchanger.
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(Line No's. 084-18", 086-18", & 241-2").
1X4DB134, Rev. 14
NSCW Train A Supply and Return Header to CVCS,
SI, CS, and RHR Motor Coolers (Line No's. 004-16",
004-4", 003-4", & 003-16").
1X4DB135-1, Rev. 17
NSCW Train A Inlet and Outlet Piping to the
Auxiliary Component Cooling Water Heat Exchanger
and Supply and Return Header Piping to the
,
Containment Coolers.
(Line No's. 390-18",
175-18", 174-18", 174-14", 179-14", 176-2",
177-2", 178-2", 062-2", 028-2", 182-2", 348-2",
187-14", 222-8", 187-10", 187-8", 195-8", 002-8",
194-8",226-8",002-10",002-14").
IX4DB161-2, Rev. 15
Auxiliary Feedwater (AFW) System Train A&B
Suction and Discharge Piping.
(Line No's.
016-8", 024-8", 046-4", 054-2-1/2", 020-4",
,
025-8", 017-8", 045-4", 042-2-1/2", 003-1/2",
091-1/2",062-2",037-2",063-2").
.
Inspections were performed on a rancom daily basis.
!
)
Specific areas examined during the pipe run walkdown for compliance with the
applicable piping & instrumentation drawings and the Plant Design and
!
Instrumentation Construction Specification No. X4AZ01, were as follows:
Vent and Drain Connections and Locations
Instrumentation Connections and Locations
Valve Installation and Orientation
Line Size and Location
Fittings Type and Location
Pipe / Valve / Fitting End Connections
Hanger Locations and Types
The Inspector reviewed and examined portions of the following procedures
pertaining to system turnover:
GD-T-31, Rev. 1
System and Area Turnover Verification
GD-A-48, Rev. 1
Nuclear Construction System Turnover
GD-A-49, Rev. O
System Walkdown and Master Tracking System
Punchlist Input.
SUM-9, Rev. 6
System Turnover
'
SUM-17, Rev. 6
System Punchlist
- .. _. -. - - -.
-
. - . . - . - . .
-.- - --..- - -.
. . . - - .
.
.
- - -
-
-
-
-
-
.
.
.
12
-
<
During the inspection, the Inspector identified the following discrepancies
regarding the as-built configuration as compared to the P&ID:
-
RHR Train B Valve No. 1-1205-X-403 was found not to be installed
1
l
RHR Trains A&B Valve No's. 1-1205-U4-120 and 1-1205-U4-121 were found
-
to be installed in the incorrect flow direction (i.e., flow is over
seat).
-
NSCW Trains A&B Valve No's. 1HV-11707 and 1HV-11621 were found to be
l
installed in the incorrect flow direction.
-
NSCW Trains A&B Valve No's. IPSV1718 and IPSV1719 were found to be
I
installed on the outlet side of the auxiliary component cooling water
(ACCW) heat exchanger. The piping and instrumentation diagram (P&ID)
shows it to be installed on the inlet side.
,
-
NSCW Train A temperature element No's. 1TE-11641, 1TE-11642, ITE-11643,
and 1TE-11644 were found to be installed in reverse order to what the
P&ID shows.
-
NSCW Train A Valve No's. 1-1202-X-312 and 1-1202-X-313 were found to be
in reverse locations from what the P&ID shows.
The above discrepancies are examples of the licensee's failure to perform an
,
adequate system walkdown during the turnover of safety-related systems.
l
Several meetings were held with the licensee to fully discuss NRC concerns
in this area.
The NRC concern centers on the fact that the above discrep-
ancies were not identified nor documented during' the construction walkdown
per Field Procedure GD-A-49. Also, the fact that these systems (i .e. , RHR &
,
NSCW) have been turned over to Operations for pre-operational testing since
September 18, 1985 and September 14, 1985, respectively and the above
!
discrepancies were not identified on the system punchlist as required by
SUM-17. Also, there does not appear to be any requirement in the Startup
.
Manual for the test supervisor or test engineers to conduct periodic system
walkdowns and to what attributes to inspect so as to ascertain the current
'
system status.
l
The foregoing is considered to be in violation of 10 CFR Part 50,
f
Appendix B, Criterion V and will be identified as Violation 50-424/86-09-01
'
" Failure to Perform an Adequate System Walkdown During the Turnover of
'
l
Safety-Related Systems."
l
'
During the above system walkdowns, the Inspector also noted the Limitorque
h
covers on Valves 1HV-8804B, 1HV-8812A, 1HV-8812B, and 1HV-2138 were not
'
properly secured after maintenance.
The inspector informed the licensee
that, pending review of the licensee's action pertaining to the restoration
of safety-related equipment, this matter will be identified as Inspector
'
Followup Item 50-424/86-09-02 " Review Licensee Action Pertaining to the
I
Restoration of Safety-Related Equipment."
!
_ , - .
,
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13
.
During the above-noted meetings, the licensee identified a problem in the
instrumentation documentation area.
Their investigation into the tempera-
ture elements revealed a problem in the documentation review process and
with it getting to the vault. The Inspector informed the licensee that,
pending review of the licensee action to resolve the problem of instrumen-
tation documentation not - getting to the vault, this matter will be
identified as Inspector Followup Item 50-424/86-09-03, " Review Licensee
Resolution of Instrumentation Documentation Forwarding to the Vault During
>
Turnover".
Selected portions of the Diesel Generator Building Ventilation system and
the Auxiliary Feedwater Pumphouse Ventilation System were inspected for
as-built configuration as compared to FSAR Sections 9.4.7.5 and 9.4.8.5.
The inspector reviewed the following documents and drawings:
FSAR Section 9.4.7 Diesel Generator Building Ventilation System
-
FSAR Section 9.4.8 Auxiliary Feedsater. Pumphouse Ventilation System
-
'
-
P&ID 1X408217, Rev. 8 Diesel Generator Building HVAC System
P&ID 1X4DB227, Rev. 7 Auxiliary Feedwater Pumphouse HVAC System
'
-
OP's Procedure No.11325, Rev. O AFW Pumphouse and DG Bldg HVAC Normal
-
Alignment
During the inspection, the Inspector noted that the following hand switches
on the Control Room HVAC Control Panel QHVC were labeled as " exhaust" fan
j
whereas the P&ID and the Operations Procedure states " supply" fan.
1-HS-12004
AFW Pumphouse Turbine Driven Pump Rm Supply Fan
-
.
1-1492-B7-003-M01
1
- 1-HS-12050A
D.G. Bldg HVAC Train A Rm Supply Fan 001 1-1566-B7-001-M01
!
- 1-HS-12051A
D.G. Bldg HVAC Train A Rm Supply Fan 003 1-1566-B7-003-M01
!
%
i
1-HS-12053A
D.G. Bldg HVAC Train B Rm Supply Fan 002 1-1566-B7-002-M01-
-
,.<:
- 1-HS-12054A
D.G. Bldg HVAC Train B Rm Supply Fan 004 1-1566-B7-004-M01
This matter will be identified as Inspector Followup Item 50-424/86-09-05,
" Review Licensee Action to Resolve HVAC Handswitch Nomenclature".
1
12.
Reactor Coolant Pressure Boundary and Safety Related Piping Welding -
Unit I and 2 (55073C) (55083C)
!
a.
Welding
Periodic inspections were conducted during daily plant surveillances on
l
safety-related pipe welding at various stages of weld completion. The
i
purpose of the inspection was to determine whether the requirements of.
applicable specifications, codes, standards, work procedures and QC
'
procedures are being met as follows:
1
I
i
'
_ _ _ _ _ _ , _ _ _ , _ _ _ - , _ _ , . _ _ _ _ _ ______--_~.
,
. .-~ . , - - _ . - - - ,
_ ,,
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.
1.
,
,
14
-
Work was conducted in accordance with a process sheet which
-
identifies the weld and its location by system, references
procedures or instructions, and provides for production and QC
signoffs.
Welding procedures, detailed drawings and instructions, were
-
readily available and technically adequate for the welds being
~
s
made.
Welding procedure specification (WPS) were in accordance with the
'
-
applicable ASME Code requirements and that a Procedure Qualifica-
tion Record (PQR) is referenced and exists for the type of weld
being made.
That the base metals, welding filler materials, flu ~es, gases, and
-
insert materials were of the specified type and grade, have been
properly inspected, tested and were traceable to test reports or
certifications.
That the purge and/or shielding gas flow and composition were as
-
.
specified in the welding procedure specification and that
protection was provided to shield the welding operation from
adverse environmental conditions.
That the weld joint geometry including pipe wall thickness was
-
specified and that surfaces to be welded have been prepared,
cleaned and inspected in accordance with applicable procedures or
instructions.
-
That a sufficient number of adequately qualified QA and QC
inspection personnel were present at the work site, commensurate
with the work in progress.
-
That the weld area cleanliness was maintained and that pipe
N
alignment and fit-up tolerances were within specified units.
That weld filler material being used was in accordance with
-
welding specifications, that unused filler material was separated
from other types of material and was stored in heated cans, and
stubs properly removed from the work location.
,-
That there were no evident signs of cracks, excessive heat input,
sugaring, or excessive crown.
Or.e of the more specific safety-related piping wolding activities
inspected was the Unit 2 Accumulator Tank Loop No. 2 Discharge Valve
(2-HV-88088) weld buildup.
.
. - .
-
-
.-
.
t
15
.
b.
Radiographic Examination
Procedure Review
The inspector reviewed and examined portions of the following procedure
pertaining to radiographic testing to determine that it complies with
'
the applicable codes, standards, NRC Regulatory Guides and licensee-
commitments. The purpose of this review was to determine whether the
radiographic examination procedure contained sufficient information to
-
assure that parameters were specified and controlled within the limits
'
permitted by the applicable code and other additional specification
requirements.
Procedure No,/ Revision
Title
IX-RT-1-W77/5-12-85
Radiographic Procedure IR-192
Butt Welded Pipe Winter 1977
Winter 1977 Addenda
Work Observation
,
!
The inspector observed the performance of radiographic examinations
including processing of the film for the welds listed below.
The
purpose of the inspection was to determine whether the requirements of
applicable
specifications,
codes,
standards,
work
performance
procedures, and QC procedures are being met as follows:
Applicable drawings, instructions, or travelers clearly specify
-
the examination procedure used and that the application of the
technique utilized was appropriate to the circumstance.
Required equipment and materials as specified in the examination
-
procedure was available at the work station.
-
Specific areas, locations and extent of examination was clearly
defined.
-
Examination attributes such as weld surface preparation, density
limitations, film identification, and geometrical unsharpness
limitations were as specified and consistent with the limits or
ranges given in the procedure.
Radiographic film was processed in accordance with the applicable
-
procedure requirements and processed film was free of chemical and
mechanical blemishes which could interfere with interpretation.
,
..
.-.
--- - l- - .-- - -.--
.
-
- - - -
- - - -
- - - - - -
- -
- - -
- .
.
-
.
1
.
16
.
CODE /
ISO NO.
WELD NO. MAT'L.
SIZE
CLASS
STAGE
TECHNIQUE
<
2K3-1208- 491-W-02
4"
ASME/
Final
Doublewall
123-03
Class II
064-W-03E SS
3"
Final
Doublewall
064-01
Class II
055-W-09
16"
ANSI
1/2
Panoramic
-062-01
B31.1
Complete *
012-W-08R SS
8"
Final /
Doublewall
-012-01
Class II Repair
- For information only.
No violations or deviations were identified.
13.
Reactor Vessel and Integrated Head Package - Unit 1 & 2 (50053C)
Periodic Unit 1 inspections consisted of examinations of the Reactor Vessel
installed in containment and the integrated head package stored on the
i
refueling floor in its designated laydown area to determine that proper
storage protection practices were in place, entry of foreign objects and
debris was prevented, and access was controlled.
During the inspection period, the Unit 1 Reactor Vessel Integrated Head
Package was installed on the Reactor Vessel in support of the Reactor
Coolant System Primary Hydrostatic Test.
The Unit 2 inspections consisted of examinations of the Reactor Vessel
installed in containment and the Reactor Vessel head with the installed
control rod drive mechanisms on the refueling floor in its designated
'
laydown area to determine that proper storage protection practices were in
place and that entry of foreign objects and debris was prevented.
Unit 2 Reactor Vessel work inspected consisted of a review of applicable
procedures, drawings, and tre.veler package and observation of work per-
taining to machining the lower radial core supports. The NISCO Traveler
Package (2-42-1, Revision 0, Core Support Machining) which controlled and
documented this work was reviewed by the inspector.
No violations or deviations were identified.
14.
Reactor Vessel Internals - Unit 1 (50063C)
Periodic inspections were conducted during the inspection period of the
upper and lower internals stored in their designated storage areas to
determine that proper storage protection practices were in place, entry of
foreign objects and debris was prevented and access was controlled.
-
_
-
.
_
_ ._
_ _ - _
, _ . - _ .
, _ _ , -
_
.
. _ . _ _
.
_
_.
_ _ _ - . _
.
'
-
,
17
.
During the inspection period the Inspector. observed the installation of the
!
Unit 1 Reactor Vessel Lower Internals in support of the Reactor Coolant
System Primary Hydrostatic Test.
No violations or deviations were identified.
15. Safety Related Components - Units 1 & 2 (50073C)
j
The inspection consisted of plant tours to observe storage, handling, and
protection; installation; and preventive maintenance after installation of
!
safety-related components to determine that work is being performed in
accordance with applicable codes, NRC Regulatory Guides, and licensee
commitments.
During the inspection the below, listed areas were inspected at various
I
times during the inspection period to verify the following as applicable:
Storage, environment, and protection of components were in accordance
-
with manufacturer's instructions and/or established procedures.
-
Implementation of special storage and maintenance requirements such as:
rotation
of
motors,
pumps,
lubrication,
insulation
testing
(electrical), cleanliness,etc.
-
Performance
of
licensee / contractor
surveillance
activities
and
documentation thereof was being accomplished.
-
Installation requirements were met such as: proper location, placement,
orientation, alignment, mounting (torquing of bolts and expansion
anchors), flow direction, tolerances, and expansion clearance.
Appropriate stamps, tags, markings, etc. were in use to prevent
-
oversight of required inspections, completion of tests, acceptance, and
the prevention of inadvertent operation.
Safety-Related piping, valves, pumps, heat exchangers, and instrumentation
were inspected in the following Unit 1 and 2 areas on a random sampling
basis throughout the inspection period:
-
Residual Heat Removal Pump Rooms
-
Diesel Generator Building
-
Containment Spray (CS) Pumps
Auxiliary Feedwater Pumphouse
-
-
Containment Spray Pump Rooms
Pressurizer Rcoms
-
Main Coolant Pump Areas
-
-
Steam Generator Areas
-
Safety Injection Pump Rooms
-
RHR and CS Containment Penetration Encapsulation Vessel Rooms
-
Component Cooling Water (CCW) Heat Exchangers, Surge Tanks and
Pump Rooms
Cable Spreading Rooms
-
-
-
- - .
- ,,
-
-
, . - - . . -
.
- -
.-
--
.
_
- - .
.
.
.
._
.
-
.
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.
18
-
Accumulator Tank Areas
-
1
Chemical and Volume Control System (CVCS) Letdown Heat Exchanger Rooms
-
Battery & Charger Rooms
-
Nuclear Grade Piping, Valves & Fittings Storage Areas
-
Spent Fuel Pool Heat Exchanger Rooms
>
-
-
Pressurizer Relief Tank Area
CVCS Centrifugal Charging Pumps & Positive Displacement Pump Rooms
-
Bottom Mounted Instrumentation (BMI) Seal Table Area
-
BMI ar.d Supports Under Reactor Vessel
-
-
NSCW Tower Pump Rooms and Pipe Tunnels
No violations or deviations were identified.
16.
Safety Related Pipe Support and Restraint Systems - Units 1 & 2 (50090C)
Periodic random inspections were conducted during the inspection period to
observe construction activities during installation of safety-related pipe
supports to determine that the following work was performed in accordance
'
with applicable codes, NRC Regulatory Guides, and licensee commitments:
Spring hangers were provided with indicators to show the approximate
-
!
" hot" or " cold" position, as appropriate.
'
No deformation or forced bending was evident.
-
Where pipe clamps are used to support vertical lines, shear lugs were
-
,
welded to the pipe (if required by Installation Drawings) to prevent
'
slippage.
-
Sliding or rolling supports were provided with material and/or
lubricants suitable for the environment and compatible with sliding
contact surfaces.
-
Supports are located and installed as specified.
The surface of welds meet applicable code requirements and are free
-
from unacceptable grooves, abrupt ridges, valleys, undercuts, cracks,
discontinuities, or other indications which can be observed on the
welded surface.
-
The inspector conducted a walkdown of the Boron Injection Tank Inlet
and Discharge Piping and the Accumulator Discharge Piping of the Safety
Injection System.
1
.
.
.
.
. .
-
.
.
.
-
.
-
.
-
-
-
-
.
_
_ . . _-
.
.
19
1
-
I
i
,
An inspection of the above attributes was conducted for the following
completed / accepted pipe supports on Unit No. 2:
Pipe Support Dwg No./ Revision
Support Type
!
V2-1208-411-H011, Rev. 4
Pipe Support Assembly
V2-1202-216-H005, Rev. I
Variable Spring
'
V2-1208-411-H014, Rev. 6
Fixed-Pipe Support
V2-1208-095-H019, Rev. 1
Fixed-Pipe Support
V2-1208-411-H019, Rev. 2
Fixed-Pipe Support
No violations or deviations were identified.
17.
Electrical and Instrumentation Components and Systems - Vaits 1 & 2 (51053C)
(52153C)
Periodic inspections were conducted during the inspection period to observe
safety-related electrical equipment in order to verify that the storage,
installation, and preventive maintenance was accomplished in accordance with
applicable codes, NRC Regulatory Guides, and licensee commitments.
During the inspection period an inspection was performed on various pieces
of electrical equipment during storage, installation, ard cable terminating
phase in order to verify the following as applicable:
3
'
Location and alignment
-
i
-
Type and size of anchor bolts
{
-
Identification
l
-
Segregation and identification of nonconforming items
l
-
Location, separation and redundancy requirements
Equipment space heating
-
Cable identification
-
-
Proper lugs used
Condition of wire (not nicked, etc.), tightness of connection
-
Bending radius not exceeded
-
Cable entry to terminal point
-
Separation
-
Unit 1 Electrical Component inspection also consisted of a review of
applicable procedures, drawings, and travel package pertaining to the
Reactor Trip Breaker Replacement Undervoltage Trip Assembly Testing.
The
i
Reactor Trip Breakers are Model No. DS-416.
This modification and testing
-
was conducted by Westinghouse in accordance with their approved QA manual.
.
i
i
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20
-
Procedure and Document Review
The inspector reviewed the following Westinghouse Traveler Package.
-
GAEM-10571-T23, Revision 0
1
Instruction and documentation for the replacement of
Undervoltage Assembly (UV) in the four (4) Reactor Trip
Switchgear Circuit Breakers per drawing IX6A-A19-155
(FCN GAEM-10571) and FEC0 N-68-BF.
Work Observation
The inspector observed the performance of the following steps of the above
procedures on the Train B Rea-tor Trip Breaker Serial No. 02YN0728-4 and the
Train B Reactor Trip Bypass Breaker Serial No. 02YN072B-2:
I
-
Proper interfacing of the UV trip device with the trip bar to ensure
satisfactory trip margin.
-
Breaker closure ard trip by remcving voltage to the UV trip device ten
(10) times to verify satisfactory operation of th: (JV trip device.
-
Trip load check to verify force / load values.
No violations or deviations were identified.
18.
Electrical and Instrumentation Cables and Terminations - Units 1 & 2
(51063C) (52063C)
a.
Raceway / Cable Installation
The inspector reviewed and examined portions of the following
-
procedures pertaining to raceway / cable installation to determine
whether they comply with applicable codes, NRC Regulatory Guices and
licensee commitments.
!
!
-
ED-T-02, Rev. 8 Raceway Installation
[
-
ED-T-07, Rev. 9 Cable Installation
Periodic
inspections
were
conducted to
observe construction
activities of Safety Related Raceway / Cable Installation.
In reference to the raceway installation, the following areas were inspected
to verify compliance with the applicable requirements:
-
Identification
,
-
Alignment
-
Bushings (Conduit)
!
Grounding
-
-
Supports and Anchorages
_
_ __ , - _ _ . _ _ _ _ _ _
_
, _ . - _ .
_-.
.
-
.
.
__
. . . _ _ . . - _
_
-
-
__-
,
-
l
.
21
-
,
In reference to the cable installation the following areas were
inspected to verify compliance with the. applicable requirements:
-
Protection from adjacent construction activities (welding, etc.)
Coiled cable ends properly secured
-
Non-terminated cable ends taped
l
-
i
-
Cable trays, junction boxes, etc., reasonably free of debris
Conduit capped, if no cable installed
-
.
-
Cable supported
Bend radius not exceeded
-
4
-
Separation
b.
Cable Terminations
The inspector reviewed and examined portions of the following proce-
dures pertaining to cable termination to determine whether they comply
with applicable codes,
NRC Regulatory Guides and licensee commit-
ments.
-
ED-T-03, Rev. 7 Cable Termination
In reference to cable terminations the following areas were inspected
to verify compliance with the applicable requirements.
-
Cable identification
-
Proper lugs used
-
Condition of wire (not nicked, etc.), tightness of connection
-
Bending radius not exceeded
-
Cable entry to terminal point
-
Separation
No violations or deviations were identified.
19. Containment and Safety Related Structural Steel Welding - Units 1 and 2
(55053C) (55063C)
Periodic inspections were conducted during daily plant surveillances on
safety-related steel welding at various stages of weld completion.
The
purpose of the inspection was to determine whether the requirements of
applicable specifications, codes, standards, work performance procedures and
QC procedures are being met as follows:
-
Work was conducted in accordance with a process sheet or drawing which
identifies the weld and its location by system, references procedures
or instructions, and provides for production and or signoffs.
Welding procedures, detailed drawings and instructions, were readily
-
available and technically adequate for the welds being made.
i
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-
,-
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-
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22
Welding procedure specification (WPS) were in accordance with the
-
applicable Code requirements and that a Procedure Qualification Record
.
(PQR) is referenced and exists for the type of weld being made.
-
Base metals and welding filler materials were of the specified type and
grade, were properly inspected, tested, and were traceable.
Protection was provided to shield the welding operation from adverse
-
environmental conditions.
-
Weld joint geometry including thickness was specified and that surfaces
to be welded were prepared, cleaned and inspected in accordance with
applicable procedures or instructions.
-
A sufficient number of adequately qualified QC inspection personnel
commensurate with the work in progress were present at the work site.
-
Weld area cleanliness was maintained and that alignment and fit-up
tolerances were within specified units.
-
Weld filler material being used was in accordance with welding
specifications, unused filler material was separated from other types
of material and was stored and controlled properly, and stubs were
properly removed frcm the work location.
-
That there were no visual signs of cracks, excessive heat input, or
excessive crown on welds.
No violations or deviations were identified.
20.
Preoperational Test Program Implementation / Verification - Unit 1 (70302)
(71302)
The inspector reviewed, in part, the implementation of the preoperational
test program. Test program attributer inspected included review of admin-
istrative requirements, document control, documentation of major test events
and deviations to procedures, operating practices, instrumentation calibra-
tions, and correction of problems revealed by testing.
Periodic facility tours were made to assess equipment and plant conditions,
maintenance and preoperational activities in progress.
Schedules for
program completion and progress reports were
routinely monitored.
Discussions with responsible personnel, as they were available, to determine
their knowledge of preoperational program. The Inspector reviewed numerous
operation deviation reports to determine if requirements were met in the
3
areas of documentation, action to resolve, justification, corrective action
and approvals.
Specific observations made included portions of:
,
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23
,
a.
Flushing Program
System
Auxiliary Feedwater System - Trains A&B Pump Suction Lines
b.
Preoperational Tests
Pre-op Test Procedure
Activity Observed
1-300-03
Primary Hydro Prerequisites
- Internals Installation
- Reactor Coolant System Venting
- Reactor Coolant Pump Start
1-3BC-01
- Integrated SI (RHR, SI, & CVCS
Pumps) Recirc. Test Briefing
- Integrated SI Injection Into
Cold Leg
Diesel SOI
Train B Diesel Loading to Verify
Governor Operation
No violations or deviations were identified.
21.
Second Corporate Management Meeting - Units 1 & 2 (303018)
On February 13, 1986, a meeting was held onsite with the persons listed
below to further discuss the change in emphasis from construction to the
operations phases. This meeting was conducted as a followup to the first
meeting conducted on August 27, 1985; see NRC Report 50-424/85-37 and
50-425/85-29.
Topics discussed at the meeting included the status and
handling of construction ana preoperational problems prior to unit
licensing, an update on the regulatory process steps in obtaining a license
recommendation from Region II, the regional inspection activity with
emphasis on the preoperational program the startup test, health physics and
emergency preparedness programs. An overview of the NRC Region II organiza-
tion and responsibilities was presented.
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Attendees
GPC & SCS
A. H. Pinson, Vice President, Vogtle Construction
H. P. Walker, Manager, Unit Operations
A. L. Mosbaugh, Initial Test Program Manager
D. S. Read, Manager, Quality Assurance
A. E. Desrosiers, Superintendent of Health Physics
C. S. Hayes, Vogtle Quality Assurance Manager
C. E. Belflower, Quality Assurance Site Manager - Operations
J. A. Bailey, Project Licensing Manager, Southern Company Services (SCS)
J. L. Leamon, Licensing, SCS
NRC
A. R. Herdt, Branch Chief, Division of Reactor Safety (DRS)
D. M. Collins, Branch Chief, Division of Radiation Safety and Safeguards
F. Jape, Section Chief, Test Program Section (TPS), DRS
M. V. Sinkule, Section Chief, Division of Reactor Projects
J. F. Rogge, Senior Resident Inspector - Operations
H. H. Livermore, Senior Resident Inspector - Construction
G. A. Schnebli, Reactor Inspector, TPS
L. E. Nicholson, Reactor Inspector, TPS
22.
Followup On Headquarters Requests (25014) Units 1 & 2
TI2500/14 (Closed) Solid State Protection System (SSPS) Manual Trip Circuit.
This inspection was performed to determine the electrical location of the
manual trip circuit in relation to output transistors Q3 and Q4. A short-
circuit failure of the output transistors would prevent the automatic
tripping of the associated reactor trip breaker. In this case, the manual trip would have to be utilized to trip the breaker.
By design the manual trip switches should be located between the transistors output and the
undervoltage trip devi:e in the breaker. A recent NRC review indicated that
erroneous controlled schematics showing the manual trip switches before the
transistors could lead to possible wiring errors.
This inspection completes the followup activities as addressed in inspection
report 50-424/85-37 and 50-424/85-29. The inspector observed the licensee
conduct a continuity check of the SSPS vendor wiring to verify proper
circuit configuration for both Train A and B Unit 1 SSPS equipment. The
inspector concluded besed on this demonstration that wiring errors do not
exist for this site.
No violations or deviations were identified.
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23. Atomic Safety and Licensing Board Hearings - Units 1 & 2 (940108)
On March 11 thru 14, 1986, the ASLB conducted hearings on the following
issues:
Contention 7, Groundwater Contamination
Contention 10.1, Dose Rate Effects
Contention 10.5, ASCO Solenoid Valves
The hearings were held at the Burke County Auditorium and were periodically
attended by the following Region II personnel and the resident inspectors:
M. V. Sinkule, Chief, Projects Section 3C
P. W. Jones, Regional Counsel