ML20137L337
| ML20137L337 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/10/1986 |
| From: | Livermore H, Rogge J, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20137L329 | List: |
| References | |
| 50-424-85-52, 50-425-85-37, NUDOCS 8601270416 | |
| Download: ML20137L337 (18) | |
See also: IR 05000424/1985052
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION ll
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101 MARIETTA STREET, N.W.
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ATL ANTA, GEORGI A 30323
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Report Nos.:
50-424/85-52 and 50-425/85-37
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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 Units 1 and 2
Inspection Conducted:
November 1 - December 2, 1985
Inspectors: @ M
///o/86
H. H. Livermore, Senior Resident
Date Signed
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Inspector, Construction
D M @&
1/ soles
g J. F. Rog'ge, Senior Resident
D' ate Signed
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Inspector, Operations
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n. J. Schepens, Resident
Date Signed
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I spector
ons ruction
ApprovedBy:)(/!
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M. V. Sirikule, Section Chief
te S'igned
Division of Reactor Projects
SUMMARY
Scope:
This
routine,
unannounced
inspection
entailed
238
resident
inspector-hours on site (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> were on backshifts) inspecting:
containment
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and safety related structures, piping systems and supports, safety related
components, auxiliary systems, electrical equipment and cables, instrumentation,
quality programs and administrative controls affecting quality, and follow-up on
previous inspection identified items.
Results: One violation was identified in the area of maintenance, paragraph 4.
9601270416 860113
ADOCK 05000425
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DETAILS
1.
Persons Contacted
Licensee Employees
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R. E. Conway, Senior Vice-President, Vogtle Project Director
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D. O. Foster, Vice-President, Project Support
- R. H. Pinson, Vice-President, Project Construction
P. D. Rice, Vice-President Project Engineering
W. T. Nickerson, Assistant to the Project Director
- D.
G. Smith, Assistant to the Assistant Project Director
D. S. Read, General Manager, Corporate Quality Assurance
W. C. Ramsey, Readiness Review Manager
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H. H. Gregory III, General Manager, Site Prudence Audit Activities
M. H. Googe, Project Construction Manager
G. Bockhold, Jr., General Manager Nuclear Operations
- H. P. Walker, Manager Unit Operation
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0. Batum, Deputy to the Vice-President Engineering
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- C. W. Hayes, Vogtle Quality Assurance Manager
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- C. E. Belflower, Quality Assurance Site Manager - Operations
- E. D. Groover, Quality Assurance Site Manager - Construction
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S. D. Haltom, Quality Assurance Engineering Support Supervisor
W. E. Mundy, Quality Assurance Audit Supervisor
J. E. Sanders, Project Construction Manager - Unit 1
D. M. Fiquett, Project Construction Manager - Unit 2
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- B. C. Harbin, Manager Quality Control
C. R. Brewer, Assistant Quality Control Manager
T. L. Weatherspoon, Assistant Quality Control Manager
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- G. A. McCarley, Project Compliance Coordinator
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W. C. Gabbard, Assistant Project Compliance Coordinator
J. O. Dorough, Administrative Manager
W. F. Kitchens, Operations Superintendent
- P. T. Ciccanesi, Regulatory Compliance Specialist
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T. Dannemiller, Senior QA Engineer
J. F. D' Amico, Regulatory Compliance Superintendent
H. W. Swain, Mechanical QC Section Supervisor
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- C, L. Coursey, Maintenance Superintendent
- M. A. Griffis, Maintenance Superintendent
Other licensee employees contacted included craftsmen,
technicians,
supervisors, engineers, inspectors, and office personnel.
Other Organizations
- H. M. Handfinger, Preoperational Test Superintendent - Bechtel
M. L. Bagale, QA Surveillance Specialist - Bechtel
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B. F. Hurless, QA Surveillance Specialist - Bechtel
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- F. B. Marsh, Project Engineering Manager - Bechtel
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- Attended Exit Interview.
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2.
Exit Interview (30703C)
The inspection scope and findings were summarized on September 26, 1985 with
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those persons indicated in paragraph 1 above. The inspector described the
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areas inspected and discussed in detail the inspection finding listed below.
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No dissenting comments were received from the licensee.
The licensee did
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not identify as proprietary any of the materials provided to or reviewed by
the inspector during this inspection,
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A separate meeting was held during the inspection period with the General
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Manager, Nuclear Operations to discuss control of access to plant equipment
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and necessary interfaces between Operations and Construction.
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(Closed) Inspector Follow-up Item 50-424/85-13-01 " Review Implementation of
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FECO N-17-BF to Install 2 Piece Balance Drum Locknuts into the CVCS Charging
Pumps" - Paragraph 4.
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(0 pen) Violation, 50-424/85-52-01 " Failure to Provide Adequate Maintenance
Procedures for Work on Safety-Related Equipment Appropriate to the
Circumstances".
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The following NRC exit interviews were attended during the inspection period
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by a resident inspector:
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November 22, 1985
J. R. Harris
November 27, 1985
0. Masnyk
3.
Licensee Action on Previous Enforcement Matters (92702)
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(Open) Violation 50-424/85-43-01, 50-425/85-32-01; " Failure to Provide
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Adequate Protection to Safety-Related Components During In-Plant Storage" A
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meeting was held on November 22, 1985 at the Resident's office to discuss
the licensee's response to NRC Violation 50-424/85-43-01, 50-425-85-32-01,
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dated November 15, 1985. The licensee informed the inspectors that they
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will be issuing a supplement to their response.
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4.
Licensee Action on Previous Inspection Items (92701)
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(Closed) Inspector Followup Item, 50-424/85-13-01 " Review Implementation of
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FECO N-17-BF to install two piece balance drum locknuts into the CVCS
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centrifugal charging pumps". The inspector reviewed maintenance work orders
(MWO) No's. 1811851 and 1811852 for the installation of the new two piece
balance drum locknut assembly per FECO N-17-BF, Rev. O on the Train "A" &
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"B" CVCS centrifugal charging pumps.
In addition, the inspector witnessed
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the installation of the new two piece balance drum locknut assembly on the
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Train "B" CVCS centrifugal charging pump.
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During the inspection of the Train
"B" CVCS centrifugal charging pump
balance drum locknut assembly change out on November 16 & 18, 1985, the
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inspector reviewed the following MWO's and procedures and the MWO associated
with a lube oil flush and speed increaser gear inspection.
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MWO 18511851
MWO To Install New Two-Piece Balance Drum Locknut
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Assembly on Train "A" CVCS Centrifugal Charging
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Pump
MWO 18511852
MWO To Install New Two-Piece Balance Drum Locknut
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Assembly on Train "B" CVCS Centrifugal Charging
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Pump
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MWO 18511088
MWO to Provide Maintenance Support for Lube Oil
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Flush and Inspection / Cleaning of Speed Increaser
Gear
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SUM-22, Rev. 10
Maintenance Work Orders
27116-C, Rev. 1
Pacific RL/IJ Pump Inspection
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During the inspection the inspector noted the following discrepancies
regarding the implementation of SUM-22:
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a.
A MWO was issued without all of the applicable documents. FECC N-17-BF
specifies the installation instructions for a new two piece balance
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drum locknut assembly.
MWO 18511852 was issued to implement
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installation of two piece balance drum locknut assembly utilizing FECO
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N-17-BF.
However, upon inspection at the work site FECO N-17-BF was
not part of the MWO package.
In addition, when FECO N-17-BF was
obtained and added to the MWO the inspector noted that it was marked as
an uncontrolled copy and not for construction use.
b.
MWO was issued without appropriate work procedures and instructions.
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MWO 18511852 & 18511851 were issued with maintenance procedure
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No. 27116-C.
This maintenance procedure was for the complete
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disassembly, inspection, and reassembly of a CVCS Pump.
The scope of
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work, however, only required the disassembly of the outboard bearing
and seal to achieve access for replacement of the two piece balance
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drum locknut assembly.
During the preparation of the MWO the
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unnecessary steps were not deleted nor was the necessary step to affect
replacement of the new locknut added,
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MWO 18511088 was issued without appropriate work procedures and
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instructions for the disassembly, inspection, and reassembly of the
speed increase gear for performing the lube oil flush. In essence the
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three MW0's should have been closely coordinated to achieve the overall
work scope intended for the CVCS Centrifugal Charging Pumps.
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c.
MV0's were processed without the ability to perform adequate reviews.
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As identified in paragraph b above, the MWO's contained numerous steps
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that would not be performed and some steps were not included.
Since
each MWO undergoes reviews by representatives from engineering,
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operation, maintenance and quality control, it was evident that proper
reviews could not be performed due to a lack of detailed instructions
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to implement the work scope. In the instance of the QC review for MWO
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18411852, hold points were established for steps that were not
performed and no hold point was established for witnessing the
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installation of the new locknut. This hold point was later established
after FEC0 N-17-BF was added to the work package as mentioned in
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paragraph a. above.
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d.
During the performance of work under MWO 18511852 it was ooserved that
a QC inspector verbally waived a hold point upon recommendation by the
vendor; however, SUM-22 requires an approved and documented consent
waiver prior to work proceeding.
The above discreparcies are examples of failure to provide adequate
control of maintenance activities regarding preplanning and review of
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work.
Several meetings were held with the licensee to fully discuss NRC
concerns in this area.
The NRC concern centers on thr- fact that the
MWO process relies on the worker to identify the problems in execution
of the maintenance and seek resolution of the problem while under
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pressure to complete the work.
In the initial execution of MWO
18511852 it was observed, and later confirmed by the licensee, that the
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workers had not read nor were following the work procedure but instead
were following the verbal directions of the vendor representative.
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The foregoing is considered to be in violation of 10 CFR Part 50,
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Appendix
B,
Criterion V and will be identified as Violation
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50-424/85-52-01 " Failure to provide adequate maintenance procedures for
work on safety-related equipment appropriate to the circumstances".
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Subsequently, the licensee took the following corrective steps prior to
resuming work:
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A maintenance foreman was assigned to supervise all of the MWO's
associated with the CVCS centrifugal charging pumps through their
completion.
MWO's 18511851 & 18511852 were enhanced by specifying the exact
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steps required to be performed in maintenance procedure No.
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27116-C.
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MWO 18511088 was voided due to inadequate instructions and
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reissued as MWO 18512832.
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MWO 18512832 was issued with detailed instructions for performing
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the lube oil flush. Instructions were also providea pertaining to
the completion of some of the work in support of the lube oil
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flush on MWO 18512833,
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Maintenance procedure No. 27115-C, Rev. O for the disassembly,
inspection, and reassembly of the speed increaser gear was issued
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on November 19, 1985.
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MWO 18512833 was issued to disassemble, clean, inspect and
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reassemble speed increaser gear per the maintenance procedure.
Additional instructions were also provided pertaining to the
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intermediate reassembly process in support of the lube oil flush
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per MWO 18512832.
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5.
Construction Inspection - Units 1 & 2
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Periodic inspections were made throughout this reporting period in the form
of general type inspections in different areas of both facilities.
The
areas were selected on the basis of the scheduled activities and were varied
to provide wide coverage. Observations were made of activities in progress
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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
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identification, material protection, performance of tests, and housekeeping.
Interviews were made with craft personnel, supervisors, coordinators,
quality control inspectors, and others as they were available in the work
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areas.
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The inspector reviewed numerous 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
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Procedure No. GD-T-01.
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On November 19, the inspectors attended one of the licensee briefings given
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to their QC inspectors to inform them of how protection under federal law is
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provided.
These briefings were an hour long and were scheduled to be
presented nine (9) times during the day to reach as many QC personnel on
both shifts. The presentation was given by W. C. Whitney, B. C. Harbin and
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L. B. Glenn.
Mr. Whitney described the legal basis for protection
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available to the employee from the Department of Labor and outlined the
legal process that could take place thru the Supreme Court. He stated that
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Vogtle takes the position that the writing of Deficiency Reports are
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protected activities. Mr. Whitney stressed that no-one on the project will
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be retaliated against for identifying a quality concern. The proper level
for resolving a concern was identified as first with supervisor then the
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Quality Concerns Program and finally the NRC which is available at any
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point.
In summary, it was stressed that no-one should get the impression
that concerns were not wanted, but instead must bring them forth as part of
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your employment. Mr. Glenn presented an overview of the Quality Concerns
Program. In the presentation, i t was pointed out that concerns would be
processed and investigated within seven days to preserve the thirty-day time
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frame the employee would have to submit a complaint to the Department of
Labor. It was also stressed that this program was not in place to be used
as a threat to a supervisor. Mr. Harbin stressed the avenues for raising a
concern; and stated that he thought that Vogtle had the best QC inspectors.
He also made the point that as the QC Manager he was available to discuss
any concerns. The meeting was opened for questions.
The inspector noted
that several times during the presentation that emphasis was made to stress
the importance of QC inspectors bringing quality concerns forward for
identification and resolution.
No violations or deviations were identified.
6.
Fire Prevention / Protection and Housekeeping Measures - Units 1 & 2 (42051C)
The inspector observed fire prevention / protection measures throughout the
inspection period. Welders were using welding permits with fire watches and
extinguishers.
Post indicator valves were being maintained in the open
position. Fire fighting equipment is in its designated areas throughout the
plant.
The inspector reviewed and examined portions of the following procedures
pertaining to the fire prevention / protection measures and housekeeping
measures to determine whether they comply with applicable codes, standards,
NRC Regulatory Guides and licensee commitments.
-GD-T-05, Rev. 6 Fire-Protection Equipment Inspection and Testing
-GD-T-15
Rev. 5 Welding and Cutting
-GD-T-17, Rev. 3 Housekeeping
The inspector observed fire prevention / protection measures in work areas
containing safety related equipment during the inspection period to verify
the following:
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Combustible waste material and rubbish was removed from the work areas
as rapidly as practicable to avoid unnecessary accumulation of
combustibles.
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Flammable liquids are stored in appropriate containers and in
designated areas throughout the plant.
Cutting and welding operations in progress have been authorized by an
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appropriate permit, combustibles have been moved away or safely
covered, and a fire watch and extinguisher was posted as required.
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Fire protection / suppression equipment was provided and controlled in
accordance with applicable requirements.
No violations or deviations were identified.
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7.
Containment (Structural Concrete) - Unit 2 (47053C)
a.
Procedure and Document Review
The inspector reviewed and examined portions of the following
procedures pertaining to the placement of concrete to determine whether
they comply with applicable codes, standards, NRC Regulatory Guides and
licensee commitments.
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CD-T-02, Rev. 15
Concrete Quality Control
CD-T-06, Rev. 9
Rebar and Cadweld Quality Control
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CD-T-07, Rev. 8
Embed Installation and Inspection
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CD-T-20, Rev. 6
Installation and Inspection of Trumpets,
Rigid Extensions, and Duct Sheathing
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b.
Installation Activities
The inspector witnessed portions of the concrete placement indicated
below to verify the following:
(1)
Forms, Embedment, and Reinforcing Steel Installation
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Forms were p operly placed, secure, leak tight and clean.
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Rebar and other embedment installation was installed
in
accordance
with
construction
specifications
and
drawings, secured, free of concrete and excessive rust,
specified distance
from forms,
proper on-site rebar
bending
(where
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
CD-T-02*18).
Construction joints were prepared as specified.
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Proper mix was specified and delivered.
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Temperature control
of the mix, mating surfaces, and
ambient were monitored.
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Consolidation was performed correctly.
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Testing at placement location was properly performed in
accordance with the acceptance criteria and recorded on a
Concrete Pikacement Pour Log (Procedure Exhibit CD-T-02*20).
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Adequate crew, equipment and techniques were utilized.
Inspections during placements were conducted effectively
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by a sufficient number of qualified personnel.
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Curing temperature was monitored.
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Pour No.
Location
Inspection Activity
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A-1111-087
Control Building Wall
Preplacement and Placement
2-59A003, 2-59A-004 Auxiliary Feedwater
Preplacement, Placement,
Pump House Base Slab
and Curing
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2-010-042/043
Containment Dome
Preplacement and Placement
No violations or deviations were identified.
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8.
Containment (Prestressing) - Unit 1 (47063C)
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a.
Procedure and Document Review
The inspector reviewed and examined portions of the following
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specification, procedure, and drawings pertaining to the installation
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of horizontal tendons, to determine whether they comply with applicable
codes, standards, NRC Regulatory Guides and licensee commitments.
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-X2AF04
Technical Provisions for Containment
Post-Tensioning System
-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
-1X2AF04-50-5
Horizontal Tendon Elevation-Unit 1
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Buttress #1 to #2
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-1X2AF04-51-4
Horizontal Tendon Elevation-Unit 1
Buttress #3 to #1
-1X2AF04-52-3
Horizontal Tendon Elevation-Unit 1
Buttress #2 to #3
-AX2AF04-78-4
Horizontal Tendon Stressing Data
- 4
-AX2AF04-79-4
Horizontal Tendon Stressing Data
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b.
Installation Activities
The inspector witnessed portions of the installation activities
indicated below to verify the following:
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The latest issue (revision) of applicable dra. ngs or procedures
are available to the installers and were being used.
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Tendons were free of nicks, kinks, corrosion; were installed in
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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
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and corrosion protection during storage, handling,
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installation, and post installation.
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Tendons were stressed in the proper sequence.
All strands in the tendon were moving together during the
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stressing and the tendon is being stressed from both ends
simultaneously.
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Elongatiari measurements were being taken properly and being
compared to the calculated elongation.
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Anchor head lift-off force was being taken and documented
properly.
The stressing operation was being monitored to identify any strand
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slippage.
The following tendons were observed:
Horizontal
From Buttress
Tendon No.
to Buttress
Seq. No.
Activity
116
2 East-1 South
20
Pull Through Dummy
Tendon
117
3 West-2 West
20
Tendon Installation
139*
1 North-3 East
24
Tendon Stressing
240
2 East-1 South
24
Tendon Stressing
- Surveillance Tendon
No violations or deviations were identified.
9.
Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)
Periodic inspections were conducted to observe containment steel and support
installation activities in progress, to verify the following:
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Compenents were being
properly
handled
(included bending
or
straightening).
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
storage.
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Fit-up/ alignment meets the tolerances in the specifications and
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drawings.
No violations or deviations were identified.
10.
Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2
,
(48063C)
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Periodic inspections were conducted to observe construction activities of
safety-related structures / equipment supports for major equipment outside the
containment to verify that:
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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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Specified clearances from adjacent components were being met.
No violations or deviations were identified.
11.
Reactor Coolant Pressure Boundary Piping - Observation of work and work
activities - Unit 1 (49053C) (52063C) (52153C) (37301)
During the inspection period, pipe run walkdowns were performed where piping
installation is near completion 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 portions of the following lines:
P&ID NO. REVISION
PIPE RUN INSPECTED
1X4DB112, Rev. 17
Pressurizer Surge Line (053-14")
Pressurizer Connections to Root Valves
Pressurizer Spray Line (030-4"/030-6")
Pressurizer PORV & Code Safety
Relief Lines to the PRT (059-6", 063-6", 060-3",
063-6", 064-12", 058-6", 057-6", 056-6", 065-6",
066-6", 067-6" & 068-3/4")
.
Specific areas examined during the pipe run walkdown for compliance with the
applicable isometric drawings and the Plant Design and Instrumentation
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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
No violations or deviations were identified.
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12.
Reactcr Vessel Protection - Units 1 & 2 (50053C)
Periodic . inspections were conducted during the inspection period to
determine that proper storage protection practices were in place, entry of
4
foreign objects and debris was prevented, and that access was controlled for
the following:
'
Unit 1 & 2 Reactor Vessel
Unit 1 Integrated Head Package
Unit 1 Upper and Lower Internals
i
No violations or deviations were identified.
'
13.
Safety Related Components - Units 1 & 2 (50073C)
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 equipment was observed at various
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
j
anchors), flow direction, tolerances, and expansion clearance.
l
Appropriate stamps, tags, markings, etc. were in use to prevent
-
oversight of required inspections, completion of tests, acceptance, and
4
!
the prevention of inadvertent operation.
__
The following Unit 1 equipment was inspected:
-
Residual Heat Removal (RHR) Pumps
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Diesel Generators
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Containment Spray (CS) Pumps
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Pressurizer
I
!
!
- i
1
-. - -
_ _ _ . . - . _ . . -
-
. - . . . -, _ - _ _ , _ .
-~,..,.,-.,~,_4-
. , _ . - . - _
- - - . - , , . _
.
_ _ -
.
. _ .
. . _ -
--
--. .-
-
..
-
-
.
l
- l
.
'
'
12
-
Main Coolant Pumps
4
-
Safety Injection Pumps
-
-
Containment Penetration Encapsulation Vessel for Train "B"
-
Component Cooling Water (CCW) Heat Exchangers, Surge Tanks & Pumps
-
-
Cable Spreading Room Train A & B
,
-
-
Accumulator Tanks
'
Reactor Coolant Drain Tank Pumps
-
-
Chemical and Volume Control System (CVCS) Letdown Heat Exchanger
-
Reactor Coolant Drain Tank & Heat Exchanger
-
Reactor Cavity Pumps
-
Battery & Charger Rooms Train A, B, C & D
.,
-
Nuclear Grade Piping, Valves & Fittings
-
Spent Fuel Pool Heat Exchangers
-
Pressurizer Relief Tank
'
CVCS Centrifugal Charging Pumps & Positive Displacement
-
Pump
4
-
Bottom Mounted Instrumentation (BMI) Seal Table
!
'
The following Unit 2 equipment was inspectea:
RHR Pumps
-
-
CS Pumps
I
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CVCS Centrifugal Charging Pumps & Positive Displacement Pump
-
-
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Safety Injection Pumps
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CCW Heat Exchangers Surge Tanks & Pumps
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Accumulator Tanks
,
!
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Pressurizer Relief Tank
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Diesel Generator Fuel Oil Tanks
!
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Nuclear Grade Piping, Valves, & Fittings
.
No violations or deviations were identified.
<
'
14.
Safety Related Pipe Support and Restraint Systems - Unit 1 (50090C)
I
Periodic inspections were conducted during the inspection period to observe
i
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:
l
-
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.
,
l
l
.
, - - , . . , - . - - . - - . . _ - . , .
-
- - . , ,
... - . .,
. . . - .,, .
, - - - . - - - - , . - - - - . - - _ , . , - - - - . - - -
-
-
'
.
13
-
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.
No violations or deviations were identified.
15.
Electrical (Components and Systems) - Units 1 & 2 (51053C)
Periodic inspections were conducted during the inspection period to observe
safety-related electrical
equipment
to verify
that
the
storage,
installation, and preventive maintenance were accomplished in accordance
with applicable codes, NRC Regulatory Guides, and licensee commitments.
During the inspection period the inspector conducted an inspection of the
below listed equipment during storage, installation, and cable terminating
to verify the following as applicable:
Location and alignment
-
-
Type and size of anchor bolt:
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Identification
-
Segregation and identification of nonconforming items
-
Location, separation and redundancy requirements
-
Equipment space heating
-
Cable identification
-
Proper lugs used
-
Condition of wire (not nicked, etc.), tightness of connection
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Bending radius not exceeded
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Cable entry to terminal point
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Separation
The following Unit 1 equipment was inspected:
1-1605-PS-SDA Train "A" Shutdown Panel
1-1605-PS-SDB . Train "B" Shutdown Panel
1-1805-S3-DAD Reactor Coolant Pumps 13.8KV Switchgear
~~
1-1805-S3-CAC Reactor Coolant Pumps 13.8KV Switchgear
1-1804-53-A03 4160V Switchgear 1BA03
1-1804-S3-A02 4160V Switchgear 1AA02
1-1805-S3-BBE MCC 1BBE
1
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_ _
_ _ .
...
-- .
_ _ ___ . _ _
_
1
.
l
1
.
14
.
1-1805-S3-806 IBB06 Switchgear
1-1805-53-807 1BB07 Switchgear
1-1805-S3-BBC MCC IBBC
1-1805-S3-804 1AB04 Switchgear
.
1-1805-S3-805 1AB05 Switchgear
+
1-1805-S3-BBD MCC 1880 Train "B"
'
1-1805-S3-ABD MCC 1ABD Train "A"
j
The following Unit 2 equipment was inspected:
~
'
2BB06 Svitchgear
2-1805-S3-806
2-1805-S3-807 28807 Switchgear
2-1605-S3-SDA Train "A" Shutdown Panel
2-1605-S3-SDB Train "B" Shutdown Panel
No violations or deviations were identified.
!
16.
Electrical (Cables and Terminations) - Unit 1 (51063C)
!
a.
Raceway / Cable Installation
.
i
The inspector reviewed and examined portions of the following
procedures pertaining to raceway / cable installation to determine
whether they comply with appiicable codes, NRC Regulatory Guides and
l
licensee commitments.
4
- ED-T-02, Rev. 8 Raceway Installation
!
- ED-T-07, Rev. 9 Cable Installation
4
'
Periodic inspections were conducted to observe construction activities
i
of Safety Related Raceway / Cable Installation in the Containment,
'
itrol and Auxiliary Buildings.
2
In reference to the raceway installation, the following areas were
inspected to verify compliance with the applicable requirements:
4
i
-
Identification
Alignment
-
-
Bushings (Conduit)
-
4
-
Grounding
-
Supports and Anchorages
In reference to the cable installation the following areas were
inspected to verify compliance with the applicable requirements:
i
Protection from adjacent construction activities (welding, etc.)
-
'
-
Coiled cable ends properly secured
-
Non-terminated cable ends taped
i
A
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.
.
.
.
.
. . .
. . .
.
. .
.-_
--
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15
.
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Cable trays, junction boxes, etc., reasonably free of debris
-
Conduit capped, if no cable installed
Cable supported
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Bend radius not exceeded
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Separation
-
b.
Cable Terminations
The inspector reviewed and examined portions of the following
procedures pertaining to cable termination to determine whether they
comply with applicable codes, NRC
Regulatory Guides and licensee
commitments.
-
.ED-T-08, 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
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Separation
No violations or deviations were identified.
~
17.
Safety Related Piping (Welding) - Unit 1 & 2 (55083C)
Periodic inspections were conducted on safety-related pipe 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:
I
-
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 made.
l
Welding procedure specification (WPS) were in accordance with the
-
applicable ASME Code requirements and that a Procedure Qualification
Record (PQR) is referenced and exists for the type of weld being made,
i
I
!
.
,
16
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That the base metals, welding filler materials, fluxes, 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 thickncss was specified
.
and that surfaces to be welded have been prepared, cleaped and inspected
in accordance with applicable procedures or instructions.
'
-
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That a sufficient number of adequately qualified QA and QC inspection
personnel were present at the work site, commensurate with the worA in
'
progress.
-
That the weld area cleanliness was maintained and that pipe 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.
No violations or deviations were identified.
18.
Preoperational Test Program Implementation / Verification - Unit 1 (70302)
(71302)
The inspector reviewed, in part, the implementation of the preoperational
test program.
Test program attributes inspected included review of
administrative requirements, document control, documentation of major test
events and deviations to procedures, operating practices, instrumentation
calibrations, and correction of problems revealed by testing.
Specific
activities reviewed included the following procedures:
Sum No.
Sum Procedure Title
11, Rev. 2
Construction Acceptance Test Program
12, Rev. 1
Construction Acceptance Test Implementation
Preop No.
Preop Test Procedure Title
1-3BN-17, Rev. O
Refueling Water Storage Tank
1-3KJ-01, Rev. 0 &
Chg. Reg's. No. 1
Diesel Generator Train "A" Starting Air System
'
-_.
-
- .
. _ .
-
_-
.
--
~
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, _-
. _ . _
.
17
The inspector also witnessed portions of the following construction
{
acceptance tests (CAT):
Cat. No.
Equipment / Generic CAT
85-2903
RHR Train "A" (CAT-M-01) Pump & Motor (CAT-E-11)
85-908
ACCW Pump #1 (CAT-M-01)
Other tests witnessed by the inspector during the inspection period
consisted of the train
"A"
safety injection pump lube oil flush.
-
4
The inspector also reviewed the following completed maintenance procedure
,
'
data sheets for the train "A" RHR pump motor prior to witnessing the above
l
listed CAT for the RHR pump & motor.
4
Maintenance Procedure No.
Maintenance Procedure Title
25734-C, Rev. O
High Potential Testing A-C Motors
No violations or deviations were identified.
,
19.
Meeting With Local Officials (94600) - Unit 1 and 2
On November 23, a meeting was held to familiarize local officials of the
City of Waynesboro and Burke County Board of Commissioners with the NRC.
The meeting presented the mission of the NRC, introduction of key NRC
personnel, discussion of lines of communication available to local
officials, ard discussion of the facility status.
The NRC presentea the
scope of the inspection and emergency preparedness programs.
,
The meeting was open for questions during the presentation.
NRC persons
>
involved with the presentation were as follows:
'
D. M. Collins, Chief, Emergency Preparedness and Radiological
Protection Branch, Division of Radiation Safety and Safeguards
M. V. Sinkule, Chief, Reactor Projects Section 20, Division of
Reactor Projects
J. F. Rogge, Senior Resident Inspector, Operations
4
R. J. Schepens, Resident Inspector
20.
Management Meetings (307028) - Unit 1
i
On November 25, 1985 the resident inspector attended a management meeting at
the Region II office in Atlanta, Georgia. The purpose of this meeting was
i
for Georgia Power Company to present Readiness Review Module No. 8
'
" Structural Steel"; Appendix D " Document Control Program; and Appendix E
" Material Control" to the NRC for review.
i
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