ML20212P801
| ML20212P801 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/26/1986 |
| From: | Barnes I, Michaud P, Phillips H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20212P745 | List: |
| References | |
| 50-445-86-01-01, 50-445-86-1-1, 50-446-86-01, 50-446-86-1, NUDOCS 8609030286 | |
| Download: ML20212P801 (5) | |
See also: IR 05000445/1986001
Text
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APPENDIX D
CONSTRUCTION INSPECTION REPORT
U.S.' NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-445/86-01
Permits:
CPPR-126
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50-446/86-01
CPPR-127
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Dockets:
50-445
Category:
A2
50-446
Applicant:
Texas Utilities Electric Company (TUEC)
Skyway Tower
400' North Olive Street
Lock Box al
Dallas, Texas 75201
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Facility Name:
Comanche Peak Steam Electric Station (CPSES), Units 1 & 2
Inspection At:
Glen Rose, Texas
Inspection Conducted:
January 1-31, 1986
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Inspectors:
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H. S. Phillips, Senior Resident Reactor
Date
Inspector (SRRI), Construction, Region IV
CPSES Group
(paragraphs 1, 2, 3, 4, and 6)
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[eP.W.Michaud,ReactorInspector,RegionIV
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(paragraph 5)
Consultant:
EG&G - J. H. McCleskey
Approved:
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I. Barnes, Chief, Region IV CPSES Group
Date
8609030286 860829
ADOCK 05000445
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Inspection Summary
Inspection Conducted: January 1-31, 1986-(Report 50-445/86-01)
Areas Inspected:
Routine, unannounced inspections of Unit I which included
inspection of pipe supports / restraints, and previous NRC inspection findings.
Results: Within the two areas inspected, no violations or deviations were
identified.
Inspection Conducted:
January 1-31, 1986 (Report 50-446/86-01)
Areas Inspected:
Routine, announced and unannounced inspections of Unit 2
.which included plant tours, containment liner and structural steel, pipe
supports / restraints, and applicant actions on previous NRC inspection findings.
Results: Within the four areas-inspect'ed, no violations or deviations were
identified.
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DETAILS
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1.
Persons Contacted
Texas Utilities Generating Company (TUGCo)
K. Anger, Site Design Engineer
R. Babb, Engineer and Site Fire Protection Leader, TUGCo Nuclear
Engineering (TNE)
G. Creamer, TNE
8. Dacko, Licensing Engineer
P. Halstead, Manager, Quality Control (QC)
J. Hicks, Licensing
R. Hooton, Civil Structural Engineer
J. Merritt, Assistant Project General Manager, Unit 2
T. Summers, Records Management Specialist
C. Welch, QC Services Sepervisor
Contractor Personnel
W. Baker, Engineer, Brown & Root (B&R)
R. Moller, Site Project Manager, Westinghouse
The NRC inspectors also interviewed other applicant employees during this
inspection period.
2.
Applicant Actions on Previous NRC Inspection Findings
a.
(0 pen) Unresolved Item (445/8516-U-08; 446/8513-U-08):
Repair and
rework of electrical penetration seals.
On January 17, 1986, the NRC
inspector met with TUGCo representatives to discuss the corrective
-action taken on Design Deficiency Report No. FP-85-063 which required
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Brand Industrial Services Inc., (BISCO) to assure the quality of.
their seals.
TUGCo had identified eight electrical penetration seals which were to
be rew:orked.
This item will remain open until TUGCo complotes their
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review of this matter and any corrective action which is necessary.
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b.
(Closed) Violation (445/8434-V-02):
Failure to report alleged
falsified records per 10 CFR 50.55(e).
The NRC inspector found that
TUGCo had conducted an investigation of this matter to validate the
signatures of QC inspectors and found no other similar occurrences.
This problem arose when two inspectors (one B&R and one Ebasco
employee who works for TUGCo) participated in an inspection, one
inspector lef t before the inspection was completed and the other
inspector signed for him.
The signature and notes added to the
traveler by the second inspector were misleading and he received a
written reprimand.
The inspection was a valid inspection of anchor
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bolts used to secure a. stairway in the Unit 1 Safeguards Building.
Training was conducted to emphasize correct documentation and
preclude repetition.
3.
General Plant Inspections (Unit 2)
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At'various times during the inspection period, the NRC inspectors
conducted general tours of the reactor building and safeguards building.
During the tours, the NRC inspector observed housekeeping practices,
preventive maintenance on installed equipment, ongoing construction work,
and discussed various subjects with personnel engaged in work activities.
No violations or deviations were identified.
4.
Reactor Building Containment Steel Liner and Penetration (Unit 2)
The NRC inspector reviewed the Final Safety Analysis Report (FSAR),
Sections 3.1.5 and 3.8 to identify the design and structural requirements.
Gibbs & Hill Inc., Specification 2323-55-14 implements FSAR requirements
and describes how the containment liner steel is anchored into the
structural concrete which must withstand the pressures and temperatures
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resulting from a spectrum of loss of coolant accidents and secondary
system ruptures.
The welded leak-tight liner wall is 3/8 inch, while that
in the dome and foundation mat is 1/2 and 1/4 inches, respectively.
A
review of the contents of the specification indicated that it was-in
compliance with the requirements of the American Society of Mechanical
Engineers (ASME) Boiler and Pressure Vessel Code,Section III for design
and ACI-359 for fabrication and construction.
The specification also
referenced NRC Regulatory Guide No.1.19, American National, Standards
Institute (ANSI) N45.2.9, Revision 0, and N45.2.11, Revision 2.
Chicago
Bridge & Iron (CB&I) Contract 74-2428 and associated file folders-
(Nos. 4.1.2, 4.1.5, 4.1.5.2, 5.2, 5.5, 6.1, 7.2.1, 7.3, 7.4, 7.6.3,_7.7.1,
7.7.2, 7.7.3, 7.10, 8.9, 8.10, 8.13, and 8.19) were. reviewed to determine
whether work installation for liner plate and mechanical penetrations MV-1:
and 2 were accomplished as required.
The liner plates were receipt.
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inspected, stored, installed, nondestructively' tested, and inspected by
qualified inspectors using appropriate test equipment;
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The required manufacturing and construction records included chemical'and
physical test certifications by offsite vendors,-and onsite welder-
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qualifications, weld metal tests, and installation records which were
appropriately verified by contractur QC personnel.
However, all NDE
' records were not located onsite.
Ultrasonic testing Procedures UTP-1813
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and UTP-25B were not onsite and notes in the CB&I QA manual indicated that
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these two sections of procedures were not received from CB&I.
This item
is open pending the receipt of the records (446/8601-0-01).
Four identical structural steel supports inside containment that are part
of the Safety Injection Support (SIS) system structure were visually
inspected.
The SIS plate (1.5 inches X 80 inches X 34 inches) located at
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elevation 816 feet 10 inches, N. Centerline 13 feet 10.5' inches in
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Room 27, was visually inspected to determine acceptable installation.
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No violations or deviations were identified.
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5.
Safety-Related Pipe Supports / Restraints (Units 1 and 2) _
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The NRC inspector reviewed audits of the installation of pipe'-supports and
restraints. TUGCo audits TCP-85-14, TCP-85-115, TCP-85-79, TCP-85-51 and
TCP-85-39 were performed in accordance with Procedures"DQP-AG-2, DQP-A6-4,
and DQP-QA-15.
Audit report TCP-51 dated September 1982 contained a deficiency (No. 1)
concerning operational work travelers that were transmitted to the vault
without routing them through the site Document Review Group (DRG).
B&R
letters dated January 3,1983, and February 4,1983, documented the
corrective action; however, the audit group did not verify that corrective
action was taken as stated prior to their close out.
This item is open
pending the review of the travelers (446/8601-0-02).
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No violations or deviations were identified.
6.
Exit Interview
An exit interview was conducted February 6, 1986, with the applicant's
representatives identified in paragraph 1 of Appendix E of this report.
During this interview, the NRC inspectors summarized the scope and
findings of the inspection.
The applicant acknowledged the findings.
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