ML20133M769
| ML20133M769 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/08/1985 |
| From: | Barnes I, Bundy H, Norman D, Phillips H, Westerman T, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20133M720 | List: |
| References | |
| 50-445-85-11-01, 50-445-85-11-1, 50-446-85-06, 50-446-85-6, NUDOCS 8510280241 | |
| Download: ML20133M769 (6) | |
See also: IR 05000445/1985011
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APP 5NDIX 0
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-445/85-11
Construction Permit:
CPPR-126
50-446/85-06
CPPR-127
Dockets:
50-445
Category:
A2
50-446
Licensee:
Texas Utilities Electric Company (TVEC)
Skyway Tower
400 North Olive Street
Lock Box 81
Dallas, Texas
75201
Facility Name: Comanche Peak Steam Electric Station (CPSES)
Unit 1 and 2
Inspection At:
Glen Rose, Texas
Inspection Conducted:
June 22-August 22, 1985
Inspectors:
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0510200241 051011
ADOCK 00000445
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L. A. 7andell, 5RRP,' Region IV
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(parr.
1, 2, and 3)
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Reviewed by:
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I. Barnes, Group Leader, Region IV CPSES Group
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Approved:
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T. F. Westerman, Chief, Region IV CPSES Group
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Inspection Summary
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Inspection Conducted June 22 through August 22, 1985 (Report 50-445/85-11)
Areas Inspected:
Routine, announced and unannounced inspections of Unit 1
which included a plant tour, review of plant status, and action on applicant
identified potential design / construction deficiency reports.
The inspection
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involved 74 inspector hours by 3 NRC inspectors.
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Results:
Within the areas inspected, no violations or deviations were
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identified.
Inspection Summary
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Inspection Conducted June 22 through August 22, 1985 (Report 50-446/85-06)
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Areas Inspected:
Routine, announced and unannounced inspection of Unit 2 which
included construction status and tours, action on appilcant identified
potential design / construction deficiency reports, concreto placement and
testing, review of reactor coolant pressure boundary (RCPB) piping welding
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procedures, review of safety related components procedures, and review of
safety related piping-work activity and records.
The inspection involved
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274 hours0.00317 days <br />0.0761 hours <br />4.530423e-4 weeks <br />1.04257e-4 months <br /> onsite by 4 NRC inspectors.
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Results:
Within the areas inspected, no violations or deviations were
identiffed.
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DETAILS
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1.
Persons Contacted
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Applicant Personnel / Consultants
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J. T. Merritt, Assistant Project General Manager, Texas Utilities
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Company (TUGCO)
P. E. Halstead, Manager, Quality Control
TUGC0
C. H. Welch, QC Services Supervisor, TUGC0
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Contractor Personnel
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G. R. Purdy, Site QA Manager, Brown and Root, Inc. (B&R)
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W. E. Baker, Welding Engineer, B&R
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2.
Action on Applicant identified Potential Design / Construction Deficiency
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Reports
Reviews were performed by the NRC inspector of selected potential
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design / construction deficiency reports for content, compliance with NRC
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10 CFR Part 50.55(e) reporting requirements, appropriate applicant
evaluation, and adequacy and implementation of corrective action. The
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following reports were closed after NRC review:
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CP-76-03, CP-76-04, CP-77A, CP-77-09, and CP-78A.
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3.
Construction Status and Tours (Unit 2)
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The NRC inspector reviewed the applicant's status reports issued during
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the inspection period.
This reporting of construction activities
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identified that the construction of Unit 1 is 99% complete and Unit 2 is
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75% complete.
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Inspections were performed to observe work in progress and to identify
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work to be inspected during future inspections. General housekeeping, in
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place storage and welding rod material control were spccifically included
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in the inspections,
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No violations or deviations were identified.
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4.
Concrete Placement and Testing (Unit 2)
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The NRC inspector observed various activities associated with placement of
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concrete in the area of the reactor containment equipment hatch.
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Construction forms and embedmont installations were inspected prior to
placement of Pour 201-5805-037. Performance of slump and air content
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testing was observed on two different truck loads.
Placement of concrete
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was observed at various tirres during the activity for conformance with
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procedures and standards.
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The NRC inspector observed 3 day compression strength tests for
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Pour 201-5805-038 (Tests 2600G, H and I) and 28 day compression strength
tests for Pour 201-5805-034 (Tests 2594 C, D, E, and F).
They were all
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performed using compression machine MTE 3031 which was verified to have a
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current calibration sticker. All break values exceeded the specified
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minimum requirements.
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No violations or deviations were identified.
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5.
Review of Safety-Related Components-Procedures
The NRC inspector reviewed the applicant's site QA/QC safety-related
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component implementing procedures for conformance to the Corporate QA
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Program and Plan, dated August 30, 1984.
The B&R QA Manual dated June 10,
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1985, was also reviewed. The following B&R ASME QA Procedures /
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Instructions were reviewed and selectively compared to requirements in
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higher tier QA documents previously described:
CP-QAP-2.1, 3.1, 4.1, 5.1,
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8.1, 8.5, 10.3, 11.1, 12.1, 12.2, 14.1, 16.1, 18.1, 18.6; Ql-QAP-2,1-4,
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2.1-5, 11.1-39; CP-CPM 4.1, 6.11, 7.1, 6.3, 10.2, 14.1. 15.1, 18.1, 22;
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MCP-1, 2; MEl-10-24,10-423, 10-536,10-574; DCP-3; DEI-9; TCP-1; and
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ICP-5.
Specifications 2323-MS-101 and ES-29 were reviewed.
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The NRC inspector identified several typographical errors and unclear
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paragraphs in the FSAR. One example was the last paragraph of page 17.1-21
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which reads, "Each process sheet shall include the date of completion of
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operation or test and the signature of the operator or in TUGCC QA
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reviews selected documentation to that it adequately reflects applicable
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quality requirements." These examples were discussed with the TUGC0 QA
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Director who acknowledged the errors and lack of clarity and he stated
the subject portions of the FSAR are currently in revision and the errors /
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lack of clarity will be addressed.
This is an open item (445/8511-0-36).
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No violations or deviations were identified.
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Review of RCPB Piping-Welding Procedures (Unit 2)
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The NRC inspector reviewed the status of RCPB activities in progress and
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work to be accomplished. The main coolant loop and major piping that
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feeds into the Nuclear Steam Supply System (NSSS) Components have been
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completed. Approximately 40 previous NRC inspections from 1978 through
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1983 evaluated this work activity (procedures, work and records).
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Currently, there is a small amount of miscellaneous piping to be
completed,
in order to inspect this remaining work the NRC inspector
reviewed the following Crown & Root ASME procedures:
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a.
QA Manual
The B&R QA Manual for controlling ASME work activities was issued
September 19, 1981, and one major revision occurred June 11, 1984.
Nine revisions to the manual have occurred since that dato, the
latest being August 13, 1985.
This manual defines the QA program for
ASME Section III, Division 1, 1974 Edition (1974 Summer Addenda for
piping and NSSS component supports; and Winter 1974 Addenda for other
component supports).
The following sections which typically control
welding were reviewed:
Section 3.0 Organization; Section 5.0 -
Procurement Document Control; Section 6.0 - Instructions, Procedures
and Orawings; Section 8.0 - Control of Purchased Items and Services;
Section 10.0 - Control of Special Processes; and Section 11.0 -
Control of Inspections,
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General Piping Procedure CP-CPM-6.9
This general B&R procedure and Appendices 6.9A-I control work
activities for ASME piping.
The following appendices were reviewed
to reaffirm control of selected welding activities:
Drawings; CP-CPM-6.98 - Weld Filler Material Control; and CP-CPM 6.9C
- Material Identification.
No violations or deviations were icantified.
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Review of Safety-Related Piping-Work Activity and Records
The inspection was performed to verify:
the applicant's system for
preparing, reviewing, and maintaining records for safety-related piping,
other than reactor coolant boundary piping; that selected records reflect
compliance with NRC requirements and FSAR commitments for manufacture,
test, and installation of components; and that as-built conditions were
adequately documented.
The sample included both items purchased from
vendors and those manufactured by B&R.
ASME Section III requirements were
used as a basis to inspect the following randomly selected items:
a.
Containment Spray (Isometric BRP-CT-2-SB-065):
(1) CT-2-58-65-1 (Vendor Pipe Spool)
(2) CT-2-SB-65-2 (Vendor Pipe Spool)
(3) CT-2-SB-65-6Q2 (B&R Pipe Spool)
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Residual Heat Removal (Isometric BRP-RH-2-R8-001):
(1) RH-2-RB-01-1 (Vendor Pipe Spool)
(2) RH-2-R8-01-2 (Vendor Pipe Spool)
(3) RH-2-RB-01-3Q (8&R Pipe Spool)
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Safety Injection (Isometric BRP-SI-2-RB-087)
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(1) SI-2-RB-87-2 (Vendor Pipe Spool)
(2) CP-2-RHEXVT-03 (Vendor Expansion Joint)
(3) SI-2-RB-87-SQ2 (B&R Pipe Spool)
Record Review
The following records were reviewed for each item inspected:
QA Receiving Inspection Report
QA Release
Code Data Report
Certified Material Test Report
Vendor Construction and Inspection Records
Fleid Weld Data Cards
No violations or deviations were identified.
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Hardware Review
The installed components were visually inspected for weld quality and to
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verify that marking and traceability requirements had been met.
Welded
joints of this item appeared adequate and the components were traceable to
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records by code data stamps, tag number, or by heat number or code.
No violatfor.s or deviations were identified.
Personnel Qualifications
Personnel who had performed selected tasks were identified during inspec-
tion of records.
Training and experience records for the personnel were
reviewed to verify that employee qualifications and maintenance of records
were current and met requirements.
Four welders and two NDE examiners,
who had performed tasks during installation of items being inspected, were
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identified and their ,ualification records reviewed.
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No violations or deviations were identified.
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Exit Interview
An exit interview was conducted August 29, 1985, with the appilcant
representatives identified in paragraph 1 of Appendix E of this report.
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During this interview, the NRC inspectors summarized the scope and
findings of the inspection.
The appilcant acknowledged the findings.
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