ML19322E366
| ML19322E366 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/12/1980 |
| From: | Beach A, Crossman W, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19322E363 | List: |
| References | |
| 50-382-80-02, 50-382-80-2, IEB-79-02, IEB-79-2, NUDOCS 8003270285 | |
| Download: ML19322E366 (6) | |
See also: IR 05000382/1979002
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U. S. NUCLEAR REGULATORY COMMISSION
CFFICE OF INSPECTION AND ENFORCEMENT
>
REGION IV
Report No. 50-382/80-02
Docket No. 50-382
Category A2
Licensee:
Louisiana Fower and Light Company
142 Delaronde Street
New Orleans, Louisiana
70174
Facility Name:
Waterford Steam Electric Station, Unit No. 3
Inspection at:
Waterford Site, Taft, Louisiana
Inspection conducted:
January 29-31 and February 1, 1980
2[/2/80
Inspectors:
~ Reactor Inspector, Projects Section
Date
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p(Paragraphs
. C. Stewart,
1, 2, 3, 4, 5 & 8)
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[ L. D. Gilbert, Reactor Inspector, Engineering Support
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Secticn (Paragraph 7)
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B. Beach, Reactor Inspector, Engineering Support
Date
Section (Paragraph 6)
Approved:
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W. A. Crossman, Chief, Projects Section
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R. E. Hall, Chief, Engineering Support Section
Date
80032702 25
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Inspection Summary:
Inspection on January 29-31 and February 1, 1980 (Report No. 50-382/80-02)
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Areas Inspected: Routine, unannounced inspection of construction activities
related to a follow-up review of in-process welding activities on Reactor
Coolant pressure boundary piping; a follow up on the licensee's response to
IE Bulletin 79-02, Revision 2; procedure review and observation of work
related to care and maintenance of installed safety-related components.
The
inspection involved sixty-five inspector-hours by three NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS
1.
Persons Contacted
Principal Licensee Employees
- T. Gerrets, QA Manager
- B. Brown, QA Engineer
- C. Chatelain, QA Engineer
- J. Woods, QA Engineer
- C. Decareaux, Project Coordinator
D. Lester, Plant Manager
_0ther Personnel
- J.
Crnich, Site Manager, Ebasco
- R. Milhiser, Project Superintendent, Ebasco
R. Hartnett, QA Site Supervisor, Ebasco
- L.
Stinson, Site QA Program Manager, Ebasco
- J. Britt, Site Manager, Nuclear Installation Services Company (NISCO)
J. Moska, QA Manager, NISCO
W. Barthle, Piping Superintendent, NISCO
J. Ball, Welding Engineer, NISCO
T. Pruitt, Site Auditor, NISCO
The IE inspectors also interviewed other licensee and contractor personnel
including members of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Licensee Action on Previous Inspection Findings
(Open) Interim Construction Deficiency Report (CDR):
" Procedural and Per-
formance Deficiencies in Ultrasonic Testing of Structural Welds Performed
by Industrial Engineering Works," dated January 2, 1980.
The IE inspector
reviewed the status of the progress in the licensee's evaluation of the
extent and magnitude of the deficiencies and the corrective action necessary.
As noted in the Interim Report, the ultrasonic testing (UT) examination
deficiencies involve the welds on the Reactor Coolant pump supports, Reactor
Coolant system pipe stops, pipe whip restraints, pressurizer support, Safety
Injection tank supports and framing over the steam generators.
It is esti-
mated by the licensee that 3000 welds are involved that require individual
review. As of January 28, 1980, the A/E has completed review of the welds
on the framing over the steam generators involving 1022 welds. Approximately
396 full penetration welds can be reduced to partial penetration, thereby,
leaving 626 welds that need UT re-examination.
The A/E is continuing weld
analysis of the remaining support structures.
This matter will be reviewed by the IE inspector during a subsequent site
inspection.
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(Closed) Infraction (50-382/79-03):
Failure to Follow Approved Drawing -
Mounting / Installation of Class IE 4160 Volt Switchgear.
During this
inspection, the IE inspector reviewed the corrective action implemented
in correcting the original discrepancy in the drawing details and disposition
described by the licensee in their letter, dated April 27, 1979.
The review
by the IE inspector included the review of Nonconformance Report W3-1295,
dated March 20, 1979, which reflects a close out, dared September 24, 1979.
The IE inspector had no further questions regarding this matter.
3.
Safety-Related Components - Procedures - Protection After Installation
During the inspection, the IE inspector reviewed the licensee's subcontactor's
procedures involving the storage, maintenance and protection of safety-related
components after installation.
Procedures and instructions reviewed included
the following:
Ebasco Procedure ASP-IV-19, " Care and Maintenance of Permanent Plant
Items," dated October 10, 1979
Mercury Company Procedures, " Material Receiving Inspection Procedure,"
QCP-3110.1, Revision 1, dated October 19, 1978; " Project Control
Procedure," PCP-2040, dated October 23, 1978; and Construction
Procedure SP.651, " Construction Procedure for Installation of Local
Mounted Instrument Racks and Cabinets," Revision 2, dated September 7,
1978
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Fischbach & Moore, Inc. Procedure QNP-303W3, " Material and Equipment
Handling, Storage and Maintenance," Revision 1, dated March 14, 1978
Tompkins-Beckwith, Inc. Procedure TBP-46, " Care and Maintenance of
Permanent Plant Items," Revision A, dated May 14, 1979
No items of noncompliance or deviations were identified.
4.
Safety-Related Components - Procedural Implementation Protection After
Installation
In conjunction with a procedure review, the IE inspector conducted an overall
plant walk-thru and records review to ascertain procedural implementation for
the protection and maintenance of safety-related components after installation.
Observations were made on all levels of both the Reactor Containment Building
and Reactor Auxiliary Building, including reactor vessel internals being
installed (core support barrel) and vessel internals stored in containment.
Records reviewed included the following:
"Inplace Monitoring Log," form ASP-IV-19-5, for the period May 31, 1979,
through January 30, 1980
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Care and Maintenance Surveillance Reports, File Folder, " Reactor Vessel
Internals," September 10, 1979, through December 28, 1979, including
cleaning water analyses reports
Folders containing Care and Maintenance Audit Reports with contractor
response for the period September through December 1979
No items of noncompliance or deviations were identified.
5.
Site Tour
The IE inspectors walked through various construction and storage areas to
observe construction activities in progress and to inspect the general state
of cleanliness and adherence to housekeeping requirements.
No items of noncompliance or deviations were identified.
6.
IE Bulletin 79-02, Revision 2
The IE inspector observed activit'e. and reviewed records for those base
plates addressed by IE Bulletin 79-02, Revision 2, " Pipe Support Base
Plate Designs Using Concrete Expansion Anchor Bolts." Ebasco Specification
No. LOU 1564.468, " Drilled-in Expansion Type Anchors in Concrete for Category
I Structures," established the installation, inspection, and testing require-
ments for the use of concrete expansion anchors at the site.
Procedure TBP-33, " Procedure for Inspecting Drilled-in Expansion Type Anchors
in Seismic Class 1 Concrete," established the torquing verification check of
all seismic Class 1 concrete expansion anchor bolts.
In addition, one out of
every one-hundred concrete expansion anchor bolts tested should also be tension
tested.
Should a failure occur, three additional anchor bolts would be tested,
and if any one of these bolts failed to meet the required tensile loads, then
the entire group of the one-hundred anchor bolts would be tested.
Procedural requirements are as follows:
Minimum
Bolt Size
Embedment
Torque (ft-lbs)
Tension (lbs)
3/8"
3"
30-40
1455
1/2"
5"90-100
3795
5/8"
6"
150-170
5060
3/4"
7"
185-210
6758
1"
7"
325-375
8602
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A field inspection of several installed base plates and a general review of
records for hangers SIRR-981, FSRR-265, and EARR-7 indicated the requirements
of IE Bulletin 79-02, Revision 2 were being met.
Additional review will be
required during a subsequent inspection concerning the design modifications
and the resulting addition of stiffener plates to include the effects of the
base plate flexibility.
No items of noncompliance or deviations were identified.
7.
Reactor Coolant Loop Piping
The IE inspector observed welding being accomplished on the four pipe welds
that connect the No. 1 steam generator to Reactor Coolant pumps No. lA and
IB.
The four welds, identified as P3Wl, P4Wl, P7W1 and P8W1 on NISCO Drawing
3015-003, were being welded with the shielded metal-are process.
The welders
were using electrode type E7018 for welding P3W1 and P7W1 and electrode type
E308-16 for welding P4W1 and P8W1 as specified in weld procedure specification
(WPS) 10.1.14, Revision E and WPS 80.3.2, Revision A, respectively.
In addition to observing welding activities, the IE inspector observed post-
weld heat treatment of weld P16W2, a, carbon steel weldment in the intermediate
pipe leg between steam generator No. 2 and Reactor Coolant pump No. 2B, for
compliance with NISCO Procedure E3016-1, Revision B and Section III NB of the
Observations by the IE inspector included spacing of the
thermocouples, placement of the heating pads, and monitoring of the controller-
recorder temperatures.
The in-process testing of two welders was observed by the IE inspector.
The
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welders were using electrode type E7018 and welding with the pipe in a 45
position as required for qualification to NISCO WPS 10.1.14 in accordance
with WQT-187, Revision C.
Bend test specimens were removed from the test
welds and evaluated by the test examiner for compliance with Section IX of
the ASME B&PV Code and the acceptable results were confirmed by the IE
inspector.
No items of noncompliance or deviations were identified.
8.
Exit Interview
The IE inspectors met with licensee representatives (denoted in paragraph
1) at the conclusion of the inspection on February 1, 1980.
The IE
inspectors summarized the purpose and the scope of the inspection and the
findings.
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