IR 05000382/1982029
| ML20028G177 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/11/1983 |
| From: | Bess J, Crossman W, Hunnicutt D, Clay Johnson, Mullikin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028G171 | List: |
| References | |
| 50-382-82-29, NUDOCS 8302070486 | |
| Download: ML20028G177 (10) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-382/82-29 Docket: 50-382 License: CPPR-103 Licensee:
Louisiana Power and Lig'ht Company (LP&L)
142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 t
Inspection At:
Taft, Louisiana Inspection Conducted:
December 13-16, 1982 Inspectors h)??
ubc N
///0/82 o*C. E. Johnson, Reactor Inspector ITate /
Engineering Section (pars. 1-4, 10, & 11)
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/ho/as D. M. Hunnicutt, Chief gate /
Engineering Section (pars.1, 3, 9, & 11)
R. P mA i /,o /ss R. P. Mullikin, Reactor Inspector Date Engineering Section (pars. 1, 3, 7, 8, & 11)
4 k L~s iholes
' p J. Bess, Reactor Inspector Date Engineering Section (pars. 1, 3, 5, 6, & 11)
l Approved:
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///c/83 D. M. Hurinicutt, Chief Ddte /
Engineering Section Mf4A/L 4As
"W. A. Crossman, Chief /
Date
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Reactor Project Section B 8302070486 830113 PDR ADOCK 05000382 O
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Inspection Summary Inspection Conducted December 13-16, 1982 (Report 50-382/82-29)
Areas Inspected:
Routine, unannounced inspection of construction activities including site tour; observation of work and review of procedures and records for safety-related structural steel and supports; review of site audit reports pertaining to cable installation and associated equipment; review of noncon-formance/ deviation reports pertinent to electrical cable pulling, terminations, and QC personnel witness of completed work; examination of inplace storage of motor control centers (MCC); selected 39 welds for independent measurement examinations by NRC and their contractor to evaluate the adequacy of the shop and field welds at the Waterford facility.
The inspection involved 104 inspector-hours by four NRC inspectors.
Results: Within the areas inspected, no violations or deviations were identified.
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Details 1.
Persons Contacted
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Principal Licensee Employees
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- L. Bass, Project QA Engineer
- R. Bennett, QA Engineer
- B. Toups, QA Engineering Technician
- R. Sandridge, QA Engineering Technician
O. E. Baker, Onsite Licensing Engineer
- T. F. Gerrets, QA Manager
- G. F. Koehler, QA Engineer
- R. I. James, QA Engineer
- C. J. Decareaux, NPSG Construction Engineer
- W. G. Cross, NPSG Licensing - Onsite L. Eaves, Start-up Engineer W. Denny, Start-up Engineer Ebasco Services Inc. (Ebasco)
- J. Davis, QA Records Installation Group
- D. McCorkle, QA Records Installation Group
- M. A. Burgan, Manager Documentation Turnover L. Conley, QA Records Installatin Group B. J. Aggarwal, Construction Engineer (Civil)
- J. Gutierrez, QA Site Supervisor Other Personnel M. Folson, Field QC/QA Manager, Nuclear Installation Services Co. (NISCO)
C. Reid, Lead Engineer, NISCO The NRC inspectors also interviewed other contractor personnel.
- Denotes those attending exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Violation 50-382/82-18:
Failure to accomplish construction activities in accordance with construction drawings and procedures.
An unspecified weld had been used to attach a plate to a diagonal horizontal angle brace at elevation 53 ft. location 9 ft. - 9 in, north and 6 ft. - 9 in, west at column L-10 AZ instead of attaching the plate with bolting as specified by Ebasco Drawing G-8420.
The licensee submitted a reply; however, NRC
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requested more information on this matter.
The licensee is presently collecting the required information to forward to NRC.
This item remains open.
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3.
Site Tour i
The NRC inspectors toured the fuel building, reactor building, and the reactor auxiliary building to observe construction in progress and to inspect housekeeping.
No violations or deviations were identified.
4.
Safety-Related Structural Steel a.
Review of Procedures The NRC inspector reviewed several procedures to assure that adequate controls have been established relative to safety related structural steel and supports.
Adequate procedures are included and appear to conform to applicable codes, standards, and construction specifications.
Procedures reviewed are listed below:
WQC-100, Rev. 3, " Structural Steel Bolt-Up Inspectica" CP-697, Rev. F, " Bolt-Up of Structural Steel" WQC-101, Rev. 2, " Inspection of Structural Steel Welding" No violations or deviations were identified.
b.
Observation of Work 1.
Structural Steel s
The NRC inspector observed structural steel members for ine missle protection over the main steam isolation valves (MSIV) in both the east and west rooms.
All members appear to be in place and joints bolted snug tight.
Steel grating had not been completely installed.
No obvious discrepancies were observed by the NRC inspector.
2.
Steel Supports The NRC inspector observed the completed installation of the reactor coolant pump volute supports #2B in the reactor building.
The completed structure consisted of base plates, diagonal bracing and the supports themselves.
There were also no apparent discrepancies observed on the 2B supports by the NRC inspector.
No violations or deviations were identified.
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c.
Review of Records 1.
Structural Steel The NRC inspector reviewed installation records of the structural members for the missle protection over the east and west main steam isolation valves.
American Bridge (AB) erected and documented most of the steel and Ebasco erected the remaining steel.
During the review of AB records, it was found that not all documentation was present for the structural members of the missile protection.
AB is no longer onsite and has turned over all documentation to the Ebasco records installation group (ERIG).
ERIG has identified some of the problems related to missing documentation by AB in this area and others.
Ebasco representative with ERIG informed the NRC inspector that final acceptance by ERIG has not been performed until all records have been married and completely assembled.
Until additional informa-tion is presented for a more thorough inspection, this will be considered an unresolved item.
Requirements to close this unresolved item will be as listed below:
Perform a complete review of AB documentation by ERIG to
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determine what documentation is missing for the structural steel over the east and west MSIV missile protection.
Perform corrective action for missing documentation.
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Reinspection by QC for missing documentation.
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Determine if other areas of safety-related structural steel
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erected by AB has documentation problems.
2.
Steel Supports The NRC inspector reviewed the records of the reactor coolant pump volute support #2B.
All required documentation was present.
Field changes were approved and initiated as required.
Any modifications on the supports were documented and approved.
No discrepancies were observed by the NRC inspector.
Erection and documentation was performed by NISCO.
Reference drawings are listed below.
Drawing No.
2610 Q-E-1, Industrial Engineering Works LOU-1564 G-842C, Ebasco LOU-1564 G-8428, Ebasco i
No violations or deviations were identified.
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5.
Review of Licensee's QA Audit Reports The NRC inspectors reviewed licensee QA audits of electric cable installa-tion and associated equipment.
The reports were examined to determine whether the required audits were performed and whether deficiencies identified were corrected (or being corrected in a timely manner), and docur.ented. Also, the reports were examined to ascertain whether the corrective action was such that repetition of the deficiency and similar deficiencies, would be precluded.
The audit documents examined are as follows:
Fischbach & Moore, Inc., Audit-W35 82-21, " Installation and Termina-
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tion of Cables in the Containment Spray System," dated March 16, 1982 Fiscabach & Moore, Inc., Audit-W3S 82-16, " Documentation and Activities
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Involving Special Techniques and Tools Used in Terminations in Reactor Control Boards," dated February 16, 1982 Fischbach & Moore, Inc., Audit-W35 82-10 " Control of Measuring and
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Test Equipment," dated January 29, 1982 Fischbach & Moore, Inc., Audit-W35 81-425, " Cable Identification,"
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dated November 16, 1981 FiscP. bach & Moore, Inc., Audit-W3S81-435, " Cable Separation and
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Routing," dated November 16, 1981 Fischbach & Moore, Inc., and Ebasco, Audit-W3S82-175, " Qualified
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Material for Cable Splicing," dated February 25, 1982 No violations or deviations were identified.
6.
Nonconformance/ Deviation Reports The NRC inspectors reviewed nonconformance and deviation reports pertinent to the identification, pulling and termination of electrical cables.
The nonconformances and deviations had been properly resolved and documented.
The reviewed records were legible, complete, reviewed, approved, and properly stored.
The nonconformance/ deviation documents examined for selected power and control cables are as follows:
Ebasco Nonconformance Report - W3-3197, Cable 30586SA, location
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RAB-35, Drawing B288, Sheet 298, Iss. 41, " Cable Pulled into the Wrong Conduit" Ebasco Nonconformance Report W3-3184, Cables 312610-SB and 31119E-SB,
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Drawing 307-82-215, " Cables Were Approximately 6 ft. too Short for Termination"
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Ebasco Nonconformance Report W3-3185, Cable 31526D-58, Inspection Report 308-83-185, " Cable Terminated to the Wrong Terminal Points" Ebasco Nonconformance Report W3-3109, Cable 31041A-SA, " Cable Pulled
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'Without QC Witness" The following nonconformance/ deviation reports on power and control' cables were also reviewed.
Ebasco NCR No.
Area W3-3433 Cable Damaged W3-3417 Insulation Damage W3-3406 Cable Pulling W3-3399 Cable Damage W3-3380 Cable Pulling W3-3374 Cable Damage W3-3368 Cable Tennination W3-3345 Cable Damage W3-3344 Cable Damage W3-3339 Insulation Damage W3-3337 Cable Termination W3-3313 Insulation Damage W3-3310 Insulation Damage W3-3305 Cable Bend Radius W3-3291 Insulation Damage W3-3290 Insulation Damage
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W3-3273 Cable Separation W3-3273 Cable Pulling W3-3239 Termination W3-3229 Insulation Damage W3-3228 Termination The nonconfornance/ deviation documents examined for selected instrumenta-tion cables are as follows:
Ebasco NCR No.
Area W3-3463 Termination W3-3367 Termination W3-3341 Cable Damage W3-3308 Cable Separation W3-3271 Termination W3-3235 Insulation Damage W3-3224 Termination W3-4772 Conduit Supports W3-4312 Termination W3-4313'
Termination W3-4217 Termination
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Ebasco
NCR No.
Area W3-10647 Termination W3-3171.
Termination The licensee's established procedures were followed for identified noncon-formance and deviation reports.
No violations or deviations were identified.
7.
Inspection of 480 Volt Motor Control Centers The NRC inspectors examined the in place storage of the two 480 volt motor control centers (MCC) which regulate the wet and dry cooling tower fans.
These two MCC (3A315 and 3B315) are unique at the Waterford 3 site in that the electrical cables are routed through conduits in the floor in a compartment at the back of the MCC.
This compartment is very narrow which can allow for damage to the cables by persons walking in this area.
It was observed that at some previous time during construction these cables had been stepped upon.
However, the NRC inspectors found no damage to the cable's insulation.
There are approximately 50 cables in each MCC.
The NRC inspectors observed that several conduits in each MCC were filled with water.
LP&L personnel stated that this was probably due to the conduit seals not being installed.
A verbal commitment was made to the NRC inspectors to remove the water and take the necessary corrective action.
An LP&L QA engineer found that several cables were being stressed at the point of entry to the back fo the MCC due to improper supports.
An LP&L QA Site Surveillance Report W35-82-885 was written on December 15, 1982, which requires these cables to be properly supported.
No further action is required on this item other than a verification of work completed during a subsequent inspection by an NRC inspector.
8.
Inspection of Emergency Diesel Generators The NRC inspectors inspected the diesel generators, the diesel generator control panels (both in the main control room and the diesel room), the diesel oil day tank, and a main diesel oil storage tank.
The NRC inspectors examined areas such as:
diesel load sequencing scheme; start-up and stop procedures; control panel switch continuity; and diesel room control panel location.
No violations or deviations were identified.
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9.
Independent Measurements - Selection of Welds The NRC inspector selected a total of 39 welds for an independent verifica-tion inspection to be conducted by Region I and an NRC contractor's (Wisconsin Industrial Testing) personnel during the period from January 17 through January 28, 1983.
NRC's Region I Mobile NDE Labo;atory will be utilized by the independent measurements personnel to perform the independent verification inspection.
The purpose of the weld selection was to provide NRC selected welds for the independent inspection by NRC to evaluate the adequacy of the licensee's quality control program through NRC independent testing.
The weld selec-tions were accomplished by the NRC inspector personally selecting each weld.
The selections were based on a tour of the reactor building, containment building, and auxiliary building and through system drawings, isometric drawings and appropriate sketches of piping systems.
The plant status was considered during the weld selections to increase the probability of the welds selected being available for the NRC independent measurements during the period of January 17 through January 28, 1983.
The NRC selected welds were intended to provide representative samples of piping systems, components, pipe sizes, and pipe thicknesses, materials, shop and field welds and ASME B&PB Code Class 1 and 2 welds.
The welds selected for NRC inspection were previously accepted by the licensee, based on vendor shop or onsite NDE licensee records.
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The following welds were selected for independent inspection:
System Number of Welds Main Steam
Low Pressure Safety Injection
High Pressure Safety Injection
Safety Injection Tank 2-A
Safety Injection Tank 1-B
Charging System (C&VCS)
Total 39 10.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations.
An unresolved item related to inspection of structural steel documentation is discussed in paragraph 4c.
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11.
Exit Interview
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The NRC inspectors met with L. Bass and other licensee and contractor
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Mr. L. Constable, NRC Senior Resident Reactor Inspector, i
attended the exit interview.
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