IR 05000482/1981016
| ML20039G791 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/10/1981 |
| From: | Crossman W, Stewart R, Vandel T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039G788 | List: |
| References | |
| 50-482-81-16, NUDOCS 8201190143 | |
| Download: ML20039G791 (7) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report No. STN 50-482/81-16 Docket No. STN 50-482/81-16 Licensee: Kansas Gas and Electric Company Post Office Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Generating Station Inspection at: September and October 1981 Inspector:
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E~. Vandel,f esident Reactor Inspector 06te'
Projects Sect. ion 3
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R. C. Stewart, Reactor Inspector Date-
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Approved:
C W. A. Crossman, Chief, Projects Section 3 Date'
Inspection Summary:
Inspection During September and October 1981 (Report STN 50-482/81-16)
Areas Inspected: Routine, announced inspection by NRC Inspectors covering follow up to previous inspection findings; observations of work activities related to class 1E electrical equipment; wireways and hangers; safety-related components; primary coolant and other safety-related piping; containment prestressing system; review of the containment prestressing system QA program and procedures; revised procedures for inspection of hanger supports; and general plant tours.
The inspection activity involved 72 inspector-hours by two NRC inspectors.
Results: Of the ten areas inspected, one violation item was identified regarding failure to provide adequate protection for class 1E electrical equipment.
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DETAILS 1.
Persons Contacted Principal Licensee Employees l
E. W. Creel, QA Manager, Corporate, Kansas Gas and Electric Company (KG&E)
- N. W. Hottel, QC Supervisor, Startup, KG&E
- 0. W. Prigel, QA Manager, Wolf Creek Station, KG&E
- G. W. Reeves, Assistant QA Manager, Wolf Creek Station, KG&E
- J. L. Stokes, Project Support Supervisor, KG&E
- R. A. Youngs, QA Supervisor, Operations, KG&E P. Burck, QA Engineer, KG&E H. Moody, QA Technologist, KG&E C. Parry, QA Technical Auditor, KG&E 0. Sayre, QA Technical Auditor, KG&E j
Contractor Personnel D. J. Dennison, Project Quality Inspection Manager, Daniel
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E. Cannon, Jr., ANI Hartford Steam Boiler Company
- Denotes attendees at one or more exit meetings held on September 10, 1981, and October 8, 1981.
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Other licensee and contractor personnel were contacted during the course of inspection activity.
2.
Licensee Activity on 50.55(e), and Previous Inspection Findings a.
Auxiliary Panels and Main Control Boards Welding (SNUPPS Construction Deficiency, see reports 50-482/81-05 paragraph 3.a, 81-06 unresolved item 81-06-01, and 81-09 paragraph 3).
Bechte! letter BLSE: 9645 dated July 14, 1981, addressed the resolution of the Main Control Panels / Auxiliary Relay Racks Weld
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deficiencies detailed in the Comsip, Inc., report dated June 8, 1981, and. approved the report resolving the deficiency report 2-SD-4604-EW for Wolf Creek.
'The report concludes that as-built welds can withstand at least twice the stress levels calculated to occur during a safe shutdown earthquake.
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This matter is considered to be closed.
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(Closed) Unresolved matter (50-482/81-01-01): Concern regarding adequacy of piping welding activities.
The NRC Inspector has conducted a number of inspections covering various aspects of pipe welding and inspection with the results being incorporated into several reports. The Daniel International Corporation (Daniel) Task Force Report Wolf Creek Welding Activities issued to the licensee on April 7, 1981, was also reviewed.
The results of inspections are summarized as follows:
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NRC Inspection Report 50-482/81-08 covered the review of
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safety-related pipe welding radiographic inspections (paragraph 2).
NRC Inspection Report 50-482/81-13 covered observations of a
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safety-related stainless steel piping weld by Dimetrics welding (paragraph 2.g), primary coola.nt loop pipe welding observations (paragraph 3), and RHR encapsulation sleeve weld work (paragraph 4).
NRC Inspection Report 50-432/81-14 covered calibration testing
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of a Dimetrics machine and encapsulation sleeve welding
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observations (paragraph 4).
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The NRC Inspector concluded that the welciing concern had been adequately resolved and that this matter is closed.
3.
Reactor Containment - Post-Tensioniog System a.
System Status The Reactor Containment Building shell has been completed and tendon installation is scheduled to start mid-November by INRYCO, Inc., utilizing the same installation crews currer;;1y completing the post-tensioning at the Callaway Nuclear Facility.
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Post-Tensioning System - QA/QC Program Review
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During the period October 19-22, 1981, the NRC Inspector
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conducted a detailed comparative review of the Wolf Creek FSAR, NRC Regulatory Guides, Bechtel (A/E) Specifications, KG&E (SNUPPS) Standard Quality Assurance Manual to the INRYCO, Inc.,
QA Manual /QC Procedures relative to the installation and inspection of the Reactor Containment Post-Tensioning System.
The review included the following documents:
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SNUPPS FSAR, Section 3.8, Revision #6
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SNUPPS Standard Quality Assurance Manual, Revision 5,
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dated May 20, 1980
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KG&E Contract No. 10466-C-155Q-1, datad December 30, 194
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Bechtel Corporation Specifications 10466-C-155Q, Revision 3,
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dated January 28, 1976, and 10466-C-156Q, Revision 3, dated i
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February 10, 1976 (
INRYC0 QA Program, " Post-Tensioning Division 90 and 170 Wire
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BBRW System," dated August 14, 1973 l
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INRYC0 " Field Installation Manual," Revision 1, dated i
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December 15, 1980, (Chapters 4 thru 9)
i Letter:
INRYCO, Inc. to KG&E, " Proposed Manual Revisions,"
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dated August 25, 1981
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NRC Regulatory Guide 1.35, " Inservice Inspection of Ungrouted
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Tendons in Prestressed Concrete Containment Structures,"
Re W on 2, January 1970 NRC Regulatory Guide 1.103, " Post-Tensioned Prestressed Systems l
for Concrete Reactor Vessels and Containments," Revision 1, dated October 1976
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Ouring the review, the NRC Inspector observed that proposed changes
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to the INRYC0 QA/QC Manuals were not complete and issued at the time l
of this inspection; therefore, this matti-r will be reviewed during a j
subsequent follow-on NRC inspection.
t No violations or deviations were ideatified.
4.
Electrical Components, Raceways, and Hangers The NRC Inspector performed observations of installation activities f
related to etass 1E 4160 Volt switchgear, raceway and hangers
installation, and installed conditions as well as review of installation
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drawings in use. The results of the inspections are as follows-L i
a.
4160 Volt Switchgear
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Medium Voltage System Class 1E 4.16 kV switchgear located at elevation 2000' of the Control Building was inspected.
Inspection
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covered preservation and protection of equipment during construction activities. On several occasions, the NRC Inspector observed wiring continuity checking in progress in the main breaker cubicles. While in progress, the breaker had t,een removed from the cubicle and left standing in the workway adjacent to the switchgear. On August 12,
1981, breaker NB0112 was observed in the workway while continuity cnecking was in prmgress. No other work was in progress in the area
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at the time. On September 9,1981, breaker NB0212 was otnerved out of its cubicle and standing in the workway approximately one-half under and one-half out from under a work scaffold.
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Construction workers were observed climbing up onto the scaffold l
platform and down while construction activities were being performed overhead above the breaker. Again on September 10, 1981, breaker
NB0212 was observed placed in the workway.
In discussions with
licensee personnel the NRC Inspector expressed concern regarding
i adequacy of protection for the breakers and the lack of an adequate l
procedure for proper protection. This item is considered to te in j
violation of 10 CFR Part 50, Appendix B, and a Notice of Violation
was issued to the licensee on September 18, 1981.
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The NRC Inspector observed on September 14, 1981, that boxes had been j!
prepared and plated available to store not only removed 4160 volt breakers, but also 480 volt breakers when removed. The Inspector I
considered the boxes to be adequate to provide protection for breakers from construction activity (50-482/81-16-01).
b.
Electrical Raceway and Supports
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The NRC Inspector performed a review of ccmplete i safety-related raceway systems installation. Selected tray installations inspected were as follows:
i Osble spreading room tray installations 1C8G27, IC8J27, and
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j IJ1J27, along with hangers ZG-104 and XW-78 Control Building elevation 2016' trays 3VIA01 and 3J1A01 and
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hangers 8228, B229, A525, and A527 Containment tray installations 4V2A26 and 4J2A26 over hanger
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DAV-24, and conduits 4G2000 and 4G2001 supported hanger DAL-36 and from containment liner hanger brackets.
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The following observations were made:
Material utilized had been accepted
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Configuration was per drawings
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I Attachments were as detailed
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Welded condition appeared acceptable
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Welder 0481 was determined to be qualified
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Location and anchorages appeared acceptable
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Identification was correct
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The trays had no sharp edges or burrs j
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I Grounding cable had been installed
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One example was observed of nonsafety-related conduits (511X38)
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and 511X3C) supported by II/I hangers crossing over safety-related cable trays Electrical drawings (4) observed being used for construction
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installation in the cable spreading room were checked for the latest
revision.
The latest revision of the drawings were being used
in each of four cases as follows:
E-0R 3903 (Q) Rev. 5
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E-0R 3904 (Q) Rev. 4
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E-OR 3905 (Q) Rev. 7
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E-0R 3906 (Q) Rev. 7
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The Inspector observed two examples of conduit hangers an'd tray supports under control of QC Hold Tags as follows:
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Conduit support brackets for conduits 4G2000 and 4G2001
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attached to the containment liner I
Cable tray hanger JX-A143 on hold because a 4" pipe, compressed
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air line KA-04 (nonsafety-related), was being supported by the I
hanger that also supported safety-related cable tray 4J1C56 Two electrical cable feeders from 480 Volt Power Center NG02, one feeder 500 MCM cable and the other feeder 350 MCM cables were checked
for minimum bending radius where they entered the cable tray (for 480
volt cables).
It was found that the cables were within the minimum i
bending radius as specified in Bechtel drawing No. E 01013 (Q), Rev.
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No violations or deviations were identified.
5.
Plant Tours
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One or more plant areas were toured several times during the reporting l
period to observe general construction practicus, area cleanliness and
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storage conditions of plant equipment. Examples of specific observations
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are as follows:
a.
The NRC Inspector observed setting an.d alignment of the Fuel Pool Cooling Pump, Equipment No. PEC01B (Q) utilizing S n cific IrStruction Sheets number Z-1 through Z-4 (Instruction items 13-17
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being completed). The pump will not be connected to the motor No. DPEC01B Class 1E because of a QC Hold Tag No. 21753, dated September 30, 1980, pending approval of IEEE-323.
b.
The NRC Inspector obsertad a Cobalt 60 radiography unit in storage near primary coolant piping Loop 1.
The unit was properly closed up, the area was roped off with magenta rope and radiation warning signs were hung from the rope.
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c.
The NRC Inspector observed that a tap nipple on the crossover leg of primary coolant Loop 1 piping was open and the nozzle was being used for a welding machine ground. When pointed out to KG&E QA personnel, the ground was removed, the pipe cleaned, and the nozzle was re-capped. A special instruction was issued pertaining to care of ground selections.
d.
A new Daniel procedure, QCP VII-204, dated September 15, 1981, entitled Inspection of Supports was reviewed by the NRC Inspector.
No concerns were identified by the Inspector.
No violations or deviations were identified.
6.
Exit Meetings The RRI met with licensee representatives identified in paragraph 1 to discuss the various inspection findings.
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The RRI also attended the Special QA Inspection exit meeting held on i
October 2, 1981, and the Management Meeting held in the Region IV Office on September 2, 1981.
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