IR 05000482/1981013
| ML20010G041 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/17/1981 |
| From: | Crossman W, Vandel T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010G038 | List: |
| References | |
| 50-482-81-13, NUDOCS 8109150266 | |
| Download: ML20010G041 (6) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-482/81-13 Docket No. 50-482 Category A2
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Licensee:
Kansas Gas and Electric Company Post Office Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Generating Station Inspection at: Wolf Creek Site Inspection conducted:
July 1981 Inspector:M/..MM A< b 7F//NR/
%1T.E.Vandel,ResidentReactorInspector Date
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Projects Section
Approved: N/,86 d/m,d h/MD 1 W. A. Crossman, Chief, Projects Section 3 Date Inspection Summary:
Inspection During July 1981 (Report STN 50-482/81-13)
Areas Inspected:
Routine, announced inspection by the Resident Reactor Inspector (RRI) including follow-up to previous inspection findings; plant tour observations of QC inspection activity; control room panel vendor wiring checkout and wiring terminations activity; concrete placement in the Reactor Building; steam generator physical protection; fuel storage racks instal-lation; safety-related piping Dimetrics welding; primary coolant piping activities and RHR encapsulation installation.
The inspection activities involved 45 inspector-hours by the RRI.
Results: No violations or deviations were identified.
8109150266 810820 PDR ADOCK 05000482 O
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DETAILS 1.
Persons Contacted Princioal Lit.ensee Employees
- E. W. Creel, QA Manager
- G. L. Fouts. Construction Manager
- D. W. Prigel, QA Manager, Wolf Creek Station
- G. W. Reeves, Assistant QA Manager, Wolf Creek Station
- C. A. Snyder, Project Construction Supervisor Contractor Personnel
- L. D. Bryant, Project Quality Manager Daniel International Corporation (Daniel)
- V. J. Turner, Project QA Engineer, Daniel
- L. F. Warrick, Project Manager, Daniel
- Denotes those in attendance during the RRI's exit meeting held July 23, 1981.
- Denotes those in attendance during the RIV Investigator's exit debriefing held on July 30, 1981.
Other licensee and contractor employees were contacted during the inspection period including both craft and QA/QC employees.
2.
Plant Tours One or more areas were toured several times by the RRI during the.
reporting period to observe general construction practices, area clean-liness and storage conditions of the plani, equipment.
Examples of specific observations were as follows:
a.
The RRI observed that Control Room control panel RL017 to RL018 vendor installed wiring was being checked for continuity and correct termina-tions by two KG&E representatives by means of a Multi-Amp Corporation Ohm-meter. The meter (MW 4133) had been calibrated on May 13, 1980 and was due for recheck on November 13, 1981.
b.
Electricians of termination crew E54 were observed performing
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terminations in Control Room control panel RL014.
Low voltage control cables were being stripped of their jacket insulation and prepared for their terminal lug.
l c.
The RRI observed installation activities related to new fuel storage racks being performed by Westinghouse Electric Corporation
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personnel.
Installation and material quality items observed included:
(1) welding of racks by the fabricator, (2) plumbness
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checks of installed racks, and (3) welding of Iacks into place (SMAW technique).
d.
Concrete placement activities inside the Reactor Building related to pour number 271501 for the top section of the pressurizer shield wall placement were observed including:
(1) QC testing
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of concrete, (2) proper handling of fresh concrete, and (3)
placing activities.
e.
Steam generator EBB 01A was observed by the RRI.
The hatch was removed from the primary coolant discharge to the crossover loop piping (Loop 1) to provide access for personnel installing interior lining protection for the steam generator.
The RRI observed a security guard stationed at the opening to prevent unauthorized
personnel from entering the steam generator.
Construction personnel with protective clothing were placing and/or repairing protective lining material inside the steam generatur.
This lining material is to protect the steam generator when welding craftsmen enter it to install pipe welding purge dams and argon purge piping to facilitate the primary coolant piping welding activities.
f.
The RRI observed an example of QC inspection control in the Control Building lower spreading room where some coiled and hung red channel cables with minimum bending radius violations had been identified.
The coiled cables had been tagged with QC Hold Tags dated July 15, 1981 (approximately 4 days prior to the NRC Inspector's observation).
g.
On July 16, 1981, the RRI observed a just completed weld on a 4" stainless steel piping run (weld F-005 on EM-04 piping system)
that rad been performed by the Dimetrics automatic welding machine.
Tne completed weld appeared very good without any evidence of weld area shrinkage in diameter as compared to adjacent piping diameter.
In discussion with the welder (D-483), the RRI learnec.
Na+ the welder was more satisfied with the welding conditions prevailing ;ince changes had been made.
He believed that:
(1) welder qualifications had been improved, (2) some welding machine setting changes resulted in improvemerts, (3) supervision is more closely involved, which has helped especially in the area of fitups, and (4) the welder has control over the way piping is placed/ prepared for him.
No violations or deviations were identified.
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3.
Primary Coolant Loop Piping Reactor Coolant Loop #1 piping preparations for welding, welding activities, and Weld Control Records (WCR) were inspected by the RRI.
Field welds number F-106, F-107, and F-108 in I Loop-1 (Q)
were observed.
The results of the inspection were as follows:
a.
Welding in progress was observed on all three field welds with two welders, one or, each side of the pipe, at each weld monitor-ing the automatic weiding in progress.
The RRI observed the weld puddle and noted that the weld machine was set so that the weld puddle was slanted on one side of the weld (viewed in cross section) on one pass and the next pass was slanted to the other side of the weld.
It was understood that this technique had been devised to lessen the possibility of lack of penetration into the parent metal along the weld preparation.
b.
Two different welding machines were checked for weld parameters i
during operation.
The readings of these two machines were then checked against the weld procedure technique sheet.
The results of this check were as follows:
Machine Machine Technique NM-8-8-B-1
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- 2 Rev. 5 Parameters Amperage 210-240 250 90-299 Voltage
10 6-12 Travel, in.
3-4 3-4 2.6-6.0 per min.
Wire Speed, 45-50 45-50 20-99 in. per min.
c.
Welders performing the automatic welding activity were checked for proper qualifications as follows:
Welder Number
- Procedure Qualified D-282 NM-8-8-B-2 0-464 NM-8-8-8-2 D-483 NM-8-8-B-2 0-280 NM-8-8-B-2
- Procedure qualification to NM-8-8-B-2 Also qualifies the welder to NM-8-8-B-1 Another welder, D-390, qualified to procedure N-8-8-BA-2, did the attachment welding for fitup only.
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d.
QC records control for the WCR for weld F-108 in I-Loop-1 (Q) was reviewed.
Weld techniques listed included:
N-8-8-BA-1 NM-6-8-B-1 N-8-8-BA-2 N-8-8-B-8 The first listed inspection point on the record called for a liquid penetrant (LP) inspection of the weld preparations prior to welding the joint.
It was flagged ar an Authorized Nuclear Inspector (ANI) hold point.
In the re. narks column it was noted that PT report PBT-PT-2629, indicated " acceptable for field weld F-108."
However, no sign-off by the ANI was noted.
In response to questioning, it was learned that the original PT inspection was observed by the ANI.
This inspection report PBT-PT-2598 dited July 6, 1981, indicated that the weld preparation was rejected because of rejectable porosity indications.
A later inspection conducted of the specific areas previously rejected resulted in acceptable report PBT-PT-2629 dated July 9,1981.
However, the ANI was not notified of this inspection and therefore did not witness this inspection as required by the ANI hold.
Other welding and inspection work proceeded even though the ANI had not signed off for this hold point acceptance.
The RRI considers this matter unresolved (482/81-13-01).
Follow up inspection by the NRC will be performed at a later date.
No violations or deviations were identified.
4.
RHR Encapsulation The RRI observed work activity related to the RHR Encapsulation System at the 1988' elevation of the Auxiliary Building.
The RRI reviewed a WCR with a supplement sheet for buttering of the weld preparation for weld joint EJ-XJ-015 to TEJ01B (field weld FW-508). Two pipefitter welders were in the process of grinding the completed buttering of the weld preparation prior to fit up.
In response to questioning, the RRI was informed that the WCR was issued only for the weld preparation buttering, and that the welding of the encapsulation sleeves was still subject to a QC hold.
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No violations or deviations were identified.
5.
Unresolved Matters Tinresolved items are matters about which more information is required
'n order to ascertain whether they are acceptable items, violations, or deviations.
An unresolved item disclosed during this inspection is discussed in paragraph 3.
6.
Exit Meetings The RRI met with licensee representatives identified in paragraph 1 on July 23, 1981, to discuss the inspection results and findings.
The RRI attended an exit debriefing conducted by Mr. D. D. Driskill, Investigation Specialist, on July 30, 1981.
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