IR 05000482/1981004
| ML19347E986 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/01/1981 |
| From: | Barnes I, Ellershaw L, Randy Hall, Tomlinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19347E984 | List: |
| References | |
| 50-482-81-04, 50-482-81-4, NUDOCS 8105150011 | |
| Download: ML19347E986 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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(j OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
(This Report Contains Investigation Results in Paragraph 4)
Report No. STN 50-482/81-04 Docket No. STN 50-482 Category A2 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name:
Wolf Creek, Unit No.1 Inspection at:
Burlington, Coffey County, Kansas Inspection Conducted: March 9-13, 1981 Inspectors M
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3 30-Sl O'. P. TomlTnson, Reactor Inspector, Engineering and Date Materials Section (paragraphs 1, 2, 4, 5, 6, 7 & 8)
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- wv2 b-\\~81 I.. E. Ellershaw, ContTacto InspectorNRoactive Inspection Date
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Section (paragraph 3)
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4 - 1-D Approved:
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I. Barnes, Chief, Reactivd Inspection Sect 90n, Vendor Date Inspection Branch
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R. E. Hall, Acting Chief, Engineering and Materials Section Date 8105150D// e.
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Inspection Suminary:
-Inspection on March 9-13,1981 (Report No. STN 50-482/81-04)
Areas Inspected:
Routine, announced inspection of construction activities and observation of work activities related to Reactor Coolant Loop piping and other safety-related piping; a documentation inspection related to procurement; and follow-up inspections related to a licensee reported problem and a previously unresolved item.
This inspection involved 44 inspector-hours by two NRC inspectors.
Results:
In the five areas inspected, no violations or deviations were identi-fied in four areas.
One violation was 1centified in the area of procurement documentation (violation - failure to follow procedures for receiving inspection -
paragraph 3).
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- D. W, Prigel, Assistant QA Manager
- d. L. Stokes, Project Support Supervisor
- R. M. Stambaugh, QA Engineer
- P. M. Burck, QA Engineer
- M. E. Clark, QA Manager, Site Other Personnel
- N. J. Criss, Audit / Procedures Coordinator, Daniel International Corporation (DIC)
- J. M. Ayres, QA Engineer, DIC
- L. D. Bryant, Project Quality Manager, DIC W. W. Wais, Assistant Engineering Manager, DIC P. S. Manley, Plant Design Liaison, Bechtel R. C. Slovic, Lead Site Liaison Engineer, Bechtel G. Robertson, Project Manager, Peabody Testing J. A. Thomas, Purchasing Coordinator, DIC
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E. Cheary, QC Engineer, DIC
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R. Albrecht, Purchasing Coordinator, Bechtel During this inspection, other site QC and construction personnel were contacted.
- Denotes those attending the exit interview.
2.
Site Tour The NRC 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.
The tour included the Reactor Buildir.3, Reactor Auxiliary Building and several outside storage areas.
No violations or deviations were identified.
3.
Procurement Document Control The NRC inspector reviewed DIC procurement documentation, such as, purchase orders and purchase specifications, pertaining to bolting materials.
In addition, a review of the associated Certified Material Test Reports (CMTR),
Material Receiving Reports (MRR), and a receiving inspection procedure was conducted.
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DIC Purchase Order No. 7158-SR-66024, dated August 16, 1978, was placed with a vendor for bolts to be used in bolting down containment spray pumps.
The purchase order specified the material to be ASME SA-449 and the bolts to be in accordance with ASME Section III, Article NF-2000, Class 2 component supports.
It further required that the vendor's documentation contain a CMTR which would be in compliance with ASME B&PV Code,Section III, NA-3767.4.
This requirement states, in part, "When specific times and temperatures (or temperature ranges) of heat treat-ments of materials are required by material specifications, they shall be reported. When specific times and temperatures (or temperature ranges)
are not required by the material specification, a statement of the type of heat-treated condition shall be reported."
The Material Specification, SA-449, paragraph 2 (b) states, "The bolts and studs shall be heat treated by quenching in a liquid medium from above the transformation tempegature and then tempering by reheating to a temperature of not less than 800 F."
Daniel International Procedure QCP-1-01, Revision 10. " Receipt, Storage and Preservations of Safety-Related Materials and Items," paragraph 4.1.4 states, in part, " Materials supplied by others not having source surveil-lance inspections... shall receive supplemental inspection and review as applicable in Appendix I,Section III of this procedure."
Appendix I, Revision 3, paragraph 3 states, in part, "Unless the co;npleted item was inspected or examined at the source, it shall be insoected or examined at the point of receiving to verify that the following character-istics conform to the specified requirements....
Assurance that physical properties conform to specification requirements and that chemical and physical test reports, if required, meet the requirements."
The vendor's CMTRs, accepted by DIC on MRRs 23141 and 42475, do not provide the required statement pertaining to the type of heat-treated condition the bolts are in.
Since these bolts did not receive source inspection, these data are required on the CMTR.
Failure to note this deficiency during receiving inspection is a violation.
IE Follow Up of Licensee Identified Item The Region IV Office was notified by KG&E that "six Peabody NDE personnel were suspected of using marijuana on the Wolf Creek site" and that all had been transferred to other locations or terminated.
The NRC inspector interviewed the Peabody Project Manager and ascertained that a total of five employees had been released, but that only one of them was suspected of on-site use of marijuana.
The other employees, although not susoected, were offered transfers to other jobs for reasons other than on-site drug use.
One in this group refused to accept the transfer and was terminated along with the suspected marijuana user.
Two in this group of five readily admitted to the Peabody Project Manager to using marijuana occasionally off site but denied ever having used it on site.
Further questioning by the NRC inspector revealed that only one of those separated was employed as a radiographer.
The others were engaged in other methods of NDE or were-4-
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general helpers not actually involved in the performance of inspections.
The NRC inspector reviewed the Peabody radiographer's log of work per-formed and selected all film produced by the suspect radiograoher since October 1,1980, to be given a thorough re-examination.
The film selection included radiographs of new welds and weld repairs.
In the case of repair radiographs, the film was compared to earlier shots to verify that technique and/or film quality had not been compromised by the suspect radiographer.
All of these radiographs were inspected for density, penetrameter image, penetrameter placement, film identification,
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proof of coverage and evident compliance with the oroper radiographic technique.
Each film was independently evaluated by the NRC inspector and the results compared to the Peabody radiographic interpretation sheets.
In all cases, the film quality was adequate and the NRC interpretations were in accord with those made by the Peabody (B&PV) Code.
inspector and the require-ments of the ASME Boiler and Pressure Vessel Each of these radiographs had been previously reviewed by a Peabody Level II inspector, a DIC Level II inspector and a DIC corporate Level III inspector.
Based on this review, it has been determined that the inspections performed by the suspect radiographer complied with the minimum requirements of the ASME B&PV Code.
No further action is considered necessary for this item.
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Follow-Up Action on an Unresolved Item
(Closed) Unresolved Item (Report No. STN 50-482/79-12):
NRC Inspection Report No. STN 50-482/79-12 identified an unresolved item concerning the retention and filing of radiographs shot on partially completed welds and designated as "information only." A discussion between the NRC inspector, the Peabody Level III inspector and the cognizant DIC Level II inspector sulted in the decision that all radiographs produced are to become part of the permanent documentation package for the particular component or weld represented. The matter was to remain unresolved until NRC verification of implementation could be made.
For this verification, the NRC inspector randomly selected four record packages for Reactor Coolant Loop pipe welds, as these have all been subjected to intermediate radiography.
"Information only" radiography is routinely performed on this heavy wall piping to locate and eliminate weld defects at a stage that minimizes the amount of metal removal.
Record packages for the weld joints examined were found to include the intermediate or "information only" radiographs.
All radiographs produced have now become part of the record package for each component or weld prior to the packages being forwarded to the records vault.
This item is closed.
6.
Welding of Safety-Related Piping The NRC inspector witnessed part of the welding on Joint FW-302 as shown on Drawing IM03EJ094 for the Residual Heat Removal (RHR) System.
This joint was being welded by welders 0-250 and 0-457 using a Dimetric machine.
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Documentation for the weld stated that two welding procedures, N-8-8-BA-2 and N-8-8-BA-4, were to be used.
Both welders are presently qualified to weld in accordance with these procedures.
A review of these procedures and the witnessing of the welding operation indicated that the weld was being produced within the established parameters.
The NRC inspector reviewed completed welding and inspection records for the following Main Steam System and ceedwater System alping joints:
Isometric No.
Joint No.
IM03AB03 F-030 IM03AB03 F-032 IM03AB03 F-032A IM03AE01 F-002 IM03AE01 F-005 IM03AE01 F-007 It03AE01 F-014 This review was conducted in the DIC record vault and included the post-weld heat treat charts produced during the stress-relieving operation.
No violations or deviations were identified.
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Reactor Coolant Loop Piping Welding
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No Reactor Coolant Loop pipe welding was being accomplished during this inspection period; but a review was made of radiography performed as is stated in paragraph 5.
A visual inspection could not be performed on completed welds or future weld joint preparations and dimensions as all had been covered with clastic sheeting and tape for environmental pro-tection.
Welding of the Loop No. 4 cross-over leg was scheduled to begin the week following this inspection.
No violations or deviations were identified.
8.
Exit Interview The NRC inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on March 13, 1981.
The NRC insoectors summarized the purpose and the scope of the inspection ano the findings.
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