IR 05000440/1978015
| ML19282B304 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/22/1979 |
| From: | Hayes D, Konklin J, Naidu K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282B301 | List: |
| References | |
| 50-440-78-15, 50-441-78-14, NUDOCS 7903120570 | |
| Download: ML19282B304 (18) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF IN',PECTION AND ENFURCEMENT
REGION III
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Report No. 50-440/78-15; 50-441/78-14 Docket No. 50-440; 50-441 License No. CPPR-148; CPPR-149 Licensee: The Cleveland Electric Illuminating Company Post Office Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Units 1 and 2 Inspection At: Perry Site, Lake' County, OH Inspection Conducted:
No-aber 28 - December 1,1978 fka l
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//f // 75 Inspectors:
J. E. Konklin
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K. R. Nai
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Accompanying Personnel:
J. F. Suermann 22-f_
Approved By:,D afe[C ef
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Projects Sect on Inspection Summary 50-440/78-15 Inspection on November 28-December 1,1978 (Report No.
and 50-441/78-14)
Areas Inspected:
Ongoing site construction activities (Units 1 and 2); -
licensee action relative to previous items of noncompliance and unresolved items (Units 1 and 2); work activities and quality records relative to containment liner welding (Units 1 and 2): work act.ivities and quality records relative to steel structures and supports (Units 1 and 2); and work activities
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relative to conta#"~ ant basa liner pressure testing (Units 1 and 2).
This ir, ton involved a total of 62 onsite inspector-hours s.
bree NRC inspectors.
Results: Of the five areas inspected, no items of noncom-Three pliance or deviations were identified in two areas.
items of noncompliance were identified in three areas'(Inf raction -
inadequate measures to control purchased materials - Section !i, Paragraphs 1.c and 2.e; infraction - inadequate measures to control welding processes - Section II, Paragraphs 2.a and 2.b; deficiency - inadequate documentation of pressure test reports - Section II, Paragraph 3.
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DETAILS Persons Contacted
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Principal Licensee Employees
- M. R. Edelman, Manager, Nuclear QA Department
- G.
W. Groscup, Manager, Nuclear Engineering Department
- D. A.
Fitzpatrick, Site Construction Manager
- J. M. Lastovka, CQS General Supervising Engineer Other Personnel
- T. L. Arney, CQS Quality Engineering Supervisor (GAI)
- W. J. Kacer, CQS Quality Control Supervisor (KEI)
- P. L. Gibson, CQS Quality Administration Supervisor (KEI)
J. J. Connelly, CQS Lead Civil Quality Engineer (GAI)
- J. W. Mehaf fey, CQS Lead Mechanical Quality Engineer (GAI)
R. E. Crofton, CQS Lead Piping Quality Engineer (GAI)
The inspectors also contacted other 2icensee and contractor employees, including members of the quality, technical and engineering staffs.
- Denotes those who attended the exit interview.
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Licensee Action on Previous Inspection Findings (Closed) Noncompliance (440/78-02-23; 441/78-01-23):
PBI requirements for followup action.
The previous RIII report (78-02; 78-01) noted that PBI's QC/QA program did not establish requirements for followup, including reaudit of deficient areas to assure that corrective action had been taken.
During this inspection, the inspector reviewed the PB1 QC/QA Manual for
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Safety Related Structural Steel Erection, Second Issue, dated November 11, 1978, and noted that Section XIII, Surveillance and Audit, now requires copies of the audit to be provided to the Contracts Manager and QA Manager, with the due date of the corrective action and reaudit included, and also requires a reaudit of deficient areas to be performed within 45 days of the initial audit.
This item is considered to be resolved.
(Closed) Noncompliance (440/78-02-07; 441/78-01-07):
Inadequate
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storage of nut and bolt assemblies and weld wire by Great Lakes (GLC).
The previous RIII report (78-02; 78-01) noted that approximately 20 safety related bolt and nut assemblies and 1/2 pound of weld wire were inadequately stored by GLC in
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the Control Complex Building. During this inspection, the inspector inspected the GLC work areas in the Control Complex Building and noted that safety related nut and bolt assemblies No were stored on pallets and were properly identified.
inadequately stored weld wire was found.
This item is,.
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considered to be resolved.
(Closed) Unresolved Item (448/78-13-01; 441/78-12-01):
Handling of returned welding materials. The previous RIII report (78-13; 78-12) noted that requirements regarding handling of returned welding materials needed to be clarified in the Pullman Power Products (PPP) procedures related to welding of safety related During this inspection, the inspector reviewed PPP piping.
Procedure VIII-3, Control of Welding Materials (Field), and noted that the revision of October 17, 1978 now contains adequate provisions regarding the handling of returned welding materials. This item is considered to be resolved.
(Closed) Unresolved Item (440/78-05-01; 441/78-04-01):
Lack of identificatien tags on reinforcing steel. The previous RIII report (78-05; 78-04) noted that two bundles of Grade 60 reinforcin steel were stored by Dick Corporation yith no identification tags attached, but that this had been During previously identified in a CEI QA surveillance report.
this inspection, the inspector inspected the Dick Corporation rebar storage in the No. 1 and Ec. 2 main storage yards and in the small rebar storage area outside the southeast No untagged bundles of reinforcing steel were found gate.
This item is considered to be resolved.
in the storage areas.
PBI (Closed) Unresolved Item (440/78-09-01; 441/78-08-01):
QC/QA Manual not specifying the year of applicable standards.
The inspector reviewed the PBI QC/QA Manual for Safety Related Structural Steel Erection, Second Issue, dated November 11, 1978, and noted that Section VI now specifies that work shall be performed in accordance with AWS Dl.1-72, together with AWS Dl.1, Revision 1-73 and AWS Dl.1, Revision 2-74.
This item is considered to be resolved.
(Closed) Noncompliance (440/77-07-8; 441/77-07-8):
Calibration The of temperature monitoring devices used by Kelley Steel.
prev'ous RIII report (77-07) noted that Kelley Steel did not have procedural requirements to assure that temperature monitoring devices used to measure weld rod oven temperatures are properly calibrated, and that records were not available to determine the accuracy of these temperature monitoring devices. During this inspection, the inspector reviewed
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Attachment Specificaton SP-708, Revision 3, dated October 11, 1978, which is attached as part of Specification SP-85, Revision 1, dated February 27, 1976, Specification for Erection of Structural Steel. Section 1:06.11 of SP-85, which is titled Control of Measurements, Inspection an,d Test Equipment, now requires calibration of measuring devices to equipment that is certified to standards recognized by the National Bureau of Standards.
The inspector also reviewed the Certificates of Calibration issued by Herron Testing Laboratories for the two Kelley weld rod oven thermometers.
Certificate No. 8967 showed thermometer S/N KS-1 had been calibrated on October 24, that 1978, and Certificate No. 8967-1 showed that thermometer S/N KS-2 had been calibrated on November 7,1978.
The certificates show traceability to the National Bureau of Standards.
In addition, the inspector verified, by that inspection of the two Kelley Steel weld rod ovens, thermometers S/N KS-1 and S/N KS-2 were in use and were This registering within the required temperature range.
item is considered to be resolved.
(Closed) Noncompliance (440/78-04-04; 441/78-03-07):
Inadequate storage and identification of Grade 40 and Grade 60 rebar.
The previous RIII report (78-04; 78-03) noted that unmarked Grade 40 rebar was observed, and that 30 pieces of Grade 60 rebar were found lying partially in oud and water in the Dick Corporation storage area. The part of this noncom-pliance related to Grade 40 rebar was resolved in a previous RIII report (78-11; 78-10).
During this inspection, the inspector inspected the Dick Corporation rebar storage in the No. 1 and No. 2 main storage yards and in the small rebar storage area outside the southeast gate. The Grade 60 rebar was properly stored on dunnage, and was properly identified. This item is considered to be resolved.
(Closed) Noncompliance (Number 1 of Investigation Report No.
50-440/78-08; 50-441/78-07). This item concerned the detail J _
of inspection criteria provided by the inspection procedure.
The item also concerned the initials of inspectors performing embed inspections being placed on the inspection checklist by someone other than the inspector. Region III Investigation 50-440/78-08; 50-441/78-07, paragraph 41 concluded Report No.
the embed inspection procedure had been revised to provide that more detailed criteria. The Nuclear Regulatory Commission letter to the Cleveland Electric Illuminating Company dated August 16, 1978, concluded that corrective action was completed
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for item 1.a.
The review of the audit performed by the Cleveland Electric Company and a review of documented inspections was per-formed by the inspector.
The details of this review are contained in Section III of this report. No initials were 1-)und that appeared to have been made by persons other than tha inspector performing inspections. This item is considered to be reso?ved.,.
(Closed) Noncompliance (Number 2 of Investigation Report No.
50-440/78-08; 50-441/78-07).
Lack of proper and complete The corrective inspector, qualification and certifications.
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actions were reviewed and found ccupleie by the inspector.
details of this review are contained in Section III of this Comp.lete and correct inspector qualification and certi-report.
fication have been accomplished.
This item is considered to be resolved.
(Closed) Noncompliance (Numbec 3 of Investigation Report No.
50-440/78-08; 50-441/78-07):
Lack of timely corrective action This item was regarding deficiencies and nonconformances.
previously reported as closeo hv D.III Inspection Report No.
50-440/78-11; 50-441/78-10.
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Section I
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Prepared by J. E. Konklin
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Reviewed by D. W. Hayes, Chief Projects Section 1.
Review of Licensee Action on Previous Inspection Findings The RIII inspector reviewed the licensee actions relative to the resolution of specific noncompliances aad unresolved items which had been identified in previous RIII inspection reports, and which were still in an open status prior to this inspection. The items reviewed, and the licensee actions relative to the resolution of each item, are discussed in the foregoing section of th'is report.
2.
Review of Embedment Inspection Program Previous RIII reports (440/78-11; 441/78-10), (440/78-12; 441/78-11), (440/78-13; 441/78-12), and (440/78-14; 441/78-13) have discussed the ongoing status of the embedment inspection and evaluation program being conducted by CEI in response to the RIII letter of July 13, 1978 to CEI.
During this inspection, the inspector reviewed the resolutions of the findings of CEI Audit Report No. 52, and discussed with the licensee the results of the CEI evaluation of the adequacy of in-place embedments.
CEI Audit Report No. 52, dated May 16, 1978, contains an evaluation of the adequacy of the embedment inspection program. Twelve Audit Action Requests (AAR's) were issued as part of Audit Report No. 52, and covered a numoer of deficiencies in the embedment inspection program.
The inspector reviewed the revised responses from CQC to CQE for the ten AAR's which still remain open, and the CQE evaluation of the responses, dated November 3,1978.
The CQE evaluation, and the inspector's review, indicated that the responses are satisfactory, but that a followup audit is required by CQE to verify that the actions dis-cussed in the responses have been implemented. A previous
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RIII report (440/78-11; 441/78-10) identified an unresolved item (440/78-11-01; 441/78-10-01) regarding the resolution of the findings in Audit Report 52 and completion of
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the evaluation of in-place embedments by CEl.
That unresolved item remains open under the previous designa-tion noted above pending completion of the followup audit by CQE.
3.
Licensee Action Reletive to Nonconforming Embedments1 and Structural Steel arevious RIII report (440/78-02; 441/78-01) identified
.ancompliance regarding weld defects in safety related a
embedments and structural steel columns.
CEI reported these deficiencies as a significant deficiency under 10 CFR 50.55(e) on February 4, 1978. The subsequent Interim Report was dated March 6, 1978.
During this inspection, the inspector reviewed the status of the licensee's corrective actions to date, and discussed with the licensee the conclusions of the Final Report on this subject, which was mailed to Region III by CEI on December 1, 1978.
The results of the stud tensile testing program performed by Nelson Division of TRW for CEI were discussed in a previous RIII report (440/78-14; 441/78-13).
Based on the results of those tests, and the detailed inspection of all embedments fabricated but not installed prior to February 4, 1978, CEI has concluded in the "Embedment
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Evaluation Report" attached to the December 1,1978 Final Report that all in-place embedments will meet their design load requirements.
With regard to the 17 reactor building columns which were identified as nonconforming in the above 10 CFR 50.55(e) reports, all of the defective welds have been repaired and MT tested, and documented on NR CQC No. 248, which was closed on' September 15, 1978.
The inspector observed the 17 columns in storage and found no evidence of defective welds. The licensee has cleared the columns for installation, which is scheduled for late Decem' 1 1978.
The inspector notified the licensee during the exit interview that the previous item of noncompliance (440/78-02-16; 441/78-01-16), and the 10 CFR 50.55(e) item will remain open pending receipt and review of the final evaluation report by NRC.
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Status of Ongoing Construction Activities _
The inspector observed ongoing work activities and status in the Units 1 and 2 containment equipment the intermediate buildings and auxiliary buildings, building, the control complex building, the rebar storage areas, and the safety related piping and structural steel storage areas.
The Unit 2 reactor pressure vessel was in a vertical position in the Reliance Trucking rigging structure preparatory to installation in the containment vessel, which is now scheduled for late December.
No items of noncompliance or deviations were identified in the areas inspected.
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Section II Prepared by K. R. Naidu
Reviewed by R. L. Spessard, Chief
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Engineering Support Section 1 Observation of Spent Fuel Storage Pool Installation 1.
Activities, Units 1 and 2_
The inspector observed the activities relative to the installacion of the spent fuel storage pool and deter-mined the following:
The inspector observed a pool of water trapped in a.
the spent fuel cask area which could cause degradation of the stainless steel liner plates. This matter was brought to the attention of the contractor Newport News Industrial Corporation (NNI).
The contractor agreed with the inspector that this condition was contrary to acceptable industry housekeeping practices and initiated corrective action to pump the water out.
The inspector requested the contractor to provide additional information as to the measures that will be established in the future, in the form of surveillance reports which will bring instances of adverse housekeeping practices to the immediate attention of NNI management to facilitate timely corrective action.
This is con-sidered an unresolved item (440/78-15-01; 441/78-14-01).
Similar items which were contrary to acceptable house-keeping practices were identified by the licensee and are documented in the Corrective Action Request (CAR)
No. 0450, pages 4 and 5.
Temporary Visqueen enclosures were erected around b.
areas where welding was being performed for protection against inclement weather conditions.
Liner plate sections, with Nelson Stud attachments, c.
had been installed. These liner plate sections were purchased to Specification SP-665, titled " Fabrication and Delivery of Stainless Steel Liners for Fuel Pools."
Paragraph 2:07:2, subparagraph 6, of SP-665 states that the Nelson Stud welds shall be inspected in accordance with paragraph 4.30 of the AWS Dl.1-1975 Code.
Contrary to this requirement, several Nelson Studs
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which had been repaired by stick welding were not struck with a hammer and bent to an angic of 15 degr,es from the original axis, as required by the code.
The fillet weld size on some of the Nelson Studs appeared to be less than 5/]6 inch, as specified in paragraph 4.28.11.1 of the code; however, no actual measurements were made by the NRC inspector.
The inspector informed the licensee that inadequate measures were established by the licensee to perform adequate inspections to control purchased material, in this instance, liner plate sections, to assure that these liner plates conformed to the specification requirements. This is identified as an item of noncompliance, contrary to the requirements o.f Criterion VII of 10 CFR 50, Appendix B.
(440/78-15-02; 441/78-14-02)
One item of noncompliance was identified in the above areas.
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2.
Observation of Containment Structural Steel Welding Activities, Units 1 and 2 The inspector observed welding activities in progress a.
during the evening shif t on November 28, 1978 in the Ut.. 2 containment. The ambient temperature was reported to be about 30 F.
Neither heating bars nor similar equipment were being used to main-tain the preheat during interruptions. Discussions with the NNI inspectors indicated that adequate measures were not established to verify and document that the preheat temperature was above 70 F, as required in the relevant specification, SP-17, for the following reasons:
(1) The NNI welding inspectors had not documented their verification of preheat in their field inspection book; however, Weld History Records, which are prepared a day or so later, document that they were verified to be greater than 70 F.
This is an attribute which is required to be verified.
(2) To maintain the preheat, or to prevent the heat from welding from rapid di ssipation during welding operation interruptions,. rating bars have been used previously. The NNI inspectors stated that
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they were under the erroneous assumption that heating bars were being used. Realizing the inadequate preheat arrangements, the contractor voluntarily terminated welding operations in progress in Unit 1 and 2 containments.
(3) Weld Procedure Specification (WPS) 465-NC-W001 is not specific as to how the metal should be preheated and " soaked" to parmit welding, cleaning and grinding, which would require the welding process to be interrupted.
Summing up the above, the inspector informed the licensee that inadequate measures were established to control the welding process and this was an item of noncompliance contrary to the requirements of Criterion IX of 10. CFR 50, Appendix B.
(440/78-15-03; 441/78-14-03)
b.
Discussions with the NNI QA manager indicates that a program was not established to control the welding machines, which are in operation, to meet the require-ments of paragrap'n 3.1.2 of the AWS Dl.1-75 Code.
Furthermore, there was no documented evidence that the contractor's inspectors verified that the requirements of paragraph 6.3.2 of the AWS Dl.1-75 Code were met.
The relevant specification, SP-17, requires conformance to AWS Dl.1-75.
This condition is considered another example of the item of noncom-pliance previously described in subparagraph a, and it is contrary to the requirements of Criterion IX of 10 CFR 50, Appendix B.
The inspector observed an excessive fitup gap c.
between the drywell liner plate and the equipment hatch. Further discussions with the contractor personnel indicated that this situation was documented in Nonconformance Report (NCR)96-241.
Drawing #288332, referenced in the NCR, inadequately identifies the size of a partial penetration fillet weld. The contractor personnel could not satis-factorily explain how this drawing underwent the review cycle. The NNI QA manager agreed to obtain information on the size of the weld and include it
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in the drawing. The inspector has no further questions on this subject.
d.
The inspector observed a mismatch condition on the drywell liner plate. Review of the weld history
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record for this weld identified as #2-1(2-16/2-17)
indicates that the mismatch condition was not documented. At the request of the NRC inspector, the NNI QC inspector measured the offset to be 3/16"; the permissible offset according to
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paragraph 6.5.3 of UNI instruction 946-N-W001, Revision F was 1/16".
The NNI inspector stated that the weld had not been visually inspected and therefore, the mismatch condition had not been documented. The NNI inspector assured the NRC inspector that the mismatch would be identified and repaired. The NRC inspector has no further questions on this subject.
The inspector questioned the size on some of the e.
welds on the weir wall stiffener angles.
The staggered 4 long 3/16" size welds attaching the carbon steel angles to the stainless steel liner r
plate appeared to be inadequate in size; at the request of the NRC inspector, the NNI QC inspectors measured four welds which did not meet 3/16" size at some places in the length of 4".
The.NNI inspectors informed the NRC inspector, that at the time these plates were initially received from the vendor, the inadequate size of the welds was brought to the attention of their supervisor.
It was reported that the QC supervisor instructed the QC inspectors to limit the scope of inspection to identify possible weld cracks which may have developed during transit.
The licensee informed the NRC inspector that he requested NNI to reinspect the welds or possible undersize welds.
This item is considered another example of inadequate control of purchased material previously identified in paragraph 1.c, and it is contrary to Criterion VII of 10 CFR 50, Appendix B.
f.
The inspector observed a mismatch conditfon on the weir wall liner plate weld #2-187 at 181 15' azimuth and elevation 581' 41".
The NRC inspector requested the licensee to investigate this matter.
Subsequent to the inspection, the licensee ir. formed the inspector on December 6,1978, that NNI surveyed the area and determined that the out of roundness was measured to be 1/2" and within the permitted 1 1/2" out of roundness.
The inspector has no further questions on this subject.
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One item of noncompliance was identified in the above areas.
3.
Review of Pressure Test ' Reports, Units 1 and 2 The inspector reviewed the Pressure Test Reports (PTR)
relative to Units 1 and 2 Reactor Vessel Pedestal embedments Leak Chase Systems. NNI procedure 465-N-T-005 titled " Pressure Test for the Containment Vessel Base Liner and Leak Chase System," Revision A, dated March 4, 1977 was used to perform the pressure tests.
The inspector identified the following:
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In four PTRs, which covered Unit 1, Area 3, Zones a.
1 through 4, the column " certified by" was not filled. These tests were performed on May 10 and 11, 1978. The NNI QA manager stated that during that period the " certified by" column was not required to be filled.
b.
One PTR which covered Unit 1, Area 1, Zone 1-1,
.erson was listed as dated November 23, 1977, a craft
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the operator, and he was not qualified.
This report was certified by a Level II inspector.
The IC41 QA manager stated that the craft person monitored the gauges, that he should not have entered his name on the PTR and that the test was actually performed by the Level II
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PTRs on Unit 2 had been recently performed.
Both the operators and certifiers were qualified Level II inspectors. The certifier attests his signature after the pressure gauge used in the test returns from NNI - Virginia after a successful calibration verification.
The inspector identified this matter (3.a and 3.b above)
as a deficiency in documentation of the personnel who conducted the tes's since the actual test results were determined acceptable. The inspector informed the licensee that this deficiency in documentation is considered an 10 CFR 50, Appendix B.
Th NNI QA manager stated that he would review all the PTRu to date and develoo a system to interpret the existing PTRs and to accurately document future PTRs.
(440/78-15-04; 441/78-14-04).
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One item of noncompliance was identified in the above areas.
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Section III Prepared by W. H. Hansen
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Reviewed by D. W. Hayes, Chief Projects Section 1.
The Nuclear Regulatory Commission RIII Investigation Report No. 57-440/78-08; 50-441/78-07 identified (item 1.b) that the initials of inspectors who performed embed inspections were placed on inspection check lists by someone other than the inspector.
As a result of this finding, the licensee performed a review of completed embed inspection checklists and nonconformance reports.
During this inspection, the licensee presented the results of the review. The review was performed by individuals not associated with inspection.
The review included more than 50% of the embed check lists (462 out of 800 check lists) and concluded that there were no additional instances where a person placed the initials of the inspector performing the inspection on the check list. During this inspection the following documents were randomly selected and reviewed by the RIII inspector:
Twenty-five Receipt Inspection Nonconformanca
a.
Reports were selected. The reports are contained in document control files CQC Section 8, File
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Fifteen CQC inspection reports c.
Seventy-five signatures on Receipt Inspection documents, d.
Fifteen construction quality action requests.
During this review, inspector initials were compared with the signature and initial log maintained by the Construction Quality Control Supervisor.
No evidence of inspector initials being placed on documents by
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someone other than the person performing the inspection were detc ted. No items of noncompliance were identified and this item is closed.
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2.
The Nuclear Regulatory Commission RIII Investigation Report No. 50-440/78-08; 50-441/78-07 identified conditions (items 2a through 2k) that were not in compliance with the American National Standards Institute N45.2.6 " Qualifications of Inspection,
Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants": in that, (Summarized):
Certificates of goalification deviated from a.
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requirements.
b.
The basis for certification was not in all cases properly documented.
c.
Certifications were made by an individual not certified as a higher level inspector than the level he certified nor in one instance qualified to make the certification.
d.
An individual was assigned responsibility for an area for which he had no qualification or certification.
During this inspection, the qualification and' certification files for the following individuals were reviewed to determine compliance with the requirements of ANSI N45. 2. 6 and SNT-TC-1A.
W. J. Kacer Correctly Certified Level III ANSI D. Cooper Correctly Certified Level III ANSI-Civil D. Colne Correctly Certified Level III ANSI-Electrical R. Hilton Correctly Certified Level III ANSI-Mecl.anical Level III SNTC-TC-1A J. Mathis Correctly Certified Level III ANSI-Mechanical R. Czyzewski Correctly Certified
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Level II ANSI-Civil M. Kritzer Correctly Certified Level III ANSI-Civi;
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A. McCoy Correctly Certified Level II ANSI-Civil J. White Correctly Certified Level II ANSI-Civil
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C. Fennell Correctly Certified Level II ANSI-Mechanical C. Freeman Correctly Certified Level II ANSI-Mechanical Level II SNT-TC-1A M. Hipple Correctly Certified Level II AN3I-Mechanical Level II SNT-TC-1A Correctly Certified A. Hurbanek e
Level II ANSI-Mechanfr..sl Level I SNT-TC-1A B. McAnally Correctly Certified Level II ANSI-Mechanical Level II SNT-TC-1A R. Mitchel Correctly Certified Level II ANSI-Mechanical Level II SNT-TC-1A S. Piatek Correctly Certified Level II ANSI-Mechanical Level II SNT-TC-1A L. Young Correctly Certified Level II ANSI-Mechanical Level II SNT-TC-1A E. Johnson Correctly Certified Level II ANSI-Receipt Inspection J. Kerr Correctly Certified Level II ANSI-Receipt Inspection D. Ronan Correctly Certified
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Level II ANSI-Receipt Inspection In each of the cualification packages reviewed the following specific points were verified:
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The qualifications of the individual making the a.
certification were adequate.
Adequate documentation concerning education and b.
experience was en file.
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The certificates included:
c.
(1) The employer's name.
(2) The duration of qualification.
The basis used for certification was contained in d.
the individual qual'.fication folders.
The identity of the examiner was in each case e.
provided.
The certified qualification log provided information f.
to support the qualifications, Persons were consistently assigned to areas for g.
which they were certified.
The sampling of certification packages consisted of and 20 out of 26 individuals in the areas of supervision, civil, mechanical and receipt inspection specialties.
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No items of noncompliance were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to decernine whether they are acceptable An unresolved items of noncompliance, or deviations.
items, item disclosed during the inspection is discussed in Section II, Paragraph 1.a.
Exit Interview (denoted The inspectors met with licensee representatives under Persons Contacted) at the conclusion of the inspection on December 1, 1978.
The inspectors summarized the purpose and findings of the inspection.
The licensee acknowledged the findings reported herein.
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