ML20148Q807
| ML20148Q807 | |
| Person / Time | |
|---|---|
| Issue date: | 03/30/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20148Q695 | List: |
| References | |
| REF-QA-99900219 NUDOCS 7811300154 | |
| Download: ML20148Q807 (3) | |
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6 General Electric Company Switchgear Business Department Philadelphia, Pennsylvania NOTICE OF DEVIATIONS Based on the results of an NRC inspection conducted on February 13-17, 1978, it appears that certain of your activities were not conducted in full accord with NRC requirements as indicated below:
A.
Criterion II of Appendix B to 10 CFR 50 states in part, "... The Quality Assurance Program shall provide control over activities affecting the quality of the identified structures, systems, and components, to an extent consistent with their importance to safety Contrary to the above, the program as described in the QA Manual does not identify or control significant engineering procedures in use, namely:
10-11.00, " Engineering Change Notice procedure," and 10-12.00, " Qualification test reports procedure."
B.
Criterion II of Appendix B to 10 CFR 50 states in part, "...
The Quality Assurance Program shall provide control over activities affecting the quality of the identified structures, systems, and componeits, to an extent consistent with their importance to safety Contrary to the above, Exhibit 3, Design and Developement Instruction 2-85.1300 of the QA. Manual does not accurately describe engineering change procedures actually in use.
Engineering procedure 10-7.00.,
" Drawing Control Procedures," is one example.
C.
Criterion II of Appendix B to 10 CFR 50 states in part, "The Quality Assurance Program shall provide control over activities affecting the quality of the identified structures, systems, and components, to an extent consistent with their importance to safety...."
Contrary to the above, Exhibit 2, Design and Development Instruction 2-85.1300 of the QA Manual does not describe engineering responsibi-lities associated with qualification testing activities and the contract requisition engineer's responsibilities are only partially identified.
D.
Criterion III of Appendix B to 10 CFR 50 states in part, " Measures shall also be established for the selection and review for suit-ability of application of materials, parts, equipment, and pro-cesses that are essential to the safetyrelated functions of the structures, systems and components.
l-781130015%
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The Design Adequacy Review Certification for equipment designated for Class 1 application in nuclear power plants, part of Design and Development Procedure, 2-85.1300, states is part, " Appendix 3 list
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requirements in the specification for this requisition which are considered special with reference to the usual application of this r
equipment."
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' Contrary to the NRC requirement and the QA program requirement, the following deviations were found:
1.
The Design Frequency Review Certification for a customer's specification 10466-E-009 did not identify special require-ments associated with qualification testing and establishing life data in accordance with IEEE 323.
2.
The Design Adequacy Review Certification for a customer's specifications 21A9300, Revision 1 and 21A9300, Revision 0, did not list.special requirements associated with equipment qualification testing to IEEE 323.
E.
Criterion X of Appendix B to 10 CFR 50 states in part, "A program I
for inspection of activities affecting quality shall be established and executed by or for the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the-activity...."
Quality Procedure D-2, In-process and Final Inspection Test, para-graph 3.3, of the Quality Assurance Manual states in part, "All subassemblies and final assemblies will be tested in accordance with applicable instructions. _No item will bear an inspe ~'in/ list acceptance stamp if parts 'are missing,- repairs have not been com-pleted, or any. Other defects have not been corrected per QA instru-tions."
Contrary to the above requirements, the following deviations were found af ter the M/C-test and Inspection Records (Form SE 462 I Revision 1) for 7.2 KV switchgear for a high pressure core spr(ay),
system was signed-off and dated by-a quality appraisal, QCE,
. approving the equipment for packing and shipment, namely:
1.
The HPCS Pump Feeder unit contained a loose electrical lead to one of the two heating elements.
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_ 2.
The 480 V transformer feeder unit contained two loose electri-cal leads to an IAC relay and two loose leads to indicatior lights.
F.
Criterion X of Appendix B to 10 CFR 50 states in part, "A program for inspection of activities affecting quality shall be established and executed by or for the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity...
Examinations, measurements, or tests of material or products processed shall be performed for each work operation where necessary to assure quality Quality Procedure D-2, In-process and Final Inspection Test, para-graph 3.3 of Quality Assurance Manual states in part, "All sub-assemblies and final assemblies will be tested in accordance with applicable instructions.
No item will bear an inspection / list acceptance stamp if parts are missing, repairs have not been completed, or any other defects have not been corrected per QA instructions."
Contrary to the above requirements, the following deviations from the switchgear frame fabrication drawing Ol68C3099 and Design Instruction 191.001 for the 7.2 KV switchgear mentioned above were found:
1.
A required weld-was missing on each horitzontal seismic member on each 90 inch door of the five unit lineup inspected.
2.
Several required welds on the horizontal seismic member were not spread in accordance with the fabrication drawing.
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