ML20010E497
| ML20010E497 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/24/1981 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010E493 | List: |
| References | |
| 50-454-81-09, 50-454-81-9, 50-455-81-08, 50-455-81-8, NUDOCS 8109040185 | |
| Download: ML20010E497 (2) | |
Text
t Appendix A NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-454 Docket No. 50-455 As a result of the inspection conducted on July 29-31, 1981, and in' accord-ance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980) the following violations were identified. The violations apply to Unit 1 only.
1.
10 CFR 50, Appendix B, Criterion V, states, in part, that " Activities affecting quality shall be prescribed in documented instructions, pro-cedures, or drawings.
. and shall be accomplished in accordance with these instructions, procedures, or drawings."
Commonwealth Edison Company Tcpical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 5 that "Tne quality assurance actions carried out for design, construction, testing, and operation activities will be described in documented instructiont., procedures, drawings, specifications, or checklists. These documents will assist personnel in assuring tPat important activities have been performed. These documents will also reference applicable acceptance criteria which must be satisfied to assure that the quality related activity has been properly carried out."
Contrary to the above, the snubber structural attachment assemblies erected within the Unit 1 Containment were not inspected and accepted by the Quality Control staff as required by the established site work procedures.
This is a Severity Level V violation (Supplement II).
2.
10 CFR 50, Appendix B, Criterion III, states, in part, "The design control j
measures shall provide for verifying or checking the adequacy.of design, such as by the performance fo design reviews.
Design control mea-sures shall be applied to iters such as.
. stress.
Design changes, including field changes, shall be subjected to design control measures commensurate with those applied to the original design.
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 3 that "The fundamental vehicle for design control involves multi-level review and/or evaluation of design docu-ments by individuals or groups other than the original designer or l
designer's immediate supervisor whose authority and responsibility are identified and controlled by written procedures. The design documents include, but are not limited to, system flow diagrams, design and construction specifications, load ~ capacity data sheets, I
design reports, equipment specifications, process drawings."
t 8109040185 810824 gDRADOCK 05000454 PDR
Appendix A Contrary to the above, three instances were observed where design changes for snubber assembly installation did not receive design review and approval measures commensurate with the original design calculations. Furthermore, the modifications were completed prior to issuance-of a Field Change Request.
This is a Severity Level V violation (Supplement II).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written state-ment or explanation in reply, including for each item of noncompliance:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this respons: shalt be submitted under oath or affirmation. Consideration may be given to extending your-response time for good cause shown.
Dated C. E. Norelius, Director Division of Engineering and Technical Inspection