ML20128G961: Difference between revisions
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NOTICE OF VIOLATION | NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-455 License No. CPPR-131 | ||
Commonwealth Edison Company | ~ | ||
As a result of the inspection conducted on July 27, 1984, through June 18, 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violation was identified: | As a result of the inspection conducted on July 27, 1984, through June 18, 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violation was identified: | ||
10 CFR 50, Appendix B, Criterion V, as implemented by CECO Topical Report CE-1-A, " Quality Assurance Program for Generating Stations," and CECO Corporate Quality Assurance Manual, Nuclear Generating Stations, Quality Requirements, equires the licensee to accomplish safety-related activities in accordance with documented procedures. | 10 CFR 50, Appendix B, Criterion V, as implemented by CECO Topical Report CE-1-A, " Quality Assurance Program for Generating Stations," and CECO Corporate Quality Assurance Manual, Nuclear Generating Stations, Quality Requirements, equires the licensee to accomplish safety-related activities in accordance with documented procedures. | ||
Contrary to the above, the Boeing steam generator snubber life cycle requalifi-cation test reported in ITT-Grinnell (ITT-G) Summary Report SPS 8471-13-0 was not perfonned in accordance with the specified ITT-G test procedure No. 5, " Life Cycle Test to Evaluate Piston Ring and Cylinder Bore Wear," dated December 11, 1984. | Contrary to the above, the Boeing steam generator snubber life cycle requalifi-cation test reported in ITT-Grinnell (ITT-G) Summary Report SPS 8471-13-0 was not perfonned in accordance with the specified ITT-G test procedure No. 5, " Life Cycle Test to Evaluate Piston Ring and Cylinder Bore Wear," dated December 11, 1984. | ||
This is a Severity Level V violation (Supplement II). | 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 statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action 'to be taken to avoid further violatons; and (3) the date when full compliance will be achieved. | 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 statement or explanation in reply, including for each violation: | ||
(1) corrective action taken and the results achieved; (2) corrective action 'to be taken to avoid further violatons; and (3) the date when full compliance will be achieved. | |||
Consideration may be given to extending your response time for good cause shown. | Consideration may be given to extending your response time for good cause shown. | ||
JUL 2 | Qp JUL 2 1985 Dated J. J. Harrison, Chief Engineering Branch s | ||
8507090371 850702 PDR | 8507090371 850702 PDR ADOCK 05000455 O | ||
PDR}} | |||
Latest revision as of 13:51, 12 December 2024
| ML20128G961 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/02/1985 |
| From: | Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20128G956 | List: |
| References | |
| 50-455-85-04, 50-455-85-4, NUDOCS 8507090371 | |
| Download: ML20128G961 (8) | |
Text
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Appendi>
NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-455 License No. CPPR-131
~
As a result of the inspection conducted on July 27, 1984, through June 18, 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violation was identified:
10 CFR 50, Appendix B, Criterion V, as implemented by CECO Topical Report CE-1-A, " Quality Assurance Program for Generating Stations," and CECO Corporate Quality Assurance Manual, Nuclear Generating Stations, Quality Requirements, equires the licensee to accomplish safety-related activities in accordance with documented procedures.
Contrary to the above, the Boeing steam generator snubber life cycle requalifi-cation test reported in ITT-Grinnell (ITT-G) Summary Report SPS 8471-13-0 was not perfonned in accordance with the specified ITT-G test procedure No. 5, " Life Cycle Test to Evaluate Piston Ring and Cylinder Bore Wear," dated December 11, 1984.
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 statement or explanation in reply, including for each violation:
(1) corrective action taken and the results achieved; (2) corrective action 'to be taken to avoid further violatons; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
Qp JUL 2 1985 Dated J. J. Harrison, Chief Engineering Branch s
8507090371 850702 PDR ADOCK 05000455 O