ML20236B812: Difference between revisions
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t NOTICE OF VIOLATION I | t NOTICE OF VIOLATION I | ||
GPU Nuclear Corporation | GPU Nuclear Corporation Docket No. | ||
10 CFR 50, Appendix B, Criterion V and Chapter 3.0 of the Oyster Creek Quality Assurance Manual requires, in part that activities important to safety be pre-scribed by documented procedures, instructions, and/or drawings of a type | 50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 EA 88-243 As a result of an inspection conducted on July 31 - September 10, 1988, and an AIT inspection conducted October 13-18, 1988, as well as review'of information sub-mitted to the.NRC on December 28,'1988' a violation of NRC requirements was iden-tified. | ||
appropriate to the circumstances and that the activities be accomplished in | In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the particular violation is set forth below. | ||
Contrary to the above, the instructions provided in Step 7.72 of Station Pro-cedure 665.5.003, " Main Steam Isolation Valve Leak Rate Test," which is a | 10 CFR 50, Appendix B, Criterion V and Chapter 3.0 of the Oyster Creek Quality Assurance Manual requires, in part that activities important to safety be pre-scribed by documented procedures, instructions, and/or drawings of a type appropriate to the circumstances and that the activities be accomplished in l | ||
This is a Severity Level IV Violation. | accordance with these documents." | ||
Contrary to the above, the instructions provided in Step 7.72 of Station Pro-cedure 665.5.003, " Main Steam Isolation Valve Leak Rate Test," which is a j | |||
surveillance test that verifies the quality of equipment important to safety, were inappropriate to the circumstances in that the procedure provided general rather than specific instructions to " return all valves to their as found positions." As a result, operators misread Step 7.72 and mispositioned valve V-14-6, an Isolation Condenser vent line isolation valve, leaving it in the closed position, rather than the required open position. This condition ex-isted during plant operation from August 10 to September 2, 1988. | |||
This is a Severity Level IV Violation. | |||
Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation (Licensee) is hereby required to submit a written statement or explanation to this office within 30 days of the date of this Notice. This reply should be clearly marked as a | Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation (Licensee) is hereby required to submit a written statement or explanation to this office within 30 days of the date of this Notice. This reply should be clearly marked as a | ||
" Reply to a Notice of Violation" and should include for each alleged violation: | |||
(1) admission or denial of the alleged violation, (2) the reasons for the violation if admitted, (3) the corrective steps that have been taken and the results achieved, (4) corrective steps that will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Consideration may be given to extending the response time for good cause shown. | (1) admission or denial of the alleged violation, (2) the reasons for the violation if admitted, (3) the corrective steps that have been taken and the results achieved, (4) corrective steps that will be taken to avoid further violations, and (5) the date when full compliance will be achieved. | ||
Consideration may be given to extending the response time for good cause shown. | |||
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Latest revision as of 02:56, 3 December 2024
| ML20236B812 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/14/1989 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236B802 | List: |
| References | |
| 50-219-88-23, 50-219-88-80, EA-88-243, NUDOCS 8903210308 | |
| Download: ML20236B812 (1) | |
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GPU Nuclear Corporation Docket No.
50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 EA 88-243 As a result of an inspection conducted on July 31 - September 10, 1988, and an AIT inspection conducted October 13-18, 1988, as well as review'of information sub-mitted to the.NRC on December 28,'1988' a violation of NRC requirements was iden-tified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the particular violation is set forth below.
10 CFR 50, Appendix B, Criterion V and Chapter 3.0 of the Oyster Creek Quality Assurance Manual requires, in part that activities important to safety be pre-scribed by documented procedures, instructions, and/or drawings of a type appropriate to the circumstances and that the activities be accomplished in l
accordance with these documents."
Contrary to the above, the instructions provided in Step 7.72 of Station Pro-cedure 665.5.003, " Main Steam Isolation Valve Leak Rate Test," which is a j
surveillance test that verifies the quality of equipment important to safety, were inappropriate to the circumstances in that the procedure provided general rather than specific instructions to " return all valves to their as found positions." As a result, operators misread Step 7.72 and mispositioned valve V-14-6, an Isolation Condenser vent line isolation valve, leaving it in the closed position, rather than the required open position. This condition ex-isted during plant operation from August 10 to September 2, 1988.
This is a Severity Level IV Violation.
Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation (Licensee) is hereby required to submit a written statement or explanation to this office within 30 days of the date of this Notice. This reply should be clearly marked as a
" Reply to a Notice of Violation" and should include for each alleged violation:
(1) admission or denial of the alleged violation, (2) the reasons for the violation if admitted, (3) the corrective steps that have been taken and the results achieved, (4) corrective steps that will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Consideration may be given to extending the response time for good cause shown.
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