ML20205B664
| ML20205B664 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/04/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205B654 | List: |
| References | |
| 50-219-85-14, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8509120188 | |
| Download: ML20205B664 (2) | |
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APPENDIX A NOTICE.0F ' VIOLATION GPU Nuclear Corporation Docket No. 50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 Forked River, NJ 08731 As a result of the inspection conducted on May 14-17, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), published in the Fe-deral Register on March 8, 1984, (49 FR 8583), the following viciation was identified:
Criterion III of Appendix B to 10 CFR 50 requires the establishment of measures to assure that applicable regulatory requirements and design basis for important to safety structures and components are correctly translated into specifications, drawings, procedures and instructions.
Section IV, Part 1, Subsection A, of Revision 2 of the Jersey Central Power and Light / General Public Utilities (JCP&L/GPU) Operational Quality Assurance Plan, the plan in effect at the time of the work, states, in part, "the Manager-Generation Engineering is responsible for controlling design work and administering the design control activities relating to modification or addition of structures, components and systems."Section X, Part 1, Subsection F, of Revision 2 of the JCP&L/GPU Operational Quality Assurance Plan states, in part, "the Manager-Generation Engineer-ing is responsible for the issuan e and approval of specification, draw-ings and installation requirements associated with modifications and ad-ditions..."
Contrary to the above, activities relating to IE Bulletins 79-02 and 79-14 were performed either: (1) with no documented engineering procedures and specifications, or (2) with procedures-and instructions which were not controlled in accordance with the Operational _QA plan.
Examples of the first category include: Calculation No. 8.13.309 - thermal expansion analysis of line No. 6-ND-10; Calculation No. 8.31.208 - containment spray system pipe support calculations; calculation for thermal analysis of emergency condenser line 10-NE-S from the reactor to NE01-A,B.
Examples of the second category include:
Field walkdown check list for implementa-tion of I.E.Bulletin 79-14; 80-44 procedure for the modification and re-pair of pipe supports; 80-45 procedure for the relocation of pipe supports; PP-001 procedure for the implementation of IE Bulletin 79-14; Special No.
79-31 procedure'for inspection test and installation procedure for concrete expansion anchor bolts in seismic piping system at OCNGS.
l This is a Severity Level IV violation (Supplement 1) applicable to License No. DPR-16.
8509120188 850904' 3
PDR ADOCK 05000219 G
PDR 1
0FFICIAL RECORD COPY IR OYC 85 0003.0.0 08/27/85 l
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W Appendix A 2
Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, in-cluding: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.
OFFICIAL RECORD COPY IR OYC 85 0003.1.0 08/27/85