ML17146A367
| ML17146A367 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/02/1986 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17146A366 | List: |
| References | |
| 50-387-86-05, 50-387-86-5, NUDOCS 8605090166 | |
| Download: ML17146A367 (2) | |
Text
e APPENDIX A NOTICE OF VIOLATION Pennsylvania Power and Light Company Susquehanna Steam Electric-Station, Unit 1
Docket No. 50-387 License No.
NPF-14 As a result of the inspection conducted on March 10-14,
- 1986, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violations were identified:
A, 10 CFR 50.55 a (g) requires that components which are classified as ASME Code Class 1, Class 2 and Class 3 shall meet the requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code.
B.
The ASME Boiler and Pressure Vessel
- Code,Section XI, 1980 Edition through Winter 1980 Addenda, in the Foreward and in Article IWA 1400, and IWB and C 2200, requires the nuclear plant owner to develop a program which will demonstrate conformance to the requirements of Section XI.
The Susquehanna, Unit 1 Inservice Inspection
( ISI) Program, document ISI-T-107.0 Revision 5, states that the program complies with the require-ments set forth in the Code of Federal Regulations, Title 10, Part 50, and Section XI of the ASME Boiler and Pressure Vessel
- Code, 1980 Edition through the Winter 1980 Addenda.
Contrary to the above as of March 14, 1986, approximately 49 ASME Class 1
and Class 2 longitudinal seam welds in the Residual Heat Removal
- System, the Reactor Recirculation System and the Core Spray System, which are required by Section XI, 1980 Edition through Winter 1980 Addenda to be included in the ISI program, were not included in this programs and con-sequently were not scheduled to receive the examinations required by ASME Section XI.
Similarly, it was noted that these same welds had not been included in, and scheduled for examination during the Preservice Inspec-tion (PSI) program, as was required by the Edition of the ASME Code gover-ning PSI activities.
This is a Severity Level IV Violation.
(Supplement I).
10 CFR 50 Appendix B, Criterion V requires that activities affecting quality be prescribed by documented instructions and be accomplished in accordance with these instructions.
Nuclear Department Instruction, NDI-gA-8.1.1, states that for follow-up of audit findings, the responsible organization shall
- respond, as re-quested by the audit report, stating the results of review and investi-gation.
The response shall clearly state the corrective action taken or planned.
8605090166 860502
, PDR ADOCK 05000387 8
PDR OFFICIAL RECORD COPY IR SUS 86-05 0003.0.0 05/01/86
Appendix A SSES Audit 85-88, dated December 16, 1986, of ISI activities, requested a
written response to audit finding 85-88-01 from the Nuclear Support Group within thirty days of receipt of the audit report.
Contrary to the above, as of Harch 14,
- 1986, the Nuclear Support Group had not yet responded to NgA audit finding, 85-88-0l,.within the time period specified in the audit report.
This is a Severity Level V Violation.
(Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Pennsylvania Power and Light Company 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, including: (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 SUS 86-05 0004.0.0 05/01/86