ML18095A576
| ML18095A576 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/01/1990 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18095A575 | List: |
| References | |
| 50-272-90-22, 50-311-90-22, NUDOCS 9011130383 | |
| Download: ML18095A576 (1) | |
Text
APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating Station Units 1 & 2 Docket Nos.
50-272 50-311 License Nos.
DPR-70 DPR-75 As a result of the inspection conducted on August 16, 1990 - October 1, 1990, and in accordance with 11General Statement of Policy and Procedure for NRC Enforcement Actions 11, 10CFR2, Appendix C (Enforcement Policy 1990), the following violation was identified.
10CFR Part 50.59 permits the licensee to make changes to the facility and to procedures without prior NRC approval provided that the change does not involve an unreviewed safety question (USQ).
A written safety evaluation which provides the bases for the determination that a USQ is not involved must be completed and maintained.
Salem Technical Specification (TS) 6.5.3.2.a requires that Station Qualified Reviewers (SQR) maintain independence when performing procedure reviews.
TS 6.5.1.6.a requires that procedure changes involving significant safety issues (SS!) be reviewed by the Station Operations Review Committee (SORC) and not through the SQR process.
- 1.
Contrary to the above, on February 8, 1990, the number 22 boric acid transfer pump was returned to service with a modified pump performance curve after maintenance, and no safety evaluation existed documenting why no USQ was involved with this change.
- 2.
Contrary to the above, as of May 25, 1990, independent SQR technical review had not been maintained in all instances, including a January 9, 1990 change to procedure SP(0)4.0.5-P-RH-12, 11 Inser:vice Testing - Residual Heat Removal.
11
- 3.
Contrary to the above, as of May 25, 1990, a Belzona 11 R 11 metal non-ASME code repair of the number 23 containment fan cooling unit was performed, and no safety evaluation existed documenting why no USQ was involved with this change.
- 4.
Contrary to the above as of May 25, 1990, procedure changes with SSis were reviewed and approved by the SQR and not by the SORC, including the revised procedure OP-ST.SJ-0013(Q) on May 20, 1990.
This is a Severity Level IV violation (Supplement I).
No response to this Salem violation is required as these issues were previously identified in NRC Inspection No. 50-272/90-81; 50-311/90-81, and the licensee 1 s response to these issues and associated corrective actions were found to be acceptable.
OFFICIAL RECORD COPY CIR SAL/HC 90-22/16 - 0005.0.0 11/29/80