ML16148A601
| ML16148A601 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/14/1992 |
| From: | Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A602 | List: |
| References | |
| 50-287-91-34, NUDOCS 9202140229 | |
| Download: ML16148A601 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket No. 50-287 Oconee Unit 3 License No. DPR-55 During an NRC inspection conducted on November 23 -
December 21,
- 1991, two violations of NRC requirements were identified.
In accordance with the "General. Statement of Policy and Procedure for NRC Enforcement Actions,0 10 CFR Part 2, Appendix C (1991),
the violations are listed below:
A. Technical Specification 6.4.1 requires that the station be operated and' maintained in accordance with approved procedures.
Operations Management Procedure 1-9, Use.of Pr:cedures, Section 6.3 requires that no deviation from the original intent of the procedure-shall be allowed without an approved procedure change.
Unit Shutdown Procedure OP/3/A/1102/10 Enclosure 4.2, Step 2.3, requires the operator to place the Turbine Bypass Valves (TBV) in Manual to control secondary pressure during cooldown.
Contrary to the above, on November 23, 1991, the station was not operated in accordance with approved procedures in that the operator chose to leave the TBV in Automatic in lieu of Manual and controlled secondary pressure by lowering the demand setpoint.
This contributed to an inadvertent Reactor Protection System actuation.
This is a Severity Level IV Violation (Supplement I).
B.
10 CFR 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, and the licensee's accepted Quality Assurance (QA)
Program (Duke-i-A, Section 17.2.5) require, in part, that for activities affecting quality, instructions, procedures and drawings shall include appropriate quanti tative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
10 CFR 50, Appendix B, Criterion X, Inspections, and the licensee's accepted QA Program (Duke-i-A, Section 17.2.10) require, in part, that if inspection of processed material or products is impossible or dis advantageous, indirect control by monitoring processing methods, equipment, and personnel shall be provided.
Both inspection and process monitoring shall be provided when control is inadequate without both.
Licensee Procedure QAE 2, Instrumentation Installation, Modifications and Maintenance Inspections, Section 5.7.C requires that for QA-1 and QA-3, verify that all fittings are tight.
9202140229 920114 PDR ADOCK 05000269 0
Duke Power Company 2
Docket No. 50-287 Oconee Unit 3 License No. DPR-55 Contrary to the above, the installation procedure for the Reactor Vessel Level Indication System (RVLIS) Instrumentation, TN/3/A/32401/AKI, did not contain manufacturers requirements, recommendations and precautions for the installation of compression fittings.
The installation procedure contained sign-off steps for the installer, independent verifier, and the quality assurance inspector but no instructions or requirements were specified pertaining to installation and inspection of the compression fittings.
Additionally, QAE 2 did not contain adequate acceptance criteria to control the fabrication of the fitting that failed.
This resulted in the failure of the fitting connection and the release of approximately 87,000 gallons of reactor coolant water into the reactor building.
This is,a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region II, a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if.contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION Alan R. Herdt, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this 14th day of Jan.
1992