ML17286A599
| ML17286A599 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/12/1991 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286A598 | List: |
| References | |
| 50-397-90-31, NUDOCS 9103010037 | |
| Download: ML17286A599 (4) | |
Text
PPENDIX A OTICE OF VIOLATION Washington Public Power Supply System Docket No. 50-397 WNP-2 License No. NPF-21
- Richland, Washington During an NRC inspection conducted on December 3, 1990 - January 13,
- 1991, violations of NRC requirements were identified.
In. accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1990), the violations are listed below:
A.
Criterion XVI of 10 CFR 50, Appendix B, states that "Heasures shall be established to assure that conditions adverse to quality,=- such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
In the case of significant'conditions adverse to quality, the measures shall assure that the cause of the condition is determined and correc-tive action taken to preclude repetition."
Criterion V of 10 CFR 50, Appendix B, further states that "Instructions, procedures, or drawings shall include appropriate quantitative or quali-tative acceptance criteria for determining that important activities have been satisfactorily accomplished."
I Contrary to the above, as of December ll, 1990, sufficient orrective measures had not been implemented in response to the diesel generator bearing failure (a significant condition adverse to quality which occurred on Nay 27, 1990.
Specifically, although bearing ojl leaka e
g was again observed, criteria for verifying acceptable generator bearing oil level had not been established, and an effective program for the monitoring of bearing oil leakage and oil additions had not been implemented.
This is a Severity Level IY violation (Supplement I).
This is a Severity Level IV violation (Supplement I).
B.
Section 4.4. 1.2. 1 of the WNP-2 Technical Specifications states in part:
"Each of the... required jet pumps shall be demonstrated OPERABLE...
by determining recirculation loop flow, total core flow and diffuser-to-lower plenum differential pressure for each jet pump...when both recir-culation loops are operating at the same flow control valve position."
Contrary to the above, on January 9,
1991, recirculation loop flow, total core flow, and diffuser-to-lower plenum differential pressure were not determined with both recirculation loops operating at the same flow control valve position, in that flow control valve "A" was 88.8% open and flow control valve "B" was 84.6/ open.
0 910301 0037 9i0212 PDR ABQCf< 05000397 G
II h
I Pursuant to the provisions of 10 CFR 2.201, Washington Public Po'wer Supply System is hereby required to submit a written statement or explanation to the U.
S. Nuclear Regulatory Commission, ATTN:
Document Control Desk,
'ashington, D.C. 20555, with a -copy to the Regional Administrator, Region V, and a copy to the NRC Senior 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 withi~ 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 Dated at Walnut Creek, California this ~th day of February, 1991 R.
P.
immerman, Director Division of Reactor Safety and Projects
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