ML17333A769
| ML17333A769 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/04/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17333A766 | List: |
| References | |
| 50-315-96-13, 50-316-96-13, NUDOCS 9702100188 | |
| Download: ML17333A769 (4) | |
Text
NOTICE OF VIOLATION American Electric Power Company D. C. Cook Nuclear Generating Plant Units 1 and 2 Docket Nos. 50-315, 50-316 License Nos. DPR-58, DPR-74 During an NRC inspection conducted on November 18 through December 13, 1996, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings,"
requires, in part, that activities affecting quality shall be prescribed by instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Maintenance procedure 12MPH5021.001.009, Revision 8, "Torque Selection,"
dated March 21, 1994, requires thread engagement of at lea".
~0 percent of nut
- height, Contrary to the above:
1.
On December 4, 1996, the inspectors identified that a maintenance work package for the 1E centrifugal charging pump, an activity affecting quality, failed to include adequate instructions for lube oil sample collection.
On November 20, 1996, the inspectors identified that maintenance procedure MDS-600, "General Erection Tolerances for Pipe and Tube Supports/Restraints,"
was not of a type appropriate to the circumstances since it failed to contain adequate minimum thread engagement acceptance criteria for activities affecting quality.
On November 21, 1996, the inspectors identified that maintenance personnel failed to perform bolting on safety-related equipment in accordance with maintenance procedure 12MHP5021.001.009, "Torque Selection."
As a result, nuts associated with emergency core cooling system equipment were identified with thread engagement less than 80 percent of nut height.
This is a Severity Level IV violation (Supplement I) (50-315/96013-01(DRS);
50-31 6/9601 3-01 (DRS)).
10 CFR 50, Appendix B, Criterion XI, "Test Control," requires, in part, that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.
9702iOOi88 970204 PDR ADQCK 050003iS 6
Notice of Violation Technical Specification 3.1.1.1, "Shutdown Margin - Tave Greater Than 200 'F,"
specifies a boration capability of 10 gallons per minute of 20,000 parts per million boron solution or equivalent.
Contrary to the above, on December 11, 1996, the inspectors identified that the correct acceptance limits to assure that the centrifugal charging pumps could perform their boron injection function as specified in Technical Specification 3.1.1.1 had not been incorporated in the licensee's inservice testing (IST) program.
This is a Severity Level IV violation (Supplement I) (50-315/96013-02(DRS);
50-31 6/9601 3-02(DRS)).
C.
10 CFR 50, Appendix B, Criterion XVI, "Corrective Actions," requires, in part, that measures shall be established to assure that conditions adverse to quality, such as r~ilures, malfunctions, deficiencies, deviations, defective material and equipment,
<i'd gonconformances are promptly identified and corrected.
Contrary to the above:
Corrective actions to address potentially inaccurate sight-glass fillmarks for safety-related pumps and motors, a condition adverse to quality, were not initiated until November 27, 1996, although in 1995 job orders were written to address potentially inaccurate sight-glass fillmarks on safety-related pumps and motors, and on March 6, 1996, an action request was written to determine correct sight-glass fillmarks on safety-related pumps and motors.
2.
On December 5, 1996, the inspectors identified that the licensee failed to take corrective actions to either locate or re-constitute a centrifugal charging pump net positive suction head (NPSH) calculation although the calculation had been identified as missing about 18 months earlier.
3.
On December 4, 1996. the inspectors determined that the licensee failed to take timely corrective actions to address equipment deficiency tagging problems.
Although the licensee had identified that about 30 percent of plant components in the work control system reviewed in a three week period were not properly tagged in the field, corrective actions to address this concern had not been initiated.
This is a Severity Level IV violation (Supplement I) 50-315/96013-03(DRS);
50-31 6/96013-03(DRS)).
Pursuant to the provisions of 10 CFR 2.201, American Electric Power Company is hereby required to submit a written statement of explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region III, and a copy to the NRC Resident Inspector at the D. C.
Cook facility, within 30 days of the date of the letter transmitting this Notice of Violation
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):he 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.
Your response may reference or include previous dockete'd correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to 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.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Lisle, Illinois, this 4th day of February 1997