ML20217F605
| ML20217F605 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/24/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20217F577 | List: |
| References | |
| 50-445-98-02, 50-445-98-2, 50-446-98-02, 50-446-98-2, NUDOCS 9804280200 | |
| Download: ML20217F605 (3) | |
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i ENCLOSURE 1 NOTICE OF VIOLATION TU Electric Docket Nos.: 50-445 Comanche Peak Steam Electric Station 50-446 License Nos.: NPF-87 NPF-89 During an NRC inspection conducted on February 15 through March 28,1998, four violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," Criterion V, " Instructions, Procedures, and Drawings," states
" activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Contrary to the above, on March 21, Station Administrative Procedure (STA) 617, "High Voltage Switching and Clearance," Revision 4, STA 617 did not prescribe adequate instructions for the control of switching activities while in Mode 2 to preclude actuation of safety systems.
This is a Severity Level IV violation (Supplement l} (50-445/9802-02).
B.
Technical Srsecification 6.8.1 states, in part, that written procedures be established, implemen'.ed, and maintained as recommended by Appendix A of Regulatory Guide 1 J3, Revision 2. Regulatory Guide 1.33, Revision 2, Section 9, specifies that i
procedures be developed for planning and performing maintenance that can affect the performance of safety-related equipment.
Contrary to the above, on February 17, during new fuel receipt and inspection, tension applied to a fuel assembly prior to loosening the top and bottom clamping frames exceeded the 100 to 500 pounds specified in Procedure RFO-201, " Receipt, inspection, and Storage of New Fuel and Insert Core Components," by approximately 800 pounds.
This is a Severity Level IV violation (Supplement 1) (50-445/9802-05).
C.
10 CFR Part 50, Appendix B, Criterion XVI," Corrective Action," states that measures be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are l
promptly identified and corrected.
Contrary to the above, corrective actions were not sufficient to identify that excessive leakage in the emergency core cooling system check valves during Unit 1 Cycle 6 required the Unit 1 safety injection pumps to be started 30 times per month, which was 15 times greater than that assumed in the equipment qualification data package for the l
9804280200 980424 DR ADOCK 05000445 PDR
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. Westinghouse " Lifeline D* motors. As a result of the failure to identify this condition, the licensee could not determine if the safety injection pump motors had exceeded their qualified lives.
This is a Severity Level IV violation (Supplement 1) (50-445(446)/9802-06).
D.
Technical Specification 6.12.2 states, in part, that areas accessible to individuals with radiation levels greater than 1000 mrem /hr at 30 centimeters (12 inches) but less than 500 rads in one hour at one meter from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry.
Contrary to the above, between March 3 and March 6, the locks on both the Unit 1 and Unit 2 containment hatches were removed. Throughout the period, the Unit 1 and Unit 2 containment buildings contained areas that met or exceeded the radiation levels specified in Technical Specification 6.12.2 for locked doors.
j This is a Severity Level IV violation (Supplement IV) (50-445(446)/9802-07).
l Pursuant to the provisions of 10 CFR 2.201, TU Electric 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 IV,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, 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 violations A, B, and C: (1) the reason for the violation, or, if contested, the basis for disputing the violation or severity level, (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 docketed 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. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial
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3-information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Arlington, Texas this 24 day of April 1998 i