IR 07100012/2011022
| ML20198S182 | |
| Person / Time | |
|---|---|
| Site: | 07100012, Comanche Peak  |
| Issue date: | 01/16/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20198S175 | List: |
| References | |
| 50-445-97-20, 50-446-97-20, NUDOCS 9801260100 | |
| Download: ML20198S182 (2) | |
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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 October 12 through November 22,1997, three violations of NRC requirements were identified. In accordance with the ' General Statement of Pokey and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
10 CFR * art 50, Appendix B, Criterion V, ' Instructions, Procedures, and Drawings,"
requires, in part, that activities affecting quality shall be prescribed by instructions of a type appropriate to the circumstances.
Contrary to the above, Procedure IPO-005B, " Plant Cooldown from Hot Standby to Cold Shutdown," Revision 2, was not appropriate to the circumstances in that the procedure did not require that pressure be maintained below the reactor coolant system pressure and temperature limits specified in Technical Data Manual TDM 3018, 'RCS Temperature & Pressure Limits, " Revision 5. As a consequence, on October 25,199, both power-operated relief valves opened when pressure was allowed to remain above the limit Thic is a Severity Level IV violation (Supplement l} (50-446/9720-01).
B.
Technical Specification e.9.4, " Containment Building Penetrations," states, in part, that, during core alterations, a minimum of one door in the personnel airlock is capable of being closed and that each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be closed.
Contrary to the above, on November 10,1997, during Unit 2 core alterations, the containment airlock pressure equalization valves for both personnel airlock doors were open and were not capable of being closed. This provided direct access from the containment atmosphere to the outside atmospheie.
This is a Severity Level IV violation (Supplement I) (50-446/9720-02).
C, 10 CFR Part 50, Appendix B, Criterion XVI, " Corrective Actions," requires, in part, that conditions adverse to quality, such as nonconformances, be promptly identified and corrected.
On November 4,1994, the licensee identified structural gaps in both Unit 2 emergency core cooling sumps that exceeded the Final Safety Analysis Report description of 0.115 inches. On November 12,1994, the licensee completed 9901260100 980116 PDR ADOCK 05000445
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Work Orders 194-078046 00 and 1-94-078047-00, which were issued to identify and repair any gap larger than 0.115 inches.
Contrary to the above,16 gaps which were conditions advarse to quality were not promptly identified and corrected in that eight gaps previously identified in 1994 and eight additional gaps that exceeded the Final Safety Analysis Report specification of 0.115 inches were identified in the Unit 2 emergency core cooling sumps on November 8,1997.
This is a Severity Level IV violation (Supplement 1) (50-446/9720-04).
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 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. 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 Informatiori 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 (POR), to the extent
. possible, it should not include any personal privacy, proprietary, or safeguards information so that it cari 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 4-information from the public.
Dated at Arlington, Texas this 16th day of Januarp 1998
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