ML20211L305
| ML20211L305 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/26/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20211L256 | List: |
| References | |
| 50-413-97-11, 50-414-97-11, NUDOCS 9710100158 | |
| Download: ML20211L305 (2) | |
Text
4 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50 413,50-414 Catawba Nuclear Station License Nos. NPF 35 NPF 52 During an NRC inspection conducted from July 20, 1997 - August 30, 1997, two 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.
Technical Specification 6,8.1 requires that written procedures be established, implemented, and maintained cove"ing the activities recommended in Appendix A of Re9J1atory Guide (RG) 1,33. Revision 2.
As referenced, this includes procedures for maintenance that can affect the performance of safety related equipment.
Procedure IP/0/A/4830/003, Calibration Checkout, and Replacement of Optical Isolators Revision 11, Prerequisite 4.1, requires that drawings, details, manuals, procedures, and other reference material as necessary be reviewed before optical isolator replacement activities are performed.
Contrary to the above, on July 27, 1997, 3 technician failed to correctly review Drawing Number CNEE-2792-01.02, Connection Diagram.
Main Steam System Terminal Cabinet 2SMTC1, Pevision 12, and developed an incorrect isolatior alan for replacing a failed digital optical isolator associated with the Jnit 20 Steam Generator (SG) Main Steam Isolation Valve. When the flawed plan was executed, the 2A, 28 and 2C MSIVs failed closed, pressure increased in the affected SGs, and control room operators had to manually cycle SG power operated relief valves to relieve pressure.
This is a Severity Level IV Violation (Supplement I),
B.
10 CFR 50, Appendix B, Criterion XVI, Corrective Action, as implemented by the Duke Power Company Topical Quality Assurance Program (Duke 1-A)
Amendment 20, requires, in part, measures shall be established to assure that conditions adverse to quality, such as deficiLicies, deviations, and nonconformances are promptly identified and corrected, Contrary to the above, as of May 20, 1997, measures established and completed for Generic Letter 96-01 reviews to ensure that all Jortions of the logic circuitry, including the parallel logic, interloccs, bypasses and inhibit circuits, were adequately covered in the surveillance procedures to fulfill the Technical Specifications (TS) requirements did not identify and initiate corrective actions for all conditions adverse to quality, Specifically, it did not identify and initiate corrective actions for deficiencies in the quarterly operational testing of the Unit I and 2 pressurizar pressure P-11 interlock as required by TS until August 4,1997, and did not identify 9710100158 970926 PDR ADOCK 05000413 G
Notice of V1olation 2
and initiate corrective actions for Unit 2 refueling calibration testing of the turbine impulse chamber pressure P-13 interlock until August 13.
1997.
This is a Severity Level IV Violatior (Supplement I).
Pursuant to the provisions of 10 CFR 2.201. Duke Energy Corporation 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, and a copy to the NRC Resident Inspector at the Catawba Nucitar Station, 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 n
time specified in this Notice, an order or demand for information may be U
issued so as to why the license should not be modified, suspended, or revcked, or why such other action as nay be proper should not be taken. Where good cause is shown, consideration will 3e given to extending the response time.
Because your res)onse will be placed in the NRC Public Document Room (PDR) to the extent possi)le. it should not include any personal privacy 3roprietary, or safeguards information so that it can be placed in the PDR wit 1out 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 Atlanta. Georgia this 26th day of September 1997 l
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