05000346/LER-2004-001, Regarding Violation of Steam and Feedwater Rupture Control System Technical Specification
| ML040650526 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/03/2004 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NP-33-04-001-00 LER 04-001-00 | |
| Download: ML040650526 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3462004001R00 - NRC Website | |
text
fENOC' 1O 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bazilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 NP-33-04-001-00 Docket No. 50-346 License No. NPF-3 March 3, 2004 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Ladies and Gentlemen:
LER 2004-001 Davis-Besse Nuclear Power Station, Unit No. 1 Date of Occurrence - January 6. 2004 Enclosed please find Licensee Event Report (LER) 2004-001, which is being submitted to provide written notification in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Technical Specifications. On January 6, 2004, it wvas identified that a Technical Specification Action was missed which required the trip of a Steam and Feedwvater Rupture Control System channel within one hour. Commitments associated with this LER are listed in the Attachment.
Very truly yours, AWB/s Attachment Enclosure cc:
Regional Administrator, USNRC Region III DB-1 NRC Senior Resident Inspector DB-1 NRC/NRR Senior Project Manager Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 NP-33-04-001-00 Attachment Page 1 of 2 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory
commitments
Please notify the Manager - Regulatory Affairs (419-321-8450) at Davis-Besse of any questions regarding this document or associated regulatory commitments.
COMMITMENTS
DUE DATE Standing Order 004-02 was issued by Operations on Complete January 13, 2004, which documented that the pre-job brief for the missed TS Action Statement did not meet expectations.
Communication was provided to Davis-Besse Personnel Complete which documented Operations role as station leadership due to their licensed responsibilities, and the senior management expectation for station personnel providing timely support to Operations for effective fulfillment of that critical role. Also included in this communication was a depiction of the operations shift organization, an explanation of the roles and responsibilities for each shift member, and a memorandum describing the Shift Manager's command responsibilities.
A lesson plan designed for Just-in-Time Training for Complete licensed operators was developed to ensure a consistent understanding of the root cause findings and corrective actions. The Operations Manager presented the lessons learned to the target population of licensed shift personnel in an interactive training session.
Operations Directive, "Conduct of Pre-Job Briefs and Complete Post-Job Reviews," has been revised to include provisions to allow the use of other checklists developed for specialized activities in addition to the existing Pre-Job Checklist form.
Docket Number 50-346 License Number NPF-3 NP-33-04-001-00 Attachment Page 2 of 2
COMMITMENTS
DUE DATE Procedure DB-OP-00100, "Shift Turnover," Attachment 1 - General Turnover Guidelines, was revised to provide guidance for review of any license requirements currently in effect to include TS, Fire Hazard Analysis Report, Off-Site Dose Calculation Manual, and Technical Requirements Manual. Also, shift turnover sheets were revised for the Shift Manager, Shift Engineer, Unit/Field Supervisor, and Reactor Operator to include review of license requirements in effect and sign-offs for the Shift Manager, Unit/Field Supervisor, and Reactor Operator indicating that responsibility for license requirements has been transferred.
The Director of Plant Operations has assessed the effectiveness of the Operations Leadership in place during the event. In accordance with the FENOC personnel policies, a new Operations Manager and Operations Superintendent, both with prior operations experience, have been appointed to strengthen Plant Operations.
A "crew update" concept towards normal plant operations will be applied as a means to keep the crew informed of changes in plant status. A consistent format will be applied to improve the formality of this communication tool.
DB-OP-00000, "Conduct of Operations," will be revised to align with FENOC wide Operations.
Complete Complete April 2, 2004 July 30, 2004
Abstract
approximately 15 single-spaced typewritten lines)
On January 6, 2004, with the plant in Mode 3, at approximately 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> the Operations shift became aware that a Technical Specification (TS) Action was missed.
Feedwater/Steam Generator 2 Differential Pressure High Instrument Actuation Channel 2, PDS-2685B, was removed from service for a channel functional test and calibration.
TS 3.3.2.2 Action 16 was entered at 1621, January 6, 2004, which required that PDS-2685B be returned to operable status, or the channel be placed in a tripped condition within one hour.
Due to less than adequate work practices and managerial methods, it was not identified until the channel was returned to service approximately two-and-a-half hours later that actions to place the required channel in the tripped position did not occur within the one hour action statement. Actions are being addressed through continual involvement of Station management's monitoring, coaching, feedback, and correction.
This event is being reported as an operation or condition prohibited by the Technical Specifications in accordance with 10 CFR 50.73 (a) (2) (i) (B).
NRC FORM 366 (7-2001)
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FAILURE DATA (continued):
From each of these events, human performance tools were not used or were used improperly. Additionally, reinforcement of desired behaviors and correction of behaviors that deviate from station standards and procedure requirements were not always corrected.
Corrective Actions listed above include actions taken to ensure a consistent understanding of the root cause findings and corrective action for licensed operators.
This was presented in an interactive training session where the adverse consequences that accompanied the failures was stressed.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
NP-33-04-ool-0O CR 2004-00181