ML040560580
| ML040560580 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/23/2004 |
| From: | Myers L FirstEnergy Nuclear Operating Co |
| To: | Caldwell J NRC/RGN-III |
| References | |
| 1-1345, CAL 3-02-001 | |
| Download: ML040560580 (7) | |
Text
FENOC -
5501 North State Route 2 Oak Harbor, Ohio 43449 L w W. hf)t?cs chief Operating Officer Docket Number 50-346 License Number NPF-3 Serial Number 1-1345 February 23, 2004 419-321-7599 Fax: 419-321-7582 Mr. James L. Caldwell, Administrator United States Nuclear Regulatory Commission, Region III 801 Warrenville Road Lisle, IL 60532-43551
Subject:
Closure of Confirmatory Action Letter Items 4 and 5 and Completion of Confirmatory Action Letter 3-02-001
Dear Mr. Caldwell:
The purpose of this letter is to provide an update and request closure of the remaining open Confirmatory Action Letter (CAL) 3-02-001 Items four (4) and five (5), provide a status for the remaining CAL Items, and request closure of the CAL in its entirety.
As a result of the identification of degradation of the Davis-Besse Nuclear Power Station (DBNPS) Reactor Pressure Vessel (RPV) head in March 2002, the Nuclear Regulatory Commission (NRC) issued FirstEnergy Nuclear Operation Company (FENOC) CAL 3-02-001 on March 13,2002, to document six specific activities FENOC intended to implement to resolve the RPV head degradation issue. As explained below, and in Attachment I, FENOC has completed the actions specified for these open Items and each of the other CAL Items.
Therefore, FENOC respectfully requests the NRC close this CAL.
Confirmatory Action Letter, Item 4 CAL Item 4 states as follows:
Obtain NRC review and approval of the repair or modification and testing plans for the RPV head, prior to implementation of those activities. Prior to restart of the reactor, obtain NRC review and approval of any modification and testing activity related to the reactor core or reactivity control systems.
CAL Item 4 Status:
On December 24,2002, the NRC provided an CAL 3-02-001B Update of the original CAL 3-02-00 1. Confirmatory Action Letter Item 4 was statused to remain open pending successful
Docket Number 50-346 License Number NPF-3 Serial Number 1-1345 Page 3 of 3 with the NRC on February 12,2004, at Camp Perry, Ohio. At this meeting FENOC requested approval for restart of the DBNPS.
Therefore, FENOC respectfully requests that CAL Item 5 be closed.
Confirmatory Action Letter 3-02-00 1 - Comdetion The March 13, 2002 CAL required FENOC to notify the NRC Regional Administrator, when the actions addressed in CAL 3-02-001 are complete. As previously described in this letter, and Attachment I, FENOC has completed the actions specified in each of the CAL Items. also lists the relevant FENOC correspondence for each CAL Item for reference.
Therefore, FENOC respectfully requests closure of CAL 3-02-001.
There are no new regulatory commitments contained in this letter. If there are any questions concerning this matter, please contact Mr. Gregory A. Dunn, Manager - Regulatory Affairs at 41 9-321 -8450.
Sincerely, JCS/s Attachments cc: U S NRC Document Control Desk John A. Grobe, Chairman NRC 0350 Panel DB-1 Senior NRC/NRR Project Manager DB-1 Senior NRC Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 1-1 345, Page 2 of 9 FENOCs Status of Completion of the Restart Confirmatory Action Letter 3-02-001 Serial Letter 3004, dated November 8,2003; Disposition of Reactor Vessel Head Sample Serial Letter 3007, dated November 20,2003; Resubmittal of Final Report on Examination of Serial Letter 301 9, dated February 13,2004; Disposition of Reactor Vessel Head Sample Piece A2B Reactor Vessel Head Degradation Pieces A2A7L. A2AJM, and A2A7N
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1345, Page 4 of 9 FENOCs Status of Completion of the Restart Confirmatory Action Letter 3-02-001 Serial Letter 1-1299, dated January 9,2003; Submittal of Root Cause Evaluations Root Cause Analysis of:
Quality Assurance Oversight; Root Cause Analysis of Operations; Assessment of Company Nuclear Review Board; Root Cause Analysis of Corrective Action Problem Resolution Human Performance and Implementation; Root Cause Analysis of Engineering Assessment Capabilities, and Evaluation of Corporate Management Serial Letter 1-1306, dated March 27,2003; Collective Significance Review of Causal Factors Associated with the RPV Head Degradation and Revision 2 of the Management and Human Performance Improvement Plan Assessment of Engineering Capabilities of the DBNPS and Request for Restart Approval Serial Letter 1 - 13 14, dated May 2,2003; Submittal of Revision 1 of the Root Cause Serial Letter 1-1336, dated November 23,2003; Integrated Restart Report to Support Restart
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1345, Page 6 of 9 FENOCs Status of Completion of the Restart Confirmatory Action Letter 3-02-001 confilm atow Action Letter. Item 4 CAL. Item Description Obtain NRC review and approval of the repair or modification and testing plans for the existing RPV head, prior to implementation of those activities. Prior to restart of the reactor, obtain NRC review and approval of any modification and testing activity related to the reactor core or reactivity control systems. If the reactor vessel head is replaced in lieu of repair or modification, the replacement must comply with appropriate Commission rules and industry requirements.
NRCS status CAL Update 3-02-001B, dated December 24,2002 (Log 1-4325):
CAL Update 3-02-001B stated, this CAL Item remains open pending NRC review of successfbl completion of the reactor coolant system pressure test and control rod drive performance test.
FENOCs Action As discussed in Section IV.B of the Integrated Restart Report, FENOC has replaced the RPV Head, and has performed inspections and tests of the new head. The Mode 3 pressure test completed in September 2003 has verified its acceptability. Also, as described in the body of this letter, the Control Rod insertion time testing was completed as the final action for this CAL Item.
FENOC Submittal References Serial Letter 1-1271, dated April 25,2002; Partial Response to CAL 3-02-001 - Repair Plans Serial Letter 1-128 1, dated August 9,2002, Replacement of the RPV Head at the DBNPS Serial Letter 1 - 1345, (this submittal); Closure of CAL Items 4 and 5 and Completion of for the DBNPS Reactor Pressure Vessel Head CAL 3-02-001
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1345, Page 8 of 9 FENOCs Status of Completion of the Restart Confirmatory Action Letter 3-02-001 Confinnatow Action Letter. Item 6 CAL Item Description Provide a plan and schedule to the NRC, within 15 days of the date of this letter, for completing and submitting to the NRC your ongoing assessment of the safety significance for the Reactor Pressure Vessel (RPV) head degradation.
NRCs Status CAL Update 3-02-001B, dated December 24,2002 (Log 1-4325):
This issue is closed.
CAL Update 3-02-001B stated, FENOCs plan and schedule for completing and submitting the assessment of the safety significance of the RPV head degradation was submitted on March 27,2002. FENOC submitted the Safety Significance Assessment to the NRC on April 8,2002 and responded to requests for additional information.
FENOC provided the DBNPS plan and schedule for Safety Significance Assessment of Reactor Pressure Vessel Head Degradation to the NRC on March 27,2002, via Serial Letter 1-1267. FENOC provided an analysis of the safety significance of the RPV head degradation on April 8,2002 (Serial Letter 1-1268) and provided the final examination report of the RPV Head Degradation, and updated the Safety Significance Assessment on August 13,2003 (Serial Letter 2968).
FENOCs Action FENOC Submittal References Serial Letter 1-1267, dated March 27,2002; Plan and Schedule for Safety Significance Serial Letter 1-1268, dated April 8,2002; Safety Significance Assessment of the DBNPS Serial Letter 1-1277, dated June 12,2002; Response to Request for Additional Information Serial Letter 1-1280, dated July 12,2002; Response to Request for Additional Wormation Assessment of Reactor Pressure Vessel Head Degradation Reactor Pressure Vessel Head Degradation Related to the DBNPS Safety Significance Assessment Related to the DBNPS Safety Significance Assessment
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1345, Page 1 of 1 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 The DBNPS. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8450) of any questions regarding this document or associated regulatory commitments.
COMMITMENTS None DUE DATE NIA