ML030220165
| ML030220165 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  (NPF-003) |
| Issue date: | 01/21/2003 |
| From: | Dyer J NRC/RGN-III |
| To: | Myers L FirstEnergy Nuclear Operating Co |
| References | |
| CAL 3-02-001, CAL 3-02-001B, CAL 3-02-001C | |
| Download: ML030220165 (5) | |
Text
January 21, 2003 CAL No. 3-02-001C Mr. Lew Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
UPDATE OF CONFIRMATORY ACTION LETTER 3-02-001B STATUS FOR DAVIS-BESSE NUCLEAR POWER STATION
Dear Mr. Myers:
On March 13, 2002, the Nuclear Regulatory Commission (NRC) issued Confirmatory Action Letter No. 3-02-001 regarding the reactor pressure vessel head degradation at the Davis-Besse Nuclear Power Station. On May 15, 2002, the NRC revised the Confirmatory Action Letter, to address the option of replacing the reactor pressure vessel head. The Confirmatory Action Letter documented six sets of commitments you intended to take prior to restart of Davis-Besse.
On December 24, 2002, the NRC provided a letter to you, documenting our understanding of the current status of each of the items. The purpose of this letter is to clarify the status of Confirmatory Action letter Issue No. 1 in that December 24, 2002 letter. As discussed between Mr. R. Fast of your staff and Mr. J. Grobe, Chairman of the Davis-Besse Oversight Panel on January 10, 2003, the enclosure to this letter details the status of CAL Issue No. 1, including our understanding of your planned actions regarding the quarantined material from the damaged reactor vessel head. Notify me if your understanding differs from that described in the enclosure.
In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
L. Myers If you have any questions regarding the information in this letter, please contact me at 630-829-9657, or John Grobe at 630-829-9637.
Sincerely,
/RA/
J. E. Dyer Regional Administrator Docket No. 50-346 License No. NPF-3
Enclosure:
Confirmatory Action Letter Issue No. 1 Status cc w/encl:
B. Saunders, President - FENOC Plant Manager Manager - Regulatory Affairs M. OReilly, FirstEnergy Ohio State Liaison Officer R. Owen, Ohio Department of Health Public Utilities Commission of Ohio President, Board of County Commissioners Of Lucas County President, Ottawa County Board of Commissioners D. Lochbaum, Union Of Concerned Scientists DOCUMENT NAME: G:DRP\\Davis-Besse 0350\\ML030220165.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII E RIII RIII E
NRR E
NAME DPasssehl/klg/RA/
CLipa /RA/
BClayton /RA/
WDean /RA by CL via tel-con/
DATE 01/17/03 01/17/03 01/17/03 1/17/03 OFFICE RIII E NRR RIII RES NAME JGrobe /RA/
SCollins /RA by CL via tel-con/
JDyer /RA/
Mayfield /RA by CL via email/
DATE 1/17/03 1/17/03 1/21/03 1/21/03 OFFICIAL RECORD COPY
L. Myers ADAMS Distribution:
AJM DFT SPS1 RidsNrrDipmIipb GEG DMC HBC CST1 C. Ariano (hard copy)
DRPIII DRSIII PLB1 JRK1 DB0350
Enclosure Confirmatory Action Letter Issue No. 1 Status "Quarantine components or other material from the RPV [Reactor Pressure Vessel] head and CRDM [Control Rod Drive Mechanism] nozzle penetrations that are deemed necessary to fully address the root cause of the occurrence of degradation of the leaking penetrations. Prior to implementation, plans for further inspection and data gathering to support determination of the root cause will be provided to the NRC for review and comment."
Status Applicable components and material have been adequately quarantined and plans for inspection and data gathering to support root cause determination have been provided to the NRC for review and comment. Following discussions between Mr. R. Schrauder of your staff and Mr. W. Dean, Vice Chairman of the Davis-Besse Oversight Panel on November 1, 2002, it is our understanding that the following additional specimens will be removed from the damaged reactor vessel head:
- 1) Approximately 8 inches diameter of head material unaffected by heat around CRDM penetration Nozzles 2 and 46,
- 2) Nozzle base material from any two of Nozzles 1, 2, 4, or 5 (heat no. M3935),
- 3) Nozzle base material from Nozzle 47 (heat no. C2649-1), and
- 4) Nozzle base material from any two of Nozzles 7, 12, 16, 20, 22-25, 27-29, 38-44, 48-55, 57, 64, 68, or 69 (heat no. C2649-1).
The nozzle base material will be cut off both at the head and below the bimetallic weld, resulting in pieces about 7 to 8 inches long. The point of contact for the shipments of these specimens to Argonne National Laboratory (ANL) is Mr. William Cullen, Jr., Senior Materials Engineer, Materials Engineering Branch, Office of Research (RES). Mr. Cullen can be reached at 301-415-6754. Following removal of the material described above, and its shipment to ANL, the NRC releases the head from quarantine. With respect to the specimen materials sent to Lynchburg, Virginia, the quarantine will be considered lifted once the Phase 3 test plan for the material has been completed. The specimen material sent to Canada is now considered released from quarantine.