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Category:NRC Preliminary Notification of Event/Occurrence
MONTHYEARPNO-III-18-002, Beaver Valley, Davis-Besse, Perry Notification of Bankruptcy Filing by Firstenergy Solutions2018-04-0404 April 2018
PNO-III-18-002: Beaver Valley, Davis-Besse, Perry Notification of Bankruptcy Filing by Firstenergy Solutions
PNO-III-16-004, A - Unplanned Shutdown of Davis-Besse Nuclear Power Station for Greater than 72 Hours - Update2016-09-23023 September 2016
PNO-III-16-004A - Unplanned Shutdown of Davis-Besse Nuclear Power Station for Greater than 72 Hours - Update
ML16257A2032016-09-13013 September 2016
PNO-III-16-004, Davis-Besse Nuclear Power Station, Unplanned Shutdown for Greater than 72 Hours
PNO-III-15-006, Davis-Besse Shutdown Due to Secondary Side Steam Line Rupture2015-05-13013 May 2015
PNO-III-15-006: Davis-Besse Shutdown Due to Secondary Side Steam Line Rupture
PNO-III-14-003, A - Update to Davis-Besse Shield Building Restoration2014-04-28028 April 2014
PNO-III-14-003A - Update to Davis-Besse Shield Building Restoration
ML14050A0262014-02-19019 February 2014
PNO-III-14-003: Davis-Besse Shield Building Voids
PNO-III-13-007, Davis-Besse Shield Building Laminar Cracks2013-09-20020 September 2013
PNO-III-13-007 Davis-Besse Shield Building Laminar Cracks
PNO-III-13-006, A: Davis Besse Preliminary Notification Update Unplanned Shutdown Greater than 72 Hours on June 29, 2013, Due to Trip of Reactor Coolant Pump and Subsequent Discovery of Reactor Pressure Boundary Leakage2013-07-15015 July 2013
PNO-III-13-006A: Davis Besse Preliminary Notification Update Unplanned Shutdown Greater than 72 Hours on June 29, 2013, Due to Trip of Reactor Coolant Pump and Subsequent Discovery of Reactor Pressure Boundary Leakage
ML13184A1762013-07-0202 July 2013
PNO-III-13-006 - Davis Besse Unplanned Shutdown Greater than 72 Hours on June 26, 2013, Due to Trip of Reactor Coolant Pump and Subsequent Discovery of Reactor Pressure Boundary Leakage
PNO-III-11-014, Davis-Besse Shield Building Indications2011-10-20020 October 2011
PNO-III-11-014, Davis-Besse Shield Building Indications
PNO-III-10-011, DAVIS-BESSE Start-Up of Following Repairs of Control Rod Drive Mechanism Nozzle Flaw Indications2010-06-29029 June 2010
PNO-III-10-011 - DAVIS-BESSE Start-Up of Following Repairs of Control Rod Drive Mechanism Nozzle Flaw Indications
PNO-III-10-008, Davis-Besse, Public Availability of Two NRC Employee Differing Professional Opinions Concerning Past Issues at Davis-Besse2010-05-20020 May 2010
PNO-III-10-008: Davis-Besse, Public Availability of Two NRC Employee Differing Professional Opinions Concerning Past Issues at Davis-Besse
PNO-III-10-003, A - Davis-Besse Nuclear Power Station - Update - Davis-Besse Control Rod Drive Mechanism Nozzle Indications2010-04-12012 April 2010
PNO-III-10-003A - Davis-Besse Nuclear Power Station - Update - Davis-Besse Control Rod Drive Mechanism Nozzle Indications
ML1007503172010-03-16016 March 2010
PNO-III-10-003 - Davis-Besse Nuclear Power Station - Davis-Besse Control Rod Drive Mechanism Nozzle Indications
PNO-III-09-005, A: Davis-Besse, Transitory Alert Due to Electric Device Failure (Update)2009-06-29029 June 2009
PNO-III-09-005A: Davis-Besse, Transitory Alert Due to Electric Device Failure (Update)
ML0917706352009-06-26026 June 2009
PNO-III-09-005: Davis-Besse, Transitory Alert Due to Electric Device Failure
PNO-III-06-002, Security Event at Davis-Besse2006-01-23023 January 2006
PNO-III-06-002-Security Event at Davis-Besse
PNO-III-04-008, Davis Besse Issued 08/04/2004 Re Automatic Reactor Shutdown2004-08-0404 August 2004
PNO-III-04-008: Davis Besse Issued 08/04/2004 Re Automatic Reactor Shutdown
PNO-III-04-003, Shutdown of the Davis-Besse Nuclear Power Station Plant for Greater than 72 Hours2004-03-17017 March 2004
PNO-III-04-003: Shutdown of the Davis-Besse Nuclear Power Station Plant for Greater than 72 Hours
PNO-III-03-010, Davis Besse: Fuel Loading2003-02-21021 February 2003
PNO-III-03-010, Davis Besse: Fuel Loading
PNO-III-02-036, Crack Identified in Vessel Head Stainless Steel Liner2002-09-10010 September 2002
PNO-III-02-036: Crack Identified in Vessel Head Stainless Steel Liner
ML0308703762002-09-10010 September 2002
Preliminary Notification of Event or Unusual Occurrence -- PNO-III-02-036
PNO-III-02-016, A; Discrete Radioactive Particles Found Outside the Radiologically Restricted Area, Davis-Besse Update2002-04-24024 April 2002
PNO-III-02-016A; Discrete Radioactive Particles Found Outside the Radiologically Restricted Area, Davis-Besse Update
PNO-III-02-006, B, Davis Besse - Reactor Vessel Head Degradation (Second Update)2002-04-0505 April 2002
PNO-III-02-006B, Davis Besse - Reactor Vessel Head Degradation (Second Update)
ML0235800962002-03-11011 March 2002
E-mail from PN1 to Events, Front, PN1, PN302006, Davis-Besse - Update - Significant Metal Loss Observed in Reactor Vessel Head
2018-04-04
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September 10, 2002 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-III-02-036 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region III staff on this date.
Facility Licensee Emergency Classification Davis-Besse Notification of Unusual Event FirstEnergy Nuclear Operating Co. Alert Oak Harbor OH Site Area Emergency Docket: 050-00346 General Emergency x Not Applicable
SUBJECT:
CRACK IDENTIFIED IN VESSEL HEAD STAINLESS STEEL LINER DESCRIPTION:
On September 9, 2002, the licensee informed Region III (Chicago) that the metallurgical laboratory performing analysis of the damaged portion of the reactor vessel head had identified a crack in the surface of the stainless steel liner of the head.
After the reactor was shut down February 16, 2002, the licensee found a cavity in the reactor vessel head where the carbon steel head material was corroded. The resulting cavity was about 4 inches by 5 inches and approximately 6 inches deep, leaving only the stainless steel liner intact.
A 17-inch diameter portion of the reactor vessel head, including the cavity, was cut from the head for further analysis.
The licensee informed Region III that the laboratory analysis had identified a crack about 3/8 inch long in the surface of the liner. The crack was found in the outside surface of the stainless steel liner where it originally met the carbon steel of the head, near the center of the cavity.
The depth of the crack is not known, but there are no indications that it is through the wall of the liner. The laboratory is performing further characterization of the crack.
The laboratory also determined that the average thickness of the liner in the sample was 0.256 inches, ranging from a minimum of 0.202 inches to a maximum of 0.314 inches. The minimum dimension is less than previously known.
The new information concerning the crack and the liner thickness will be considered in the NRCs ongoing review of the safety significance of the reactor vessel head damage.
The State of Ohio will be informed. The information in this preliminary notification has been reviewed with licensee management.
There has been news media interest in the metallurgical findings.
The licensee has submitted photographs of this area of the cladding, which are available on the NRCs web site at http://www.nrc.gov/reactors/operating/ops-experience/vessel-head-degradation/news.html, under the images link.
This information is current as of 1 p.m. CDT on September 10, 2002.
CONTACTS:
Christine Lipa John Grobe 630/829-9619 630/829-9637
