Event Notification Report for November 25, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/22/2002 - 11/25/2002
** EVENT NUMBERS **
38513 39387 39388 39389 39391 39392 39393 39394 39395 39396 39397 39399
39400 39401 39402
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38513 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/23/2001|
| UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 12:30[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/23/2001|
+------------------------------------------------+EVENT TIME: 12:10[EST]|
| NRC NOTIFIED BY: CHARLIE PIKE |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA STATE INVOLVING RECOVERED SEA TURTLE FROM |
| UNIT 1 INTAKE STRUCTURE |
| |
| "A sea turtle with no external injuries but appearing to be distressed was |
| recovered from the Unit 1 Intake Structure. The State Stranding Coordinator |
| for sea turtles has been contacted." |
| |
| * * * UPDATE 11/23/01 AT 1255EST FROM CHARLIE PIKE TO S. SANDIN * * * |
| |
| "Turtle has died." |
| |
| The licensee informed both the State of Florida and the NRC Resident |
| Inspector. |
| |
| * * * UPDATE 1413EST ON 12/3/01 FROM JACK BREEN TO FANGIE JONES * * * |
| |
| At approximately 1215 EST on 12/3/01, a report was made to the Florida |
| Department of Fish and Wildlife concerning the recovery of an injured sea |
| turtle from the plant's intake canal. The turtle was a green sea turtle in |
| the intake canal that appeared distressed and looked to have a wound from a |
| boat motor on its back. It will be transferred to the State for |
| rehabilitation. |
| |
| The licensee plans to notify the NRC resident inspector. Notified |
| R2DO(MacAlpine). |
| |
| * * * UPDATE 1333EST ON 12/15/01 FROM JACK BREEN TO JOHN MACKINNON * * * |
| |
| At approximately 1215 EST on 12/15/01, a report was made to the Florida |
| Department of Fish and Wildlife Conservation Commission to pick up a Green |
| Turtle for rehabilitation. The Green Turtle was taken from the plant's |
| intake canal, and the turtle appears to have shark bites. |
| |
| The licensee plans to notify the NRC resident inspector. Notified R2DO |
| (Chuck Ogle). |
| |
| * * * UPDATE 1450EST ON 01/06/02 FROM TULLIDGE TO JOHN MACKINNON * * * |
| |
| At 1350EST, a notification to the State of Florida Department of Fish and |
| Wildlife Conservation Commission was made due to finding an injured |
| Loggerhead sea turtle in Unit 1 intake. The sea turtle was transported |
| offsite for rehabilitation. R2DO (Tom Decker) notified. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| ***UPDATE 1330EST ON 4/23/02 FROM JACK BREEN TO RICH LAURA*** |
| |
| The licensee rescued a Loggerhead sea turtle from the intake canal. The |
| Florida Fish and Wildlife Conservation Commission was notified, and the |
| turtle was turned over for rehabilitation. |
| |
| The NRC Resident Inspector was informed. Notified R2DO (B. Bonser). |
| |
| ***UPDATE 1241EDT ON 5/29/02 FROM DAVE WILLIAMS TO RICHARD LAURA*** |
| |
| The licensee reported that an offsite notification was made to the Florida |
| Fish and Wildlife Conservation Commission concerning the discovery of a live |
| loggerhead sea turtle found in the plant's intake canal. The turtle was |
| lethargic and was sent for rehabilitation. |
| |
| The NRC Resident Inspector was informed. Notified R2DO (K. Landis). |
| |
| ***** UPDATE AT 1125 EDT ON 06/01/02 FROM CHARLES MARPLE TO LEIGH TROCINE |
| ***** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1020 on 06/01/02, a notification was made to the Florida Fish and |
| Wildlife Conservation Commission regarding a weak and emaciated Loggerhead |
| turtle found in the plant intake barrier net. The turtle will be sent |
| off-site to the Marine Life Center for Rehabilitation." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R2DO (Kerry Landis). |
| |
| *****UPDATE AT 11:53 EDT ON 6/2/02 FROM MARPLE TO LAURA****** |
| |
| "A notification was made to the Florida Fish and Wildlife Conservation |
| Commission regarding a dead small green sea turtle found in the tangle net. |
| The turtle will be maintained on ice for a postmortem examination." |
| |
| The NRC resident inspector was notified. Notified R2DO (K. Landis) |
| |
| *****UPDATE AT 12:45 EDT ON 7/18/02 FROM BREEN TO LAURA****** |
| |
| A notification was made to the State regarding a dead green sea turtle that |
| was removed from the intake canal. |
| |
| The NRC resident inspector will be notified. |
| |
| Notified R2DO (C. Payne |
| |
| ***UPDATE AT 1045 EDT ON 10/20/02 FROM KORTH TO NORRIS*** |
| |
| A Loggerhead turtle was retrieved from the plant's intake canal. The turtle |
| was in need of rehabilitation. Per the plant's turtle permit, the Florida |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 0927 EDT. |
| |
| The NRC Resident Inspector has been notified. |
| |
| Notified R2DO (Barr) |
| |
| * * * UPDATE AT 1338 EDT ON 10/22/02 FROM KELLY KORTH TO GERRY WAIG * * * |
| |
| A Loggerhead turtle was retrieved from the plant's intake canal. The turtle |
| was in need of rehabilitation. Per the plant's turtle permit, the Florida |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 1250 EDT. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| Notified R2DO (Bob Haag) |
| |
| * * * UPDATE ON 11/22/2002 @ 1821 BY FIELDS TO GOULD * * * |
| |
| The licensee notified the Florida Department of Environmental Protection of |
| the recovery of a distressed loggerhead sea turtle from their intake canal. |
| The turtle was taken to a rehabilitation facility. |
| |
| The NRC Resident inspector will be notified. Notified R2DO (David Ayres). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39387 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 00:03[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/21/2002|
+------------------------------------------------+EVENT TIME: 19:55[CST]|
| NRC NOTIFIED BY: TOM GORDON |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO LAW ENFORCEMENT |
| |
| Notifications were made to the FBI and Linn County Sheriff by the licensee. |
| There was no impact on plant operations. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| See the HOO Log for additional information. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39388 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 00:50[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 11/21/2002|
+------------------------------------------------+EVENT TIME: 19:53[EST]|
| NRC NOTIFIED BY: KEVIN W. DAHM |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OPRM CHANNELS DECLARED INOPERABLE |
| |
| "On November 21, 2002, Detroit Edison received confirmation from General |
| Electric of a non-conservative analysis of OPRM Period Setpoint. |
| |
| "The non-conservative analysis affected the OPRM [Oscillating Power Range |
| Monitor] Reactor Protection System (RPS) scram setpoint. The RPS setpoint |
| may result in violating the Minimum Critical Power Ratio (MCPR) safety |
| limits during a thermal-hydraulic instability. |
| |
| "All OPRM channels have been declared inoperable. Technical Specifications |
| 3.3.1.1 Action J requires an alternate method of detecting and suppressing |
| thermal-hydraulic instabilities to be implemented within 12 hours. |
| Alternate methods have been established, thus the Technical Specification |
| has been satisfied. |
| |
| "This report is being made in accordance with 10CFR50.72(b)(3)(v), any event |
| or condition that could have prevented the fulfillment of the safety |
| function of a system needed to shut down the reactor and maintain it in a |
| safe shutdown condition. |
| |
| "This report is also being made in accordance with 10CFR50.72(b)(3)(vi). |
| Events covered in paragraph (b)(3)(v) of this section may include one or |
| more procedural errors, equipment failures, and/or discovery of design, |
| analysis, fabrication, construction, and/or procedural inadequacies." |
| |
| The NRC Resident Inspector has been notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39389 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 06:27[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 11/21/2002|
+------------------------------------------------+EVENT TIME: 21:56[CST]|
| NRC NOTIFIED BY: JOHN DAMPF |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID SPECIFIED SYSTEM ACTUATION DURING MAINTENANCE |
| |
| "At 2156, 11/21/02, while performing OSP-SB-0002E, a valid actuation signal |
| was generated that caused the 'B' Reactor Trip Breaker to trip open. The |
| cause of the event was the inadvertent mispositioning of a rotary selector |
| switch utilized in the Solid State Protection System (SSPS) circuitry, which |
| enabled the P-10 permissive circuit. Permissive P-10 is normally energized |
| when power increases above 10 percent and this in turn enables a Reactor |
| Trip permissive (P-7) for a low Pressurizer pressure reactor trip which has |
| a setpoint of 1885 psig. Since the plant was in Mode 4 with primary system |
| pressure at 970 psig, a valid Reactor Trip signal was generated and caused |
| the Reactor Trip breaker to open. In addition to tripping the 'B' Reactor |
| Trip breaker, one Source Range detector was de-energized due to energizing |
| the P-10 permissive circuitry. All systems actuated as expected. |
| Performance of OSP-SB-0002B was terminated, the plant was stabilized, a |
| recovery plan was developed, and the procedure was then successfully |
| completed. An Event Review Team (ERT) was assembled to determine the cause |
| of the event. Additional corrective action to be taken will be based upon |
| recommendations provided by the ERT." |
| |
| The Resident Inspector will be notified by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39391 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 13:34[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 10:45[EST]|
| NRC NOTIFIED BY: BRUCE SHICK |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO MARYLAND DEPARTMENT OF ENVIRONMENT |
| |
| |
| Hydraulic oil spill from a Sky Lift resulted in 5 gallons of hydraulic fluid |
| deposited on the gravel and pavement below the Sky Lift. The spill was from |
| a separated oil line. No water ways or storm drains were involved. ERPIP |
| 3.0 Hazardous Material Spill and Spill Plan were implemented. Maryland |
| Department of Environment was notified of the hydraulic oil spill (quantity |
| >26 gallons). The event was terminated and the spill was cleaned up at |
| 1300 hours. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39392 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GENERAL ELECTRIC COMPANY |NOTIFICATION DATE: 11/22/2002|
|LICENSEE: GENERAL ELECTRIC COMPANY |NOTIFICATION TIME: 13:43[EST]|
| CITY: SAN JOSE REGION: 4 |EVENT DATE: 11/22/2002|
| COUNTY: STATE: CA |EVENT TIME: [PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/22/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |MOHAMED SHANBAKY R1 |
+------------------------------------------------+DAVID AYRES R2 |
| NRC NOTIFIED BY: JASON POST (fax) |BRENT CLAYTON R3 |
| HQ OPS OFFICER: CHAUNCEY GOULD |JACK FOSTER NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GENERAL ELECTRIC IDENTIFIED THE STABILITY OPTION III PERIOD BASED DETECTION |
| ALGORITHM Tmin SPECIFICATION HAS A DEFECT |
| |
| "Stability solution Option III is implemented in the Oscillation Power Range |
| Monitor (OPRM). Each OPRM channel contains 18 to 33 OPRM cells (depending |
| upon plant size). Each OPRM cell signal is summed from three to four |
| closely spaced Local Power Range Monitor (LPRM) signals. Each OPRM cell |
| signal is processed through the Option Ill detection algorithms to determine |
| when a trip is required. Trip of one OPRM cell causes its OPRM channel to |
| trip, and when sufficient OPRM channels trip (one-out-of-two taken twice, or |
| two-out-of-four), a reactor scram is initiated to terminate the |
| oscillation. |
| |
| "An OPRM trip is enabled for plant operation within the OPRM Armed Region as |
| defined on the power/flow map. The Armed Region extends from natural |
| circulation to 60% of rated core flow. The licensing basis for the OPRM is |
| to detect all expected oscillations within the OPRM Armed Region, and |
| initiate a reactor trip to suppress the oscillation and provide Minimum |
| Critical Power Limit (MCPR) safety limit protection. |
| |
| "GE LTR NEDO-31960-A, Supplement 1, 'BWR Owners' Group Long - Term Stability |
| Solutions Licensing Methodology (Supplement 1),' November 1995, describes |
| the Option III detection algorithms. The Period Based Detection Algorithm |
| (PBDA) provides licensing basis MCPR safety limit protection. Other |
| algorithms provide defense-in-depth protection. The PBDA includes two |
| parameters called Tmin and Tmax. The PBDA will not evaluate oscillations if |
| the period is less than Tmin or greater than Tmax because these would not |
| be indicative of an expected coupled neutronic/thermal - hydraulic |
| instability. The LTR specifies that 'typical' Tmin values are in the |
| range of 1.0 to 1.4 seconds and 'typical' Tmax values are in the range of |
| 3.0 to 3.5 seconds. |
| |
| "The expected period of a coupled neutronic/thermal-hydraulic instability |
| depends upon the fluid transit time through the core, and therefore depends |
| upon core flow rate. This has been demonstrated in reactor operation and is |
| predicted by GE computer models. At high core flow, the expected |
| oscillation period is shorter. At low core flow rate, the expected |
| oscillation period is longer. The intent of the OPRM is that Tmin and Tmax |
| provide a wide range with adequate margin to the expected oscillation period |
| for operation within the OPRM Armed Region so that all expected coupled |
| neutronic/thermal-hydraulic instabilities will be detected by the PBDA." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39393 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [2] [] STATE: AR |NOTIFICATION TIME: 15:10[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 08:56[CST]|
| NRC NOTIFIED BY: HATHCOTE |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS R4 |
|10 CFR SECTION: | |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECURITY REPORT |
| |
| Unattended security weapon, compensatory measures put in place upon |
| discovery. |
| |
| The NRC Resident Inspector was notified |
| |
| Contact HOO for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39394 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: UNITED STATES ARMY -ABERDEEN |NOTIFICATION DATE: 11/22/2002|
|LICENSEE: UNITED STATES ARMY |NOTIFICATION TIME: 15:31[EST]|
| CITY: ABERDEEN REGION: 1 |EVENT DATE: 10/31/2002|
| COUNTY: STATE: MD |EVENT TIME: [EST]|
|LICENSE#: 91-30563-01 AGREEMENT: Y |LAST UPDATE DATE: 11/22/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |DAVID AYRES R2 |
+------------------------------------------------+FRED BROWN NMSS |
| NRC NOTIFIED BY: JOYCE KUYKENDALL | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING CHEMICAL AGENT DETECTOR CONTAINING 30 MILLICURIES OF NICKEL-63 |
| |
| During a conversation in a training exercise on October 31, 2002, the |
| Radiation Safety Officer at Fort Bragg, NC learned that a Unit had lost a |
| GID-3 Chemical Agent Detector, containing 30 millicuries of Nickel-63, |
| during a training exercise back in Oct/Nov of 2001. The training area was |
| searched and other Units were asked if they had possession of the missing |
| Chemical Agent Detector. The detector was not found and is now it considered |
| missing. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39395 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FRAMATOME ANP |NOTIFICATION DATE: 11/22/2002|
|LICENSEE: FRAMATOME ANP |NOTIFICATION TIME: 15:48[EST]|
| CITY: RICHLAND REGION: 4 |EVENT DATE: 11/22/2002|
| COUNTY: STATE: WA |EVENT TIME: [PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/22/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |BRENT CLAYTON R3 |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JERALD HOLM | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE "POWERPLEX" MONITORING SOFTWARE CONTAINS AN ERROR |
| |
| "The MCPR calculation using the SPCB correlation in the MICROBURN-B2 and |
| MICROBURN-B codes and associated POWERPLEX monitoring software contains an |
| error. The error is in the determination of the axial adjustment factor for |
| use in the SPCB CPR [Critical Power Ratio] correlation. This can lead to |
| non-conservative CPR calculations when using the SPCB CPR correlation and |
| potentially a violation of the MCPR [Minimum Critical Power Ratio] Technical |
| Specification operating limit since the POWERPLEX incore monitoring code may |
| under predict the MCPR for comparison to the operating limit. This error in |
| MICROBURN-B2 and MICROBURN-B had no impact on the operating limit itself. |
| The POWERPLEX incore monitoring software in use at River Bend, Grand Gulf, |
| and LaSalle Unit 1 is impacted by this error." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39396 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 16:18[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 10:00[EST]|
| NRC NOTIFIED BY: SCHORK |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT START OF "B" EMERGENCY DIESEL GENERATOR |
| |
| "The cause of the inadvertent actuation was human error by an Auxiliary |
| Operator. The Auxiliary Operator mistakenly placed the "A" diesel generator |
| Engineering Safeguards Test Switch in the "Test" position, instead of |
| placing the "B" EDG Engineering Safeguards Test Switch in the "Test" |
| position. During the "B" ESAS [Emergency Safeguards Actuation System] |
| testing, a portion of the test sends a simulated start signal to the "B" |
| EDG. With the "B" EDG Engineering Safeguards test switch in the "Test" |
| position, a light actuates when the simulated ESAS start signal is received, |
| indicating that the ESAS start signal had been received. However, the "B" |
| EDG Engineering Safeguards Test Switch was not in the "Test" position. |
| Therefore the "B" EDG started in accordance with the plant design. |
| |
| "A review of this event has determined that the event is reportable to the |
| NRC in accordance with the guidance in NUREG 1022, Rev. 2. The signal to |
| start the "B" EDG is not considered a "valid" signal because it was not a |
| signal initiated by any actual plant condition or parameter. Therefore, |
| this event is considered to be an inadvertent actuation that was caused by |
| an invalid signal and has been determined to be reportable to the NRC in |
| accordance with 10 CFR 50.73 (a)(2)(iv)(A). |
| |
| "There was no effect on the TMl-1 plant due to the inadvertent start, beyond |
| the "B" Emergency Diesel Generator, The "B" EDG did not initiate block |
| loading or any other sequence of events. The "B" EDG was immediately |
| shutdown and an event investigation was initiated. The "A" EDG remained |
| operable throughout the event. Throughout the event, the "A" EDG was |
| capable of providing emergency alternating current including performing the |
| required "fast start" and block loading in response to an ESAS auto-start |
| signal, an undervoltage condition or loss of offsite power event. |
| |
| "As an immediate action, a test run of the "B" EDG is being performed for |
| approximately 1 hour to confirm that the inadvertent "fast" start did not |
| have any impact on its ability to provide emergency alternating current in |
| the event of an ESAS auto-start signal, an undervoltage condition or loss of |
| offsite power. |
| |
| "As stated above, an event investigation has been initiated. The event will |
| be documented in the site corrective action program. When the cause of the |
| human error is identified, appropriate corrective action will be taken and |
| documented in the applicable corrective action report." |
| |
| The Sr. Resident Inspector has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39397 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 16:29[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 13:28[EST]|
| NRC NOTIFIED BY: BAIN |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID AYRES R2 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS OF THE OSCILLATION POWER RANGE MONITOR PERIOD |
| SETPOINT |
| |
| "On November 22, 2002, Brunswick Unit 1 received notification from General |
| Electric of a Part 21 Non-Conservative Analysis of the Oscillation Power |
| Range Monitor (OPRM) Period Setpoint. The non-conservative analysis |
| affects the OPRM Reactor Protection System setpoint which may result in |
| inoperability of the OPRM Technical Specification function. Unit 2 does not |
| have the OPRM system installed and is not affected by this condition. Due |
| to the implementation of Technical Specification required compensatory |
| actions, there is minimal safety significance. |
| |
| "All Unit 1 OPRM channels have been declared inoperable. Technical |
| Specification 3.3.1.1 Action I requires an alternate method of detecting and |
| suppressing thermal hydraulic instabilities to be implemented within 12 |
| hours. The alternate methods of detection and suppression are currently in |
| place. Activities are in progress to make the necessary adjustments to |
| return the OPRM channels to an operable status." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39399 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 21:17[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 16:50[CST]|
| NRC NOTIFIED BY: JOHN J. REIMER |LAST UPDATE DATE: 11/23/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 97 Power Operation |97 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE |
| |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or |
| Condition that could have prevented fulfillment of a Safety Function needed |
| to Mitigate the Consequences of an Accident. During inspection of the High |
| Pressure Core Spray (HPCS) 2VY02A area cooler, missing sheet metal screws |
| were discovered. This could have prevented the High Pressure Core Spray |
| System (HPCS), a single train safety system, from performing its design |
| function during a seismic event. This also made the Division 3 Diesel |
| Generator inoperable. This is reportable as an 8 hour ENS notification. |
| |
| "The required actions of Technical Specification (TS) 3.5.1 were entered on |
| 11/22/02 at 1650 when the system was made inoperable. TS 3.8.1 does not |
| require Division 3 Diesel Generator operability if HPCS is declared |
| inoperable. Preparations to replace the missing sheet metal screws are in |
| progress. All other Emergency Core Cooling Systems are operable at this |
| time. An extent of condition review will be performed on all divisions for |
| both units." |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| |
| * * * UPDATE ON 11/23/02 @ 1333 BY CLARK TO GOULD * * * |
| |
| "Subsequent to ENS notification EN #39399, repairs were affected to the HPCS |
| area cooler (2VY02A) and the system was returned to operable. An extent of |
| condition inspection was performed on the remaining Unit 1 and Unit 2 |
| divisional area coolers. During these inspections it was discovered that |
| the Unit 1, Division 2 area cooler (1VY03A) was also missing several sheet |
| metal screws. The system was removed from service, repaired and returned |
| to operable. No problems were discovered on either of the two remaining |
| Unit 1 divisional area coolers. |
| |
| During inspection on Unit 2, the Division 2 area cooler (2VY03A) was missing |
| all of its sheet metal screws. At the time of discovery of the Division 2 |
| inoperability, the HPCS (Division 3) area cooler had already been repaired |
| and declared operable. It was determined however, that at some point both |
| the HPCS (Division 3) and Division 2 Emergency Core Cooling System (ECCS) |
| injection subsystems were under these conditions simultaneously. Per |
| Technical Specification (TS) 3.5.1 Bases when this combination of ECCS |
| subsystems are inoperable, the plant is in a condition outside of the design |
| basis. |
| |
| Investigation of equipment and maintenance history will be performed to |
| determine if any additional periods existed with multiple divisions under |
| these conditions simultaneously. At this time all divisional area coolers |
| on both Units have been inspected. Those with deficiencies have been |
| repaired and declared operable." |
| |
| |
| The NRC Resident Inspector was notified. |
| |
| Reg 3 RDO(Clayton) was informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39400 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/22/2002|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 22:54[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 01:04[EST]|
| NRC NOTIFIED BY: STEVE NICOLAOS |LAST UPDATE DATE: 11/22/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS OF THE OSCILLATION POWER RANGE MONITOR PERIOD |
| SETPOINT |
| |
| "On November 22, 2002, Nine-Mile Point Unit 2 received confirmation from |
| General Electric of a Non-Conservative Analysis of the OPRM Period |
| Setpoint. |
| |
| "The Non-Conservative Analysis affected the OPRM Reactor Protection System |
| (RPS) scram setpoint. The RPS setpoint could have resulted in violating the |
| Minimum Critical Power Ratio (MCPR) safety limits during a thermal - |
| hydraulic instability. |
| |
| "At the time of the notification Nine-Mile Point Unit 2 was in Mode 4 cold |
| shutdown. Upon notification, the OPRM's were immediately declared |
| inoperable. |
| |
| "On November 22, 2002, the OPRM's were adjusted to satisfy the vendor |
| recommendations and the OPRM's have since been declared operable. |
| |
| "This report is being made in accordance with Nine-Mile Point Unit 2's |
| Operating License 2.C.2 Technical Specification and Environmental Protection |
| Plan. Nine-Mile Point Nuclear Station, LLC shall operate the facility in |
| accordance with Technical Specifications." |
| |
| The NRC Resident Inspector has been notified of this event |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39401 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 11/23/2002|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 07:37[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/23/2002|
+------------------------------------------------+EVENT TIME: 03:32[EST]|
| NRC NOTIFIED BY: ALISON MACKELLAR |LAST UPDATE DATE: 11/23/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID AYRES R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 85 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO LOW-LOW STEAM GENERATOR LEVEL |
| |
| "At 0332 hours, with Surry Power Station Unit 2 at 85% reactor power, a low |
| low S/G level signal was received which resulted in an automatic reactor |
| trip. Immediately prior to the trip, the Turbine Stop and Governor Valves |
| were being manipulated for a scheduled Governor Valve Freedom Test. While |
| closing Turbine Governor Valve #3 the Turbine Valve Limiter failed to zero |
| closing all four governor valves. This led to the automatic reactor trip. |
| |
| "IRPI indications for six control rods indicated between 11 and 20 steps |
| following the trip. [Unit 2 was] borated as necessary to ensure adequate |
| shutdown margin. All other control rods fully inserted into the core as |
| designed. The shutdown margin for Unit 2 was determined to be satisfactory. |
| Auxiliary feedwater automatically initiated [ESFAS] as designed on low low |
| steam generator level. All three Main Steam Trip Valves were manually |
| closed due to inability to verify full closed indication on #1 Turbine Stop |
| Valve. Primary RCS temperature decreased to approximately 547 degrees |
| following the reactor trip and is currently stable on the Secondary Power |
| Operated Relief Valves. |
| |
| "No primary safety or power operated relief valves were actuated during the |
| event. No indication of primary to secondary leakage exists, therefore no |
| adverse radiological consequences resulted from this event. |
| |
| "All electrical busses transferred properly following the trip and all |
| emergency diesel generators are operable. There were no radiation releases |
| due to this event, nor were there any personnel injuries or contamination |
| events. The cause of the event is being investigated. |
| |
| "Unit 2 is currently at Hot Shutdown with RCS temperature being maintained |
| at approximately 547 degrees. |
| |
| "Unit 1 was not affected by this event and remains stable at 100% power |
| operations. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(b)." |
| |
| The Resident Inspector was notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39402 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/24/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 10:29[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/24/2002|
+------------------------------------------------+EVENT TIME: 08:14[CST]|
| NRC NOTIFIED BY: DUSTIN PRICE |LAST UPDATE DATE: 11/24/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOTIFICATION OF OFFSITE AUTHORITIES OF FIRE IN ONSITE WAREHOUSE |
| |
| "At approximately 08:14, Sunday, November 24,2002, East Warehouse Sprinkler |
| System Initiated annunciator alarmed. Seconds later, 1P-48 Electric Fire |
| Pump initiated as indicated on panel 1C40. The Second Assistant was |
| dispatched and reported the sprinkler system in operation and a portion of |
| the East Warehouse filled with smoke. The on-site fire brigade was assembled |
| at this time. |
| |
| "The Fire Brigade Leader, after reaching the East Warehouse, reported no |
| open flames and smoke emanating from a popcorn machine located in a |
| breakroom in the warehouse. As a precaution, off-site assistance was |
| requested of the Palo Fire Department. Currently the fire is out and the |
| building is being ventilated. This notification is being made due to |
| notification of offsite fire department and local law enforcement |
| agencies." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021