Event Notification Report for November 22, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/21/2002 - 11/22/2002
** EVENT NUMBERS **
39326 39387 39388
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39326 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/29/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:26[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/28/2002|
+------------------------------------------------+EVENT TIME: 23:15[EDT]|
| NRC NOTIFIED BY: JIM CASE |LAST UPDATE DATE: 11/21/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES CREED R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| DAMAGED CONTROL ROOM DOOR SEAL |
| |
| "Declared both trains of Control Room Emergency Recirc inoperable, entered |
| Tech Spec 3.0.3 from Tech Spec 3.7.3 on loss of Control Room boundary. A |
| damaged door seal leading from the Control Complex to the Service building |
| caused the loss of the Control room boundary. Door was closed and |
| temporarily sealed per SOI-M25/26. Exited Tech Spec 3.0.3 at 00:15 on |
| 10/29/02." |
| |
| The NRC Resident Inspector was notified. |
| |
| |
| **** RETRACTION on 11/21/02 at 1717EST by Ken Russell taken by MacKinnon |
| **** |
| |
| Evaluation determined that the door seal leakage was bounded by a |
| calculation for degraded Control Room door seals that determined the maximum |
| leakage allowed by the analysis in the Updated Safety Analysis Report (USAR) |
| would not be exceeded even if the entire seal was removed. Therefore, it |
| has been concluded that the Control Room boundary was not lost and this was |
| not a condition that could have prevented the fulfillment of a safety |
| function. |
| |
| As indicated in the original notification, entry was made into Technical |
| Specification 3.0.3 as a result of the assumed loss of Control Room |
| Emergency Recirculation. However, the condition was corrected within one |
| hour, such that it was not necessary to initiate actions to shutdown and |
| thus this condition was not reported per 10CFR50.73(a)(2)(i)(B), a condition |
| which was prohibited by the plant's Technical Specification. R3DO (Brent |
| Clayton) notified. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 39387 |
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| 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
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| 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. |
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|Power Reactor |Event Number: 39388 |
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| 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
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| 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 analyses affected the OPRM 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021