Event Notification Report for April 24, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/23/2001 - 04/24/2001
** EVENT NUMBERS **
37823 37856 37940 37941
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37823 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/10/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 18:59[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/10/2001|
+------------------------------------------------+EVENT TIME: 17:05[CST]|
| NRC NOTIFIED BY: P DECKER |LAST UPDATE DATE: 04/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| DIFFERENTIAL PRESSURE TO OPEN THE SUPPRESSION CHAMBER TO DRYWELL VACUUM |
| BREAKERS DISCREPANCIES WERE IDENTIFIED. |
| |
| During review of Inservice Testing requirements, while the plant was in |
| shutdown, discrepancies were identified with acceptance criteria for the |
| torque values used to determine the equivalent differential pressure to open |
| the suppression chamber to drywell vacuum breakers. The measured torque |
| values indicate that the differential pressure required to fully open the |
| suppression chamber to drywell vacuum breakers would be greater than that |
| assumed in containment analyses. The suppression chamber to drywell vacuum |
| breakers insure that the 2 psig external design pressure for the primary |
| containment drywell suppression chamber and vent system is not exceeded and |
| containment integrity is assured. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
| |
| * * * RETRACTION ON 04/23/01 AT 1805ET BY JIM MCKAY TAKEN BY MACKINNON * * |
| * |
| |
| Retraction of notification made on March 10, 2001. The notification stated |
| that discrepancies were identified with acceptance criteria for the torque |
| values used to determine the equivalent differential pressure to open the |
| suppression chamber to drywell vacuum breakers. The measured values |
| indicated a greater differential pressure required to fully open then |
| assumed in containment analysis. Upon further evaluation and review of the |
| containment analyses, the results of the containment analysis were |
| effectively independent and not adversely impacted by the suppression. |
| |
| R3DO (Tom Kozak) notified. |
| |
| NRC Resident Inspector will notified of this retraction by the licensee |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37856 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/22/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 02:16[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/21/2001|
+------------------------------------------------+EVENT TIME: 21:30[CST]|
| NRC NOTIFIED BY: DUSTIN WRIGHT |LAST UPDATE DATE: 04/23/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DRYWELL TO TORUS BYPASS LEAKAGE NOT REEVALUATED FOR POWER RERATE |
| |
| "An unanalyzed plant condition may exist due to Drywell to Torus bypass |
| leakage as defined in Tech Spec Bases 3.7.A was not reevaluated for power |
| rerate. The original evaluation determined that the maximum allowable |
| leakage capacity was 0.12 square feet. When power rerate was being |
| evaluated, General Electric assumed that Monticello was bound by a generic |
| evaluation for the drywell to torus allowable capacity of an 0.01 square |
| feet." |
| |
| Corrective action includes a reevaluation, as appropriate. The licensee |
| informed the NRC resident inspector. |
| |
| * * RETRACTION ON 04/23/01 AT 1805 ET BY JIM MCKAY TAKEN BY MACKINNON. |
| |
| Retraction of notification made on March 22, 2001. The notification stated |
| that an unanalyzed plant condition may exist due to a drywell to torus |
| vacuum breaker bypass leakage [which] was not re-evaluated for power rerate. |
| Upon further revaluation conducted by General Electric Company and based on |
| a review of the original analysis, the bounding assumptions used to |
| calculate the maximum allowable bypass leakage area was effectively |
| independent of reactor power and are, therefore, not adversely impacted by |
| power rerate. As such, an unanalyzed condition does not exist. |
| |
| R3DO (Tom Kozak) notified. |
| |
| NRC Resident Inspector will be notified of this retraction by the licensee. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37940 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/23/2001|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 21:35[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/23/2001|
+------------------------------------------------+EVENT TIME: 20:12[CDT]|
| NRC NOTIFIED BY: BRIAN CABLE |LAST UPDATE DATE: 04/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |BILL JONES R4 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|*AEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOHN ZWOLINSKI NRR |
| |KEN BROCKMAN R4 |
| |ELMO COLLINS R4 |
| |SAM COLLINS NRR |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| LOSS OF ALL ANNUNCIATORS IN THE MAIN CONTROL ROOM |
| |
| At 2012 CT, the licensee entered an Unusual Event per EAL 4.1.2, unplanned |
| loss of most or all safety system annuncuators. Plant computer remained on |
| line but will not give alarms. I&C Technicians have been called in to |
| investigate. All emergency core cooling systems are fully operable, and the |
| electrical grid is stable. The licensee notified state and county officials |
| that they had entered an Unusual Event. |
| |
| "Initial indication of loss of annunciators was received via annunciator |
| 'Annunciator System Trouble.' Abnormal Procedure 2.4.8.2, 'Annunciator |
| Failures,' was entered, and the determination was made that all annunciators |
| in the Main Control Room [were] lost." |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE ON 04/23/01 AT 2211 ET BY S. JOBE TAKEN BY MACKINNON * * * |
| |
| Unusual Event Terminated at 2105 CT. |
| |
| "At 2105 [CT,] the Emergency Director exited the EAL when the Main Control |
| Room Annunciator System 'A' was restored by re-booting the Ronan System for |
| the Main Control Room." State and Local officials were notified that the |
| Unusual Event was exited. |
| |
| The NRC Resident Inspector will be notified of this update by the licensee. |
| |
| The NRC operations center notifications were the same as the above. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37941 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/24/2001|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 03:23[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/24/2001|
+------------------------------------------------+EVENT TIME: 02:06[CDT]|
| NRC NOTIFIED BY: MIKE MEYER |LAST UPDATE DATE: 04/24/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |THOMAS KOZAK R3 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|*AEC 50.72(a) (1) (i) EMERGENCY DECLARED |NADER MAMISH IRO |
| |GENE CANUPP FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DECLARATION OF AN UNUSUAL EVENT DUE TO A SMALL DEBRIS FIRE ON A STEAM |
| GENERATOR PLATFORM DURING THE PERFORMANCE OF EDDY CURRENT TESTING |
| |
| At 0148 CDT, the control room was notified of a fire in the Unit 1 |
| containment. It is currently believed that a problem with eddy current |
| testing equipment (possibly an electrical fault) resulted in a fire |
| involving a small pile of debris on the 8-foot elevation steam generator 'A' |
| platform. The fire brigade was dispatched immediately, and the fire was |
| extinguished within 2 to 3 minutes of the time the extinguishing agent |
| (water) was applied. Offsite assistance was not required. At 0211 CDT, a |
| second team provided the control room with a confirmatory report that the |
| fire had been successfully extinguished. There were no reports of injuries |
| or the spread of contamination as a result of the fire. |
| |
| The exact time the extinguishing agent was applied to the fire was not known |
| at the time of this event notification. Because the exact duration of the |
| fire (i.e., less than or greater than 10 minutes) was not known, the |
| licensee declared an Unusual Event at 0206 CDT as a conservative measure. |
| |
| At the time of this event, Unit 1 was defueled, and Unit 2 was operating at |
| 100% power. |
| |
| The licensee notified Manitowac and Kewaunee Counties, the Sate of |
| Wisconsin, and the NRC resident inspector. |
| |
| ***** UPDATE AT 0343 EDT ON 04/24/01 FROM MIKE MEYER TO LEIGH TROCINE ***** |
| |
| The licensee terminated the Unusual Event at 0243 CDT. |
| |
| The licensee plans to notify Manitowac and Kewaunee Counties, the Sate of |
| Wisconsin, and the NRC resident inspector. The NRC operations officer |
| notified the R3DO (Kozak), NRR EO (Richards), IRO (Mamish), and FEMA |
| (Canupp). |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021