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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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    |
|                                                   |                          |
|                                                   |                          |
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                                   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       |
+------------------------------------------------------------------------------+
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| 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                                   
+------------------------------------------------------------------------------+
| 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.          |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37941       |
+------------------------------------------------------------------------------+
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| 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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