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Event Notification Report for June 23, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/22/1999 - 06/23/1999

                              ** EVENT NUMBERS **

35822  35840  35842  35851  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   35822       |
+------------------------------------------------------------------------------+
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| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 06/14/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 17:59[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/14/1999|
+------------------------------------------------+EVENT TIME:        16:00[CDT]|
| NRC NOTIFIED BY:  GARY HARRINGTON              |LAST UPDATE DATE:  06/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF SOME ESF EQUIPMENT OUT OF SERVICE AT THE SAME TIME            |
|                                                                              |
| "KNPP [Kewaunee Nuclear Power Plant] recognized on 6/11/99 that the 'B'      |
| diesel generator governor control speed sensor was misadjusted on 6/2/99.    |
| The actual impact of the misadjusted switch is unknown.  Nevertheless, KNPP  |
| is reporting this as though the condition resulted in the diesel generator   |
| being inoperable.  The basis for reporting this event is that during the     |
| time between 6/2 and 6/11 while the control was misadjusted, the opposite    |
| train Shield Building Vent system was removed from service for maintenance   |
| on 6/3, and the opposite train Internal Containment Spray system was removed |
| from service for maintenance on 6/10.  Having both trains of ESF equipment   |
| out of service is reportable as being in an unanalyzed condition.            |
|                                                                              |
| "Currently all ESF equipment is operable.  Corrective action program efforts |
| need to determine why the operability/reportability assessment was not       |
| performed on 6/11.  KNPP will also continue to pursue what the actual        |
| operability impact is from the misadjusted control."                         |
|                                                                              |
| The licensee is also investigating the cause of the misadjustment that       |
| occurred on 6/2/99.                                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT ON 6/22/99 AT 1139 BY HARRINGTON, RECEIVED BY WEAVER * * *   |
|                                                                              |
| The licensee has requested retraction of this event report based on testing  |
| conducted subsequent to the report.  On 6/17/99, the licensee tested the     |
| diesel generator using the speed setting from the as found condition.        |
| Based on the results of this test the licensee has concluded that the diesel |
| generator was operable and therefore that no reportable event occurred.  The |
| licensee informed the NRC resident inspector.  The Operations center         |
| notified the R3DO (Jordan).                                                  |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35840       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 21:01[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        17:22[CDT]|
| NRC NOTIFIED BY:  S MARIK                      |LAST UPDATE DATE:  06/22/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION.                                                               |
|                                                                              |
| At 1722 CDT the 2D primary containment vacuum breaker 2PC001D went from the  |
| closed (normal) position to an indicated dual position.  The valve is        |
| actuated by a differential pressure between the suppression chamber and the  |
| drywell air space and is designed to open at 0.5 psid or less.  Differential |
| pressure at 1722 CDT was 0.23 psid.  An operator was dispatched and the      |
| containment vacuum breaker was manually cycled.  After being manually cycled |
| the containment vacuum breaker returned to the closed position.  The         |
| licensee subsequently satisfactorily performed an operability test on the    |
| containment vacuum breaker.                                                  |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
|                                                                              |
|                                                                              |
| *** UPDATE ON 6/22/99 @ 1611 BY MARIK TO GOULD ***   RETRACTION              |
|                                                                              |
| BASED ON A REVIEW BY STATION MANAGEMENT AND CONCURRENCE FROM CORPORATE       |
| REGULATORY ASSURANCE, THE LICENSEE IS RETRACTING THIS EVENT.  FOLLOWING      |
| ADDITIONAL REVIEWS OF 10CFR50.72 AND NUREG-1022 REV 1, IT HAS BEEN           |
| DETERMINED THE ACTUATION OF THE "D" CONTAINMENT VACUUM BREAKER IS AN         |
| ACTUATION OF A SINGLE COMPONENT OF THE CONTAINMENT VACUUM RELIEF             |
| SYSTEM(CVARS).  THIS ACTUATION BY ITSELF WOULD NOT BE CAPABLE OF PROVIDING   |
| THE CVARS ESF DESIGN FUNCTION OF PROTECTING THE DRYWELL FLOOR AGAINST        |
| ADVERSE NEGATIVE PRESSURE DIFFERENTIALS.  THEREFORE, THIS EVENT IS NOT       |
| REPORTABLE AS AN ESF ACTUATION AND ACCORDINGLY IS BEING RETRACTED.           |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.   REG 3 RDO (JORDAN) WAS NOTIFIED.      |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35842       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/18/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:48[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/18/1999|
+------------------------------------------------+EVENT TIME:        02:50[CDT]|
| NRC NOTIFIED BY:  JIM SPIELER                  |LAST UPDATE DATE:  06/22/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION - VACUUM BREAKER                                               |
|                                                                              |
| At 0250 CDT,  #2PC001D, the 2D Primary Containment Vacuum Breaker went from  |
| the (normal) closed position to an indicated dual position.  Locally, it was |
| determined that the valve was just cracked open.  The valve is designed to   |
| open when suppression chamber pressure is approximately 0.5 psig greater     |
| than drywell pressure.  When the vacuum breaker opened the aforementioned    |
| differential pressure was approximately 0.2 psid.  The vacuum breaker was    |
| closed by an equipment attendant and then cycled per LOS-PC-M2 "Unit 2       |
| Drywell-Suppression Pool Vacuum Breaker Operability Test for Condition 1, 2  |
| and 3" to verify proper operation.  The valve cycled satisfactorily.         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| NOTE:  THIS  EVENT IS SIMILAR TO EVENT #35840.                               |
|                                                                              |
|                                                                              |
| *** UPDATE ON 6/22/99 @ 1611 BY MARIK TO GOULD ***         RETRACTION        |
|                                                                              |
| BASED ON A REVIEW BY STATION MANAGEMENT AND CONCURRENCE FROM CORPORATE       |
| REGULATORY ASSURANCE, THE LICENSEE IS RETRACTING THIS EVENT.  FOLLOWING      |
| ADDITIONAL REVIEWS OF 10CFR50.72 AND NUREG-1022 REV 1, IT HAS BEEN           |
| DETERMINED THAT THE ACTUATION OF THE "D" CONTAINMENT VACUUM BREAKER IS AN    |
| ACTUATION OF A SINGLE COMPONENT OF THE CONTAINMENT VACUUM RELIEF SYSTEM      |
| (CVARS).  THIS ACTUATION BY ITSELF WOULD NOT BE CAPABLE OF PROVIDING THE     |
| CVARS ESF DESIGN FUNCTION OF PROTECTING THE DRYWELL FLOOR AGAINST ADVERSE    |
| NEGATIVE PRESSURE DIFFERENTIALS.  THEREFORE, THIS EVENT IS NOT REPORTABLE AS |
| AN ESF AND ACCORDINGLY IS BEING RETRACTED.                                   |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.  REG 3 RDO (JORDAN) WAS NOTIFIED.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35851       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 06/22/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 18:23[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/22/1999|
+------------------------------------------------+EVENT TIME:        16:48[CDT]|
| NRC NOTIFIED BY:  FERGUSON                     |LAST UPDATE DATE:  06/22/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SEPARATION CRITERIA FOR REACTOR TRIP SWITCHGEAR NOT MET.                     |
|                                                                              |
| IT WAS DISCOVERED THAT BOTH TRAINS OF THE REACTOR TRIP SWITCHGEAR WERE 12"   |
| APART WHILE THE REQUIRED SEPARATION IS 20 FEET.  THIS CONDITION PUTS THE     |
| PLANT OUTSIDE ITS DESIGN BASIS AS PER 10CFR50 APPENDIX R, SEC. III.G.2.      |
| THEY HAVE STATIONED A CONTINUOUS FIRE WATCH IN THE AREA.  PLANT OPERATION    |
| WILL CONTINUE.  AS A CORRECTIVE MEASURE VARIOUS OPTIONS ARE BEING            |
| CONSIDERED, WITH ONE REQUIRING A PLANT SHUTDOWN.  THEY HAVE NOT YET          |
| DETERMINED WHICH CORRECTIVE OPTION THEY WILL IMPLEMENT.  INSTRUCTIONS HAVE   |
| BEEN GIVEN TO TRIP THE REACTOR UPON A REPORT FROM THE CONTINUOUS FIRE WATCH  |
| OF AN ACTIVE FIRE IN THE AREA THAT IS BEING MONITORED.                       |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
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