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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 !!!!!!!
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|Power Reactor |Event Number: 35840 |
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+------------------------------------------------------------------------------+
| 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. |
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!!!!!!!!! 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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021