Event Notification Report for September 22, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/21/2000 - 09/22/2000
** EVENT NUMBERS **
37251 37300 37304 37330 37358 37359 37360 37361 37362 37363 37364 37365
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37251 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 18:22[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: BOB KIDDER |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - ECC SYSTEM MOV MAY NOT CLOSE DURING A LOCA AND A LOOP AS REQUIRED - |
| |
| While reviewing motor operated valve (MOV) data from December, 1999, plant |
| staff personnel identified an error in the analyzed data for the closing |
| torque for an MOV in the Emergency Closed Cooling (ECC) System that is |
| required to close during a Loss of Coolant Accident (LOCA) and a Loss of |
| Offsite Power (LOOP). |
| |
| The valve, #OP42-F0295B, isolates the ECC System from the Nuclear Closed |
| Cooling (NCC) Water System. A second isolation valve, #OP42-F0290, was |
| subsequently found to have insufficient data to ensure that it alone would |
| have provided the required isolation. Failure of both valves to potentially |
| not close completely could cause the ECC System to transfer the system's |
| cooling water inventory via the NCC Water System to the Intermediate |
| Building resulting in the loss of cooling capability of the ECC System. This |
| would result in the loss of cooling capability for the systems required to |
| support the Residual Heat Removal (RHR) 'B' and 'C' Subsystems. The #F0290 |
| valve has been successfully tested to ensure that it has adequate torque to |
| close under accident conditions; however, there is insufficient leakage test |
| data available on this valve at this time. Therefore, assuming that valve |
| #F0290 leaks and valve #F0295B does not fully close, a total loss of |
| inventory would potentially occur for Division 2. |
| |
| Therefore, this condition is being conservatively reported to the NRC as a |
| loss of safety function during a past outage which removed RHR 'A' from |
| service, until further evaluation is completed. |
| |
| Valve #OP42-F0295B has been electrically closed under static flow conditions |
| to ensure continued operability of the ECC System. |
| |
| Licensee planned actions include further evaluation of past test data or |
| performance of a specific leak test on valve #OP42-F0290 and further |
| evaluation of data on valve #OP42-F0295B. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * RETRACTED AT 1622 EDT ON 9/21/00 BY MICHAEL McFARLAND TO FANGIE JONES |
| * * * |
| |
| "A 10 CFR 50.72, four (4) hour non-emergency notification was initially made |
| on 8-23-2000, due to Emergency Closed Cooling Loop B inoperability |
| subsequent to valve OP42-F0295B inoperability, due to inadequate closing |
| torque under dynamic flow conditions concurrent with an outage on the |
| alternate, Division 1, equipment. it was indeterminate at that time if |
| sufficient torque existed for the valve to close under accident conditions. |
| |
| "Subsequent to the event notification, the valve has been tested under |
| dynamic flow and reevaluated. This information has resulted in a |
| determination that the OP42-F0295B valve has been, and continues to be, |
| operable under both normal and accident conditions. |
| |
| "Since the valve was determined to have been continuously operable, no |
| Technical Specification Required Actions were exceeded and both loops of ECC |
| remained operable. This event was determined not reportable and ENF 37251 is |
| retracted." |
| |
| The licensee notified the NRC Resident Inspector. The R3DO (Bruce Burgess) |
| was notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37300 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/09/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:21[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/08/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/21/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING SAFETY SYSTEM ACTUATION |
| |
| "On 9/8/2000 at 2000 hours a safety system actuation occurred in the X344 |
| building. Autoclave #4 was in Mode II 'Heating' when the High Condensate |
| Level Shutoff safety system actuated. Per TSR 2.1.3.7, the autoclave was |
| placed in Mode VII 'Shutdown', a mode in which the High Condensate level |
| Shutoff system is not required, and declared inoperable. This is being |
| reported as a valid safety system actuation. An engineering evaluation has |
| been initiated to review the system conditions that surrounded the actuation |
| of the safety system." |
| |
| Operations notified both the NRC resident inspector and DOE site |
| representative. |
| |
| * * * RETRACTED AT 2323 EDT ON 9/21/00 BY ERIC SPAETH TO FANGIE JONES * * * |
| |
| "RETRACTION: On 09/21/00, the Plant Shift Superintendent retracted the |
| above Event. At the time of the High Condensate Level Shutoff (HCLS) system |
| actuation, the autoclave was being cycled on and off in accordance with the |
| applicable procedure for heating a Russian cylinder. Follow up investigation |
| by engineering and operations has determined the HCLS actuation occurred |
| while AC #4 was in Mode VII 'Shutdown'. |
| |
| "Discussions with building supervision and the operator who witnessed the |
| HCLS actuation revealed the AC #4 had been shutdown as part of the on/off |
| heating cycle before the actuation occurred. Based on the configuration of |
| AC #4 at the time, the AC would have been in Mode VII 'Shutdown'. |
| |
| "Since the HCLS system is not required to be operable in Mode VII |
| 'Shutdown', the HCLS system actuation was invalid, and is not reportable in |
| accordance with 10CFR76.120(c)(2). Accordingly, this event is being |
| retracted." |
| |
| The plant has informed the NRC Resident Inspector. The R3DO (Bruce Burgess) |
| and NMSS EO (John Greeves) has been notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37304 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LAKEHEAD PIPE LINE CO., INC |NOTIFICATION DATE: 09/11/2000|
|LICENSEE: LAKEHEAD PIPE LINE CO., INC |NOTIFICATION TIME: 11:20[EDT]|
| CITY: LEWISTON REGION: 3 |EVENT DATE: 09/11/2000|
| COUNTY: STATE: MI |EVENT TIME: 08:00[EDT]|
|LICENSE#: 22-26732-01 AGREEMENT: N |LAST UPDATE DATE: 09/21/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK RING R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT POLLOCK | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REPORT INVOLVING POSSIBLE EQUIPMENT SAFETY DEVICE FAILURE |
| |
| THE LAKEHEAD PIPE LINE RADIATION SAFETY OFFICER (RSO), WAS INFORMED AT 0800 |
| ON 9/11/00 THAT THE COUNTER ON A NUCLEAR DENSITY GAUGE HAD STOPPED WORKING |
| SOMETIME IN MAY OF THIS YEAR AT THEIR LEWISTON STATION LOCATED IN LEWISTON, |
| MICHIGAN. THE SOURCE IS IN THE SHIELDED AND LOCKED POSITION. THE DEVICE IS |
| A MODEL 7400 MANUFACTURED BY BERTHOLD SYSTEMS CONTAINING A 350 MILLICURIE |
| CS-137 SOURCE. |
| |
| * * * RETRACTED AT 1601 EDT ON 9/21/00 BY ROBERT POLLOCK TO FANGIE JONES * * |
| * |
| |
| After discussion with NRC Region 3 (Geoffrey Wright), it was determined that |
| this event was not reportable as the source was not involved, safely stored |
| at all times, and the problem was only with the electronics. This event |
| notification is retracted. |
| |
| The R3DO (Bruce Burgess) and the NMSS EO (John Greeves) has been informed. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37330 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 17:57[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/15/2000|
+------------------------------------------------+EVENT TIME: 15:05[EDT]|
| NRC NOTIFIED BY: JESSE JAMES |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 15 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUALLY SCRAMMED THE REACTOR AFTER ENTERING THE RESTRICTIVE AREA OF THE |
| POWER TO FLOW MAP. |
| |
| On September 15, 2000 at Peach Bottom Atomic Power Station, Unit 2 was |
| manually scrammed per operating procedure during turbine testing in |
| preparation for the refuel outage. |
| |
| The manual scram was due to entering restricted area of the power to flow |
| map from Technical Specification 3.4.1, after the trip of the "2B" |
| recirculation pump. All rods fully inserted and the reactor was shutdown. |
| Reactor level during the scram lowered to 0" and a Group II and III primary |
| and secondary containment isolation was received. The isolations functioned |
| as designed. The plant is stable in hot shutdown with the main condenser as |
| a heat sink and the feedwater system is in service for level control. No |
| radioactive release or Emergency Core Cooling System injection occurred |
| during the scram. |
| |
| The turbine was tripped in accordance with the refuel outage plan when the |
| recirculation pump tripped. The plan was to perform turbine testing and |
| then to manually scram the reactor at the same power level. |
| |
| The reactor was manually scrammed less than one minute after entering the |
| restricted area of the power to flow map. No power oscillations were seen. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1715 EDT ON 9/21/00 BY ANDREW WINTER TO FANGIE JONES * * |
| * |
| |
| "On September 15, 2000 PBAPS reported that Unit 2 was manually scrammed in |
| accordance with operating instructions during turbine testing. The report |
| identified that the manual scram was initiated based on entering the |
| restricted area of the power to flow map after the tripping of the 2B |
| Recirculation Pump. This notification is being retracted based on the |
| following: |
| |
| "NUREG 1022 Revision 1 specifically states that 'The Commission is |
| interested both in events where an ESF was needed to mitigate the |
| consequences (whether or not the equipment performed properly) and events |
| where an ESF actuated unnecessarily....This indicates an intent to require |
| reporting actuations of features that mitigate the consequences of |
| significant events.' Therefore, the following is an analysis of these two |
| underlying reasons for reporting ESF actuations: |
| |
| 1. The need for the ESF to mitigate the consequences of an event: |
| |
| The September 15, 2000 PBAPS manual scram was initiated because the plant |
| operator made a conservative decision in accordance with station procedures |
| to initiate a reactor scram. At the time this decision was made, the plant |
| conditions were approximately 16 percent power and 24 percent core flow. |
| Although this condition is close to an operational limit conservatively |
| established by the licensee and the operator made the correct decision to |
| commence the plant shutdown, the ESF actuation was not necessary to mitigate |
| the consequences of this evolution. Moreover, plant conditions were not |
| changing in a direction that would have required the manual scram to |
| mitigate the consequences of significant events. |
| |
| 2. Events where an ESF actuated unnecessarily: |
| |
| The actuation of a manual scram and the subsequent PCIS Group II and Ill |
| actuations were part of a preplanned shutdown for the commencement of the |
| PBAPS Unit 2's thirteenth refueling outage (2R13) and were necessary to |
| complete the plant shutdown. The decision to insert the manual scram in |
| accordance with station procedures, resulted in the preplanned shutdown |
| commencing slightly early. Therefore, the ESP did not actuate unnecessarily |
| since it was already planned to shutdown the plant by inserting a manual |
| scram. |
| |
| "Therefore, based on the above discussion, this event is not reportable |
| because the manual scram resulted from and was, in accordance with the |
| licensee's procedure, and part of a preplanned sequence of reactor |
| operation." |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (William Ruland) |
| has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37358 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/20/2000|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 17:51[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/20/2000|
+------------------------------------------------+EVENT TIME: 16:05[CDT]|
| NRC NOTIFIED BY: RYAN RODE |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT OUTSIDE 10 CFR PART 50 APPENDIX R DESIGN BASIS DUE TO PROCEDURAL |
| ISSUES |
| |
| "During the final review of the new Appendix R rebaselining project, it was |
| discovered that the refueling water storage tank (RWST) inventory could be |
| lost if AOP 10A, 'Safe Shutdown-Local Control' and AOP 10B 'Safe to Cold |
| Shutdown in Local Control' were performed as written. The postulated event |
| occurs during an Appendix R fire where SI-851(RHR pump suction from |
| containment sump B) encounters a spurious open signal, causing the RWST to |
| drain via backflow into containment. The procedures do not address this |
| potential failure early enough into the event to preclude a potential loss |
| of RWST inventory. This puts Point Beach Nuclear Power Plant outside of its |
| design basis because 10CFR50 Appendix R Section III.L.2.b performance goals |
| might not be met for the above scenario." |
| |
| The NRC resident inspector will be informed of this notification by the |
| licensee. |
| |
| * * * UPDATE AT 1424 EDT ON 9/21/00 BY RYAN RODE TO FANGIE JONES * * * |
| |
| "This is an update to Event Notification 37358. That notification reported a |
| procedural deficiency involving AOP 10A, 'Safe Shutdown - Local Control' and |
| AOP 10B. 'Safe to Cold Shutdown in Local Control,' in the event of a |
| postulated Appendix R fire which results in a spurious open signal to the |
| SI-851A/B valves, 'RHR Pump Suction from Containment Sump B.' This |
| notification discussed the concern with this spurious valve opening |
| occurring during AOP 10A, which was a potential loss of RWST inventory to |
| the containment sump through the SI-856A/B, 'RHR Pump Suctions From RWST,' |
| valves. |
| |
| "Although appropriately identified in the License's condition report, this |
| notification did not include a discussion of the concern identified during |
| conduct of procedure AOP 10B. Specifically, since no action is specified to |
| verify that the SI-851 A/B valves are closed in either AOP 10A or AOP 10B, |
| in the event of the Appendix R fire which results in the spurious opening of |
| those valves, when the RHR system is aligned for normal recirculation during |
| the cooldown, the RCS inventory could be reduced by leakage through the open |
| SI-851 valve to the containment sump. As mentioned in the original event |
| notification, 10 CFR 50 Appendix R Section III.L.2.b requires the |
| performance goal for maintaining RCS level within the level indication in |
| the pressurizer be met. The procedures as written do not assure this |
| performance goal would be met and are reported as a potential condition that |
| is outside the Appendix R design basis." |
| |
| The licensee notified the NRC Resident Inspector. The R3DO (Bruce Burgess) |
| has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37359 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 09/21/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 06:51[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 09/21/2000|
+------------------------------------------------+EVENT TIME: 06:00[EDT]|
| NRC NOTIFIED BY: LUCAS |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|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 96 Power Operation |96 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE DRIVEN EMERGENCY FEED PUMP DISCHARGE VALVE WAS DISCOVERED LOCKED. |
| |
| The turbine driven Emergency Feed pump discharge valve (XV601036-EF) was |
| discovered locked closed instead of locked open as required. This condition |
| rendered the turbine driven Emergency Feed pump inoperable. The valve was |
| last operated on 8/4/00. During the period when the discharge valve was |
| closed, both diesels had been removed from service for maintenance. The "A" |
| D/G was removed from service between 9/5/00 - 9/6/00 and the "B" D/G was |
| removed from service between 9/19/00 - 9/20/00. The licensee is |
| investigating the cause. |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37360 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MARYLAND DEPART. OF THE ENVIRONMENT |NOTIFICATION DATE: 09/21/2000|
|LICENSEE: D W KOZERA INC |NOTIFICATION TIME: 09:48[EDT]|
| CITY: BALTIMORE REGION: 1 |EVENT DATE: 09/20/2000|
| COUNTY: STATE: MD |EVENT TIME: 14:30[EDT]|
|LICENSE#: MD0514901 AGREEMENT: Y |LAST UPDATE DATE: 09/21/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM RULAND R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MANLEY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST TROXLER MOISTURE DENSITY GAUGE REPORTED TO THE MARYLAND DEPARTMENT OF |
| THE ENVIRONMENT (MDE) |
| |
| Maryland licensee, D W Kozera Inc. of Baltimore, Md. lost a Troxler moisture |
| density gauge model 3430 serial # 25607 in Adamstown, Md. The gauge was |
| missing from the back of a flat bed truck , which had its tailgate down, |
| that was being driven around the Greenhill Manor Residential subdivision(New |
| Design Rd & Union Ridge Rd in Fredrick City). The gauge, which apparently |
| fell out of the back of the truck, was not in its case and the source rod |
| was not padlocked. The source (7.2 millicuries of cesium 137 and 39.7 |
| millicuries of americium 241), as far as they know, was in the shielded |
| position and has not been found. MDE has conducted an initial investigation |
| and it appears that they may issue a press release. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37361 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/21/2000|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 16:07[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/21/2000|
+------------------------------------------------+EVENT TIME: 15:30[EDT]|
| NRC NOTIFIED BY: JOHN POPIELARSKI |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE EMERGENCY SIRENS IN DEGRADED CONDITION |
| |
| "On September 21, 2000 at 1530, it was identified that at least 17 of Peach |
| Bottom's 97 Emergency Offsite Sirens were in a degraded condition. The exact |
| cause of the degraded sirens is not known at this time, but the ability of |
| the licensee to detect the degraded sirens has been compromised due to poor |
| maintenance practices. A plan is being developed and implemented to repair |
| the degraded sirens and appropriate interim compensatory measures are being |
| put in place to compensate for the degraded condition." |
| |
| An investigation is underway into this matter. The contractor responsible |
| for the siren maintenance has no other responsibilities on site. |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37362 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/21/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:15[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/21/2000|
+------------------------------------------------+EVENT TIME: 11:38[CDT]|
| NRC NOTIFIED BY: DONALD CHASE |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
|AIND 50.72(b)(2)(iii)(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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSSIBILITY THAT BOTH DIVISION 1 AND 2 DIESEL GENERATORS WERE INOPERABLE FOR |
| 9 HOURS |
| |
| "This condition deals with a past Reportability issue. During a condition |
| report review for Functional Failure/Maintenance Preventable Functional |
| Failure determination (FF/MPFF), River Bend has determined that both Standby |
| Diesel Generators may have been inoperable at the same time. |
| |
| "A failure in a light socket related to the Division I Diesel Generator |
| created a functional failure in that during a seismic event, the breaker |
| logic for the Division I diesel generator output breaker could have been |
| affected in such a way that the breaker would not close. The failed light |
| socket was identified and corrected on 9/5/00 as part of work to replace the |
| light bulb. Since the MAI on the light bulb failure was written on 8/22/00, |
| it is assumed that the socket failure occurred at that time. |
| |
| "During the same time period, a lube oil leak developed on the Division II |
| oil supply which has been determined to be a functional failure. The damaged |
| oil line was replaced on 8/30/00. |
| |
| "Therefore, based on the functional failure determinations, there is an |
| overlapping period of approximately 9 hours that the Division I and II |
| diesel generators may not have been capable of performing their design bases |
| function. |
| |
| "This report is being made based on the information available at this time. |
| River Bend will continue to evaluate the condition associated with the |
| potential Division I inoperability and will assess the reportability of this |
| condition further based on the results of that evaluation." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37363 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/21/2000|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 19:09[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/19/2000|
+------------------------------------------------+EVENT TIME: 07:30[PDT]|
| NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 09/21/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO A SULFURIC ACID LEAK CONTAINED ON SITE |
| |
| "This 4-hour telephone notification is being provided in accordance with |
| 10CFR50.72(b)(2)(vi) for notification of other government agencies. For the |
| event below, on September 19, 2000, at 0920 PDT, SCE notified the Department |
| of Environmental Health and the Office of Emergency Services (OES Incident |
| number 00-4232). This notification was delayed due to an internal |
| miscommunication. |
| |
| "On September 19, 2000, at about 0730 PDT, control room personnel were |
| notified of a sulfuric acid leak from the High Flow Makeup Demineralizer |
| Bulk Acid Storage Tank. The leak was from a gasket located between level |
| transmitter 2/3LT5045 and isolation valve AST-38. The isolation valve was |
| closed and the leak stopped. All acid (estimated to be about 650 gallons) |
| was contained within the tank's bermed area and then routed to the waste |
| neutralization sump. The entire sump contents (about 2,500 gallons of |
| sulfuric acid and water) were removed for disposal off-site. This occurrence |
| was not a significant impact to the environment and did not hamper site |
| personnel in the performance of their duties necessary for safe operation. |
| |
| "At the time of this occurrence, both Units 2 and 3 were operating at about |
| 100 percent power; Unit 1 remains permanently defueled. SCE will notify the |
| NRC resident inspectors about this notification and will provide them with a |
| copy of this report." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 04:26[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 04:00[EDT]|
| NRC NOTIFIED BY: HAMM/SCHALL |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |THOMAS DECKER R2 |
|10 CFR SECTION: |BILL BATEMAN NRR |
|AAEC |JOSEPH GIITTER IRO |
| |LUIS REYES R2 |
| |HEYMAN FEMA |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FIRE IN THE PROTECTED AREA LASTING GREATER THAN 10 MINUTES RESULTING IN A |
| REACTOR SCRAM. |
| |
| AN UNUSUAL EVENT WAS DECLARED @ 0400 DUE TO A FIRE IN THE MAIN TRANSFORMER |
| THAT LASTED >10 MINUTES. OFF SITE FIRE DEPARTMENT WAS CALLED IN TO RESPOND |
| AND THE FIRE WAS EXTINGUISHED WITHIN 14 MINUTES, HOWEVER THE PLANT STILL |
| REMAINS IN THE UNUSUAL EVENT. A REACTOR SCRAM FROM 100% POWER OCCURRED |
| FOLLOWING A MAIN TURBINE GENERATOR LOCKOUT WHICH RESULTED FROM THE |
| TRANSFORMER FAILURE. THERE WERE SOME ERRONEOUS INDICATIONS OF CONTROL ROD |
| POSITION, BUT ALL RODS APPEAR TO BE FULLY INSERTED. THERE WAS NO ECCS |
| ACTUATION AND NO SAFETY RELIEF VALVES LIFTED DURING THIS EVENT. THE PLANT |
| DID NOT LOSE OFFSITE POWER DUE TO THE AUTO TRANSFER FROM THE MAIN |
| TRANSFORMER TO THE STARTUP AUXILIARY TRANSFORMER. THE DIESELS AUTOMATICALLY |
| STARTED AND WERE STILL RUNNING AT THE TIME OF THIS REPORT. GROUP 2,6 AND 8 |
| ISOLATIONS WERE ALSO RECEIVED. THERE WAS A PROBLEM WITH THE STARTUP LEVEL |
| CONTROL VALVE WHEN THEY REESTABLISHED REACTOR FEED PUMP, VALVE DID NOT OPEN |
| PROPERLY SO THEY HAD TO USE THE BACKUP PATH IN THE FEED SYSTEM. AS A |
| RESULT OF THIS THE LEVEL WENT LOW ENOUGH TO RECEIVE A SECOND REACTOR SCRAM |
| SIGNAL. THE CONDENSER IS BEING USED AS THE HEAT SINK AND THE PLANT IS |
| STABLE. THE CAUSES FOR THE TRANSFORMER FIRE AND THE ERRONEOUS CONTROL ROD |
| INDICATIONS ARE BEING INVESTIGATED. THERE HAVE BEEN NO INJURIES REPORTED |
| AND IT IS NOT KNOWN AT THIS TIME IF A PRESS RELEASE WILL BE ISSUED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| * * * UPDATE ON 9/22/00 @ 0528 BY HAMM TO GOULD * * * |
| |
| THE NOUE WAS TERMINATED AT 0512 DUE TO THE FIRE BEING COMPLETELY |
| EXTINGUISHED. |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. |
| THE EO(BATEMAN), RDO(DECKER), FEMA (HEYMAN) AND IRO(GIITTER) WERE |
| NOTIFIED. |
| |
| SEE EVENT # 37365. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37365 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 06:37[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 03:40[EDT]|
| NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|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 |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT HAD ESF ACTUATIONS DURING A REACTOR SCRAM |
| |
| A main turbine trip resulted in a reactor scram. As expected following the |
| scram, reactor water level dropped to the actuation setpoint for Groups 2, 6 |
| and 8 isolations. The main turbine trip apparently resulted from a fire in B |
| main power transformer. The fire was reported to the control room at 0346. |
| The site fire brigade responded and the fire was extinguished at 0402 using |
| the automatic deluge system and fire hoses. Offsite fire department |
| assistance was requested but was not needed to extinguish the fire. An |
| Unusual Event was declared at 0400 in accordance with the plant's emergency |
| procedures. The Unusual Event was terminated at 0512 based on the plant |
| being in a stable condition. During the transient the startup level |
| control did not control level in the automatic mode. Reactor level was |
| controlled using a feedwater bypass valve. A second reactor scram signal |
| was generated due a low reactor water level signal received while manual |
| level control was being established, however all rods were already tully |
| inserted. The plant emergency diesels started but did not load. Offsite |
| power remained available throughout the event. The NRC Resident Inspector |
| was notified. |
| |
| HOO Note: see event # 37364 |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021