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Event Notification Report for September 19, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/18/2000 - 09/19/2000
** EVENT NUMBERS **
37307 37333 37338 37339 37340 37341 37342 37343 37344 37345 37346
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37307 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COMMONWEALTH OF KENTUCKY |NOTIFICATION DATE: 09/11/2000|
|LICENSEE: COMMONWEALTH OF KENTUCKY |NOTIFICATION TIME: 17:21[EDT]|
| CITY: LEXINGTON REGION: 2 |EVENT DATE: 09/11/2000|
| COUNTY: STATE: KY |EVENT TIME: 06:00[CDT]|
|LICENSE#: 201-142-51 AGREEMENT: Y |LAST UPDATE DATE: 09/18/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KERRY LANDIS R2 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: VICKI JEFFS | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN GAUGE |
| |
| "On September 11, 2000, Fuller, Mossbarger, Scot and May Engineers, Inc., |
| reported a stolen moisture/density gauge. The gauge was a Troxler 3440, |
| serial number 24606, containing an 8 millicurie cesium-137 and a 40 |
| millicurie americium-241 source. |
| |
| "The gauge was stolen sometime between 12:00 am. and 6:00 a.m. on September |
| 11 from an employee's residence located in Lexington, KY. The police have |
| been notified. The employee had stored the gauge, in its transport |
| container, in his garage. He put the gauge, in its transport container in |
| the bed of his truck at about midnight in order to be ready to leave for the |
| job Site the next morning. One of the owners of the company stated that the |
| container was locked to the bed of the truck with a chain and padlock. The |
| thief used a hacksaw to cut the chain and remove the transport container |
| with the gauge inside. |
| |
| "The owner stated he believed the source rod to also be locked and that the |
| employee would have still have the keys to this lock." |
| |
| * * * UPDATE 1133 9/18/2000 FROM VICKI JEFFS VIA FACSIMILE * * * |
| |
| "The gauge, Troxler 3440, S/N 24606, was found, undamaged, on the side of |
| the road. The licensee now has possession of it. Licensee was cited for |
| improper gauge storage." |
| |
| Notified R2DO (Cahill). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37333 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 09/16/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 23:43[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 09/16/2000|
+------------------------------------------------+EVENT TIME: 23:15[EDT]|
| NRC NOTIFIED BY: LEON GAGNE |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |STEPHEN CAHILL R2 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|AAEC |FRANK CONGEL IRO |
| |AUSTIN FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - HURRICANE WARNING |
| |
| The licensee declared an unusual event at 2315 due to a hurricane warning |
| being declared for Citrus County, Florida. Further actions will be taken |
| depending upon the direction Hurricane Gordon takes in the next 24 hours. |
| The licensee intends to remain at power and will continue to evaluate this |
| storm. |
| |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector. |
| |
| * * * UPDATE AT 0049 ON 9/18/00 BY GAGNEY, RECEIVED BY WEAVER * * * |
| |
| The licensee exited the unusual event at 0035. The hurricane warning is no |
| longer in effect. The storm caused no damage at the plant and it continues |
| to operate at full power. |
| |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector. |
| |
| HOO notified FEMA (CIBOCH); RDO (CAHILL); EO (ZWOLINSKI); IRO(CONGEL) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37338 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 06:16[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 04:50[EDT]|
| NRC NOTIFIED BY: KEITH POPE |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEPHEN CAHILL R2 |
|10 CFR SECTION: | |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF RHR (RECIRC CAPABILITY) INOPERABLE FOR APPROXIMATELY SEVEN |
| HOURS |
| |
| "While placing RHR Train'B' in shutdown cooling during a refueling outage |
| the pump minimum flow valve did not close as expected. Investigation |
| revealed that the mini-flow transmitter 1 FIS-0611 was isolated causing the |
| valve 1 FV0611 to remain open with RHR flow in excess of setpoint that would |
| cause the valve to close. Work was performed on August 29, 2000, to |
| calibrate this transmitter. On September 9, 2000, RHR Train 'A' seal |
| cooler was isolated for maintenance rendering both trains of RHR inoperable |
| for 6 hours and 54 minutes. The Cold leg injection capability from RHR |
| Train 'A' remained available during this time. The Cold leg recirculation |
| capability during these inoperabilities was not available. This would have |
| required entry into T. S. 3.0.3. |
| |
| "RHR Train 'B' mini-flow transmitter 1FIS-0611 was discovered isolated |
| causing the valve 1FV0611 to remain open with RHR flow in excess of setpoint |
| that would cause the valve to close. The transmitter has been returned to |
| service and the valve 1 FV0611 is operating properly." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37339 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 06:47[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 05:03[EDT]|
| NRC NOTIFIED BY: MICKLOW |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R N 0 Startup |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING PLANT SHUTDOWN |
| |
| "A plant shutdown was in progress for a refueling outage, RCS pressure was |
| at 2236 psig, Tavg at 541F. Power as indicated on intermediate range |
| channels N35 & N36 was 4 x10 minus 12 amps and 7.5 x 10 minus 11 amps, |
| respectively. Control room operator was in the process of driving control |
| rods to 5 steps on Bank A, when P-6 permissive reset. Coincident with P-6 |
| reset, a control power fuse blew on IR channel N-36, causing a Rx trip from |
| 1/2 IR channels high. All rods fully inserted on the trip. Cause of the |
| blown fuse is under investigation and plant shutdown will continue using |
| normal operating procedures." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37340 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NORTH CAROLINA DIV OF RAD HEALTH |NOTIFICATION DATE: 09/18/2000|
|LICENSEE: WATAUGA REGIONAL MEDICAL CENTER |NOTIFICATION TIME: 10:12[EDT]|
| CITY: BOONE REGION: 2 |EVENT DATE: 09/17/2000|
| COUNTY: STATE: NC |EVENT TIME: 12:00[EDT]|
|LICENSE#: 095-0491-2 AGREEMENT: Y |LAST UPDATE DATE: 09/18/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |STEPHEN CAHILL R2 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFFRIES | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT |
| |
| A member of the cleaning staff at Watauga Regional Medical Center in Boone, |
| NC removed the linens from the room of an I -131 patient in isolation. The |
| mistake was caught by one of the nuclear medicine technicians and the linens |
| were retrieved from the linen company. There was no spread of |
| contamination. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37341 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 13:41[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 11:50[CDT]|
| NRC NOTIFIED BY: OSCAR PIPKINS |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT OUTSIDE DESIGN BASIS OF FIRE PROTECTION PROGRAM |
| |
| "During review of the plant Cable and Conduit List (CCL) database, it was |
| observed that six essential cables were not listed as requiring fire wrap |
| and the cables are not wrapped in the field. The cable, with one exception, |
| is listed in the safe shutdown analysis as required for hot and cold safe |
| shutdown, but are not provided with Appendix R separation per 10CFR50 |
| Appendix R Section IIIG. The cables are located in Room 299 on the +46 ft |
| elevation of the Reactor Auxiliary Bldg (RAB) in Fire Area RAB 2. The |
| condition has existed since plant original construction. At the time of |
| discovery, the plant is operating at 100% Reactor Power. The cables were |
| immediately listed as impaired, and compensatory actions were established |
| (hourly fire watches). The condition has been entered into the plant |
| corrective action program (CR-WF3-2000-1088). The equipment would be |
| affected by a hypothetical fire in that fire area include the A/B Essential |
| Chillers, RAB HVAG Exhaust Fan A, RAB HVAC Equipment Room Supply Fan AH-13 |
| (3A-SA) Dampers. These components should be the protected components in the |
| fire area. The condition affects the ability to achieve safe shutdown. |
| Therefore, the condition is considered to be outside the design basis of the |
| fire protection program." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37342 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 15:26[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 14:15[CDT]|
| NRC NOTIFIED BY: CARL EHRHARDT |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|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 13 Power Operation |13 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MAIN GENERATOR PARTIAL LOAD REJECT MAY NOT CAUSE REACTOR SCRAM AS ASSUMED |
| |
| "During evaluation of the data from a recent Reactor scram (Event #37325 on |
| 9/15/00) a possible unanalyzed condition was found. Specifically, a Main |
| Generator partial Load Reject can actuate a circuit contained in the turbine |
| controls that may not always activate a reactor scram/recirculation pump |
| down shift as required by analysis. Theoretically, with the partial load |
| reject that fails to actuate the Reactor Scram/Recirculation pump trip and |
| assuming failure of the bypass valves, MCPR limits could be affected. |
| Immediate corrective action is to change the setpoint of the EHC trip to |
| ensure that a partial load reject will result in a scram and Recirculation |
| pump transfer to slow speed." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37343 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 15:55[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/17/2000|
+------------------------------------------------+EVENT TIME: 06:20[PDT]|
| NRC NOTIFIED BY: HOWARD SMITH |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|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
+------------------------------------------------------------------------------+
| OPERATORS MANUALLY STARTED EMERGENCY CONTAINMENT AIR COOLERS |
| |
| "On September 17, 2000, at about 0620 PDT, 2-ME-201 (non-safety containment |
| normal chiller) tripped on low oil pressure. Operators began to start the |
| containment normal chiller 2-ME-202, but stopped when prestart checks |
| indicated low freon level. Because containment temperatures were slowly |
| increasing, plant operators placed the emergency containment cooler units in |
| service and started an additional containment dome air circulator. To |
| perform their ESF function, the containment emergency coolers automatically |
| actuate on safety injection actuation signal and on containment pressure, |
| but not on containment temperature. SCE considered that the emergency |
| coolers were not performing an ESF function during this occurrence, and a |
| report to the NRC was not required. |
| |
| "On September 18, 2000, at 1000 PDT, SCE determined that actuation of the |
| emergency cooler units could be considered to meet the clarification |
| provided in section 3.3.2 of NUREG-1022, Rev. 1. Therefore, SCE is |
| conservatively and voluntarily providing this report to the NRC. After |
| determining that 2-ME-202 was functional with an indicated low freon level, |
| plant operators started 2-ME-202 at about 0818 PDT, terminating this |
| occurrence. The emergency coolers and dome air circulators operated as |
| designed. At the time of this occurrence, both units 2 and 3 were operating |
| at about 100% power. Unit 1 remains permanently defueled." |
| |
| The NRC resident inspector will be informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37344 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 19:51[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 17:10[EDT]|
| NRC NOTIFIED BY: SCOTT RICHARDSON |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| ECCS PERFORMANCE POTENTIALLY IMPAIRED DUE TO VALVE CLOSURE DURING TESTING |
| |
| "During review of emergency core cooling system (ECCS) valve operability |
| test procedures, it was determined that, on one occasion in 1995 and again |
| in 1997, one safety injection (SI) system containment isolation valve (CIV) |
| was closed for valve operability testing with reactor power at or near 100%. |
| With a CIV closed, injection from the two SI pumps following a small break |
| loss of coolant accident (SBLOCA) would be directed to only two of the four |
| reactor coolant system loops. At this power level, the high head SI system |
| function of maintaining peak clad temperature (PCT) below 2200þF following a |
| SBLOCA may not be satisfied. The condition becomes worse if a single failure |
| is considered to affect one of the two SI pumps. Further evaluation of the |
| condition is in progress." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37345 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2 REGION: 4 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 19:56[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 15:09[PDT]|
| NRC NOTIFIED BY: J. W. GASTON |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 65 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DUE TO DECREASING CONDENSER VACUUM |
| |
| "At 1425 PDT the plant experienced a sudden increase in offgas flow and |
| decreasing condenser vacuum. Reactor power was reduced from 100% to 65% in |
| accordance with the plant abnormal procedures for the loss of condenser |
| vacuum. When the condenser back pressure continued to rise, a manual scram |
| was inserted. All safety systems functioned as designed. The plant is |
| currently stable in mode 3. The cause of the increase in off-gas flow is |
| currently under investigation." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37346 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/19/2000|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 01:26[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 22:30[CDT]|
| NRC NOTIFIED BY: BRIAN GRANT |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED WHILE SHUTDOWN - FAILED CONTAINMENT LEAK RATE TEST |
| |
| System Engineering reports the local leak rate test results for 3A Feedwater |
| Header Inboard and Outboard Drywell Check Valves (3-0220-58A & 3-0220-62A) |
| are indeterminate due to excessive leakage. This exceeds the containment |
| pathway leakage values allowed by Technical Specifications Primary |
| Containment Leakage Rate Testing Program. |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+