Home
> NRC Library
> Document Collections
> Reports Associated With Events
> Event Notification Reports > 2000
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. | +------------------------------------------------------------------------------+