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Event Notification Report for January 13, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/12/2000 - 01/13/2000

                              ** EVENT NUMBERS **

36552  36580  36581  36582  36583  36584  36585  36586  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36552       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/30/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/30/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:30[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/12/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRUCE BURGESS        R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTE:  THIS EVENT IS A CONTINUATION OF EVENT #35790.                         |
|                                                                              |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified   |
| that during walkdowns of the High Pressure Fire Water System in C-337, a     |
| total of 13 corroded sprinkler heads were discovered in System B-2.  The     |
| system was declared inoperable and actions were taken as required by the     |
| technical safety requirement.  The PSS determined that an update to this     |
| event report is required.                                                    |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
|                                                                              |
| * * * UPDATE 2233EST ON 1/12/00 FROM ERIC WALKER TO S. SANDIN * * *          |
|                                                                              |
| At 0910 on 1/12/00 the Plant Shift Superintendent (PSS) was notified that    |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337,   |
| two adjacent corroded heads were discovered on system B-10. Per Engineering  |
| Notice C-822-99-047 Rev. 2, the criteria necessary for system operability    |
| was not being met. The system was declared Inoperable and actions were taken |
| as required by the TSR. The PSS determined that an update to this event      |
| report is required.                                                          |
|                                                                              |
| It has been determined that this event is reportable under 10CFR76.120(c)(2) |
| as an event in which equipment is disabled or fails to function as           |
| designed.                                                                    |
|                                                                              |
| The NRC Resident Inspector has been notified of this event. Notified         |
| R3DO(Clayton) and NMSS(Haughney).                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36580       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/11/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 22:26[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/11/2000|
+------------------------------------------------+EVENT TIME:        17:52[CST]|
| NRC NOTIFIED BY:  STEVE WHEELER                |LAST UPDATE DATE:  01/12/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| POSTULATED CONDUCTOR-TO-CONDUCTOR SHORT IN FIRE PUMP CONTROL CIRCUITRY COULD |
| INHIBIT THE ABILITY OF THE PLANT TO SAFELY SHUT DOWN FOLLOWING A FIRE.       |
|                                                                              |
| "During preparation of the permanent plant modification to replace a         |
| Temporary Modification associated with LER 96-009-03, another configuration  |
| was found that could inhibit the ability of the plant to safely shutdown     |
| following a fire. For an Alternate Shutdown Fire (10 CFR 50 Appendix R       |
| Section III.L) in the Cable Spreading Room fire area, the Diesel Fire pump   |
| is relied upon to provide emergency backup gland seal water to the essential |
| service water pumps. A fire scenario in the cable spreading room assumes of  |
| a loss of offsite power (which disables the normal gland water supply) as    |
| well as concurrent hot shorts which disable the emergency gland seal water   |
| supply MOV's (because their control cables are routed through the Cable      |
| Spreading Room). A multi-conductor cable located in the Cable Spreading Room |
| carries 24 VDC start control circuits and 120 VAC annunciator power          |
| circuits. The postulated fire scenario requires the assumption that the fire |
| could cause a conductor to conductor short within this cable such that the   |
| 24 VDC circuits would be energized by the 120 VAC power. This would disable  |
| the automatic starting capability of the diesel fire pump (the currently     |
| credited emergency backup gland seat water).  A fire watch has been posted   |
| in the Cable Spreading Room as a compensatory measure. The Cable Spreading   |
| Room fire area is the only fire area affected by this configuration. The     |
| operator's ability to recognize and correct a loss of gland water to the     |
| Service Water pumps would not be impaired. Sufficient procedural guidance is |
| provided for the post-fire restoration of the essential service water pumps  |
| such that loss of gland seal water would have been detected prior to service |
| water pump damage. Fire fighting activities would have immediately indicated |
| loss of the fire pump. A modification to separate the starting circuits from |
| the power circuits is being pursued. CNS has conservatively concluded that   |
| this postulated scenario is reportable under 10CFR50. 72(b)(2)(iii)(A).      |
|                                                                              |
| "The NRC Resident Inspector has been notified."                              |
|                                                                              |
| * * * UPDATE 1833EST ON 1/12/00 FROM STEVEN JOBE TO S. SANDIN * * *          |
|                                                                              |
| "Per the requirements of 10 CFR 50.72 (c) (2), the licensee is providing the |
| following additional information.                                            |
|                                                                              |
| "The 120 VAC annunciator power circuits referred to in the initial report    |
| are more appropriately described as indicating lamp power circuits.          |
|                                                                              |
| "As additional clarification, the diesel fire pump running capability would  |
| be disabled along with the automatic starting capability.                    |
|                                                                              |
| "Based on further investigation, the licensee has determined that            |
| insufficient time exists to recognize and correct the loss of gland seal     |
| water prior to the onset of service water pump damage.                       |
|                                                                              |
| "The compensatory measures described in the initial report (posting of fire  |
| watch) are still in place. These measures, in conjunction with the defense   |
| in depth fire protection program, are adequate to ensure the ability of the  |
| plant to safely shutdown following a fire, and are consistent with the       |
| facility license and the guidance of Information Notice 97-78 'Inadequate or |
| Inappropriate Interim Fire Protection Compensatory Measures."                |
|                                                                              |
| "Evaluation of this postulated scenario is ongoing and additional action     |
| will be taken as appropriate.                                                |
|                                                                              |
| "The Senior Resident lnspector has been notified."                           |
|                                                                              |
| Notified R4DO(Shackelford).                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36581       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEST-CON                             |NOTIFICATION DATE: 01/12/2000|
|LICENSEE:  TEST-CON                             |NOTIFICATION TIME: 12:19[EST]|
|    CITY:  DANBURY                  REGION:  1  |EVENT DATE:        01/12/2000|
|  COUNTY:                            STATE:  CT |EVENT TIME:        08:00[EST]|
|LICENSE#:  06-30240-01           AGREEMENT:  N  |LAST UPDATE DATE:  01/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE DOERFLEIN   R1      |
|                                                |KEVIN RAMSEY         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHIN OKWUKA                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN HUMBOLT MOISTURE DENSITY GAUGE                                        |
|                                                                              |
| THE RADIATION SAFETY OFFICER (RSO) FOR TEST-CON , LOCATED AT 16 E. FRANKLIN  |
| IN DANBURY, CT 06810, REPORTED THAT A HUMBOLT MODEL 5001 MOISTURE DENSITY    |
| GAUGE, SERIAL NUMBER 1967,  CONTAINING TWO (2) RADIOACTIVE SOURCES [8 mCi    |
| Cs-137 AND 40 mCi Am-241:Be) WAS STOLEN FROM A VEHICLE PARKED ON MORRIS AVE  |
| IN BRONX, NY.  THE DEVICE WAS REMOVED BETWEEN 0500 AND 0700 HOURS ON 1/12    |
| FROM THE TRUNK OF A HYUNDAI AUTO WITH NO VISIBLE SIGN OF FORCED ENTRY.       |
|                                                                              |
| THE LICENSEE INFORMED NRC REGION I AND WILL FILE A POLICE REPORT WITH THE NY |
| CITY PD.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36582       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 01/12/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 14:52[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        01/12/2000|
+------------------------------------------------+EVENT TIME:        14:19[EST]|
| NRC NOTIFIED BY:  TOM EGAN                     |LAST UPDATE DATE:  01/12/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNPLANNED INOPERABILITY OF HIGH PRESSURE CORE SPRAY DUE TO REQUIRED          |
| SURVEILLANCE TESTING NOT PERFORMED (TECH. SPEC. 4.3.3.3)                     |
|                                                                              |
| "THE REQUIRED RESPONSE TIME TESTING OF HIGH PRESSURE CORE SPRAY SYSTEM       |
| ACTUATION INSTRUMENTATION WAS NOT PERFORMED WITH THE TECH SPEC SURVEILLANCE  |
| FREQUENCY.  THE INSTRUMENTATION HAS BEEN DECLARED INOPERABLE.  THE HIGH      |
| PRESSURE CORE SPRAY HAS BEEN DECLARED INOPERABLE PER TECH SPEC 3.3.3 ACTION  |
| 36b.                                                                         |
|                                                                              |
| "WITH HIGH PRESSURE CORE SPRAY INOPERABLE, ENTERED TECH SPEC 3.5.1.c.1 (14   |
| DAY LCO)."                                                                   |
|                                                                              |
| THIS IS AN 18-MONTH SURVEILLANCE WHICH WAS LAST PERFORMED MARCH 1997.  THE   |
| LICENSEE IDENTIFIED THAT AN INCORRECT SURVEILLANCE INTERVAL WAS USED IN THE  |
| TRACKING SYSTEM.  THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36583       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 01/12/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 17:26[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/12/2000|
+------------------------------------------------+EVENT TIME:        15:15[CST]|
| NRC NOTIFIED BY:  MARK S. FELTNER              |LAST UPDATE DATE:  01/12/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JEFF SHACKELFORD     R4      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TRANSPORT OFFSITE OF POTENTIALLY CONTAMINATED INJURED EMPLOYEE               |
|                                                                              |
| "At 1515 on 1/12/2000, an injured contract employee at River Bend Station    |
| was transported offsite to the West Feliciana Hospital for medical           |
| treatment. The individual was erecting scaffolding in the Turbine Building,  |
| fell approximately 20 feet and sustained injuries. The individual was        |
| working inside the Controlled Access Area, but not inside a Contaminated     |
| Area, and a thorough survey for radioactive contamination could not be       |
| performed prior to transport. Therefore, the individual is considered to be  |
| potentially contaminated.                                                    |
|                                                                              |
| "In accordance with plant administrative procedures. a radiation protection  |
| technician is accompanying the ambulance to the hospital and a second        |
| radiation protection technician has been dispatched to the hospital as       |
| well."                                                                       |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
|                                                                              |
| * * * UPDATE 2057EST ON 1/12/2000 FROM ROHM TO S. SANDIN * * *               |
|                                                                              |
| "The injured contract employee has been verified not contaminated.           |
| Preliminary medical evaluation revealed no life threatening injuries."       |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified                  |
| R4DO(Shackelford).                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36584       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STATE OF CALIFORNIA                  |NOTIFICATION DATE: 01/12/2000|
|LICENSEE:  GOFFMAN, McCORMICK & URBAN           |NOTIFICATION TIME: 19:14[EST]|
|    CITY:  RANCHO SANTA MARGARITA   REGION:  4  |EVENT DATE:        01/10/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|
|LICENSE#:  3674 (CA)             AGREEMENT:  Y  |LAST UPDATE DATE:  01/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JEFF SHACKELFORD     R4      |
|                                                |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DONALD BUNN                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN CAMPBELL PACIFIC NUCLEAR MOISTURE DENSITY GAUGE                       |
|                                                                              |
| ON 1/10, A CAMPBELL PACIFIC NUCLEAR (CPN) MOISTURE DENSITY GAUGE MODEL M,    |
| SERIAL NUMBER 36076956, WAS STOLEN FROM A VEHICLE IN IRVINE, CA.  THE GAUGE  |
| CONTAINS TWO (2) SOURCES (9 mCi Cs-137 AND 40 mCi Am-241: Be).  THE          |
| LICENSEE, GOFFMAN, McCORMICK AND URBAN, INC. LOCATED IN RANCHO SANTA         |
| MARGARITA, CA, REPORTED THE LOSS TO THE STATE OF CALIFORNIA RADIOLOGIC       |
| HEALTH BRANCH (INCIDENT #011100) AND THE IRVINE POLICE DEPARTMENT.  A REWARD |
| HAS BEEN OFFERED IN THE LOCAL NEWSPAPER.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36585       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 02:55[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        00:59[CST]|
| NRC NOTIFIED BY:  STEWART DRESSER              |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|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     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SWITCHYARD FAULT RESULTED IN MAIN GENERATOR TRIP/TURBINE TRIP/REACTOR TRIP.  |
|                                                                              |
| At 0059CT a Reactor Trip occurred on Unit 2.  A fault in the switchyard      |
| resulted in a Main Generator Trip which caused a Turbine Trip/Reactor Trip.  |
| All rods fully inserted into the core. All other systems responded per       |
| design with the following exceptions:                                        |
|                                                                              |
| 1).   Unit 1/Unit 2 Containment Ventilation Actuation occurred (caused by    |
| electrical spike in the switchyard). This is not an ESF Actuation because    |
| all the Containment Ventilation Isolation valves were already closed.        |
|                                                                              |
| 2).  Fuel Handling Building Ventilation ESF Actuation occurred (caused by    |
| the electrical spike in the switchyard).                                     |
|                                                                              |
| 3).  "A" Train Main Control Room Makeup Air Filter Unit ESF Actuation        |
| occurred (caused by the electrical spike in the switchyard).                 |
|                                                                              |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are   |
| fully operable if needed. At this time the Motor Driven Auxiliary Feedwater  |
| Pump is maintaining proper Steam Generator Water Levels with Tave being      |
| maintained at a no load temperature of 557 degrees F.                        |
|                                                                              |
| Switchyard fault is being investigated.                                      |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36586       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 04:21[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        03:26[EST]|
| NRC NOTIFIED BY:  JIM BURGESS                  |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|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                                   
+------------------------------------------------------------------------------+
| ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR 17 MINUTES DUE TO LOW DIFFERENTIAL |
| PRESSURE BETWEEN  CONTROL ROOM AND THE AUXILIARY BUILDING.                   |
|                                                                              |
| A LOW CONTROL ROOM VENTILATION SYSTEM DIFFERENTIAL PRESSURE WAS DISCOVERED   |
| WHILE CONTROL ROOM VENTILATION SYSTEM AND AUXILIARY BUILDING VENTILATION     |
| SYSTEM COMPENSATORY ACTION IN EFFECT DUE TO AUXILIARY BUILDING VENTILATION   |
| SYSTEM WORK.  LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 AT 0326ET.  AT  |
| 0333ET THE LICENSEE SECURED "2A" AUXILIARY BUILDING VENTILATION FILTER       |
| EXHAUST FAN.  TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT 0343ET AFTER       |
| CONTROL ROOM DIFFERENTIAL PRESSURE WAS VERIFIED ABOVE MINIMUM LIMIT.         |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
+------------------------------------------------------------------------------+