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Event Notification Report for November 17, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/16/2000 - 11/17/2000

                              ** EVENT NUMBERS **

37524  37525  37527  37528  37529  

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|Power Reactor                                    |Event Number:   37524       |
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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 11/15/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 15:49[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/15/2000|
+------------------------------------------------+EVENT TIME:        14:22[EST]|
| NRC NOTIFIED BY:  VERITA BELLAMY               |LAST UPDATE DATE:  11/16/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|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       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MANUAL REACTOR TRIP DUE TO FAILURE OF TURBINE RUNBACK ACTUATION CIRCUITS     |
|                                                                              |
| Unit 2 experienced a turbine runback at 1410 EST.  The control room          |
| operators noticed all status lights for overpower and overtemperature delta  |
| T runback were illuminated.  The operators decided to manually trip the      |
| reactor from about 23 % rated thermal power.  The reactor trip resulted in a |
| turbine trip as expected.  Auxiliary feedwater pumps started due to low-low  |
| steam generator levels.  The unit is stable in Mode 3.                       |
|                                                                              |
| The runback bistables are locked in without having the logic bistables       |
| tripped that feed the trip circuit.  The licensee is troubleshooting the     |
| problem and the cause is unknown at this time.  The plant will remain in     |
| Mode 3 until the problem is corrected.                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE 1345EST FROM TIM HEADNON TO BOB STRANSKY * * *                  |
|                                                                              |
| The licensee is updating their report to include the following information:  |
|                                                                              |
| "On November 15, 2000, McGuire Unit 2 experienced a turbine runback which    |
| ultimately resulted in plant operators manually tripping the reactor (RPS    |
| Actuation). Following the trip, the Unit 2 Auxiliary Feedwater Pumps started |
| due to low-low steam generator levels (ESF Actuation)                        |
|                                                                              |
| "Further investigation has determined that the turbine runback was caused by |
| actuation of all four channels of over power delta temperature (OPDT) and    |
| over temperature delta temperature (OTDT) runback logic following a trip of  |
| an electrical breaker which supplies power to the logic circuitry. The       |
| turbine runback was a result of the breaker trip and was not initiated by a  |
| valid OPDT or OTDT condition. Subsequent to the turbine runback, a decision  |
| was made to manually trip the reactor. Plant equipment necessary to safely   |
| shutdown the unit operated correctly and the Unit is stable and in Mode 3.   |
| The Unit 2 Auxiliary Feedwater Pumps have been secured. Actions needed to    |
| restart Unit 2 are in progress."                                             |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R2DO(Ernstes).   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37525       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 11/15/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 19:04[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        11/15/2000|
+------------------------------------------------+EVENT TIME:        17:50[EST]|
| NRC NOTIFIED BY:  JERE FREEMAN                 |LAST UPDATE DATE:  11/16/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       1        Startup          |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL                       |
|                                                                              |
| The plant received a low water level reactor scram during turbine            |
| manipulation after 2 turbine bypass valves opened.  All systems functioned   |
| as designed.  The actual cause is not fully understood and is under          |
| investigation.                                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE 1513EST ON 11/16/00 FROM STEVE FULLER TO S. SANDIN * * *        |
|                                                                              |
| The following information was received as an update:                         |
|                                                                              |
| "On 11/15/00 at 1748 EST, Oyster Creek Nuclear Generating Station            |
| automatically scrammed on reactor low water level (as described on Event     |
| Number 37525). The station was in the process of restarting from the plant   |
| from the recent 1 SR refueling outage. The operators were in the process of  |
| securing High Pressure Turbine warm-up and preparing to perform Steam Chest  |
| warm-up. As they transitioned between these activities, the turbine bypass   |
| valves opened. As a result of the bypass valves opening, reactor water level |
| increased. The operators responded to the reactor water level transient but  |
| failed to recognize the pressure reduction. The loss of inventory resulted   |
| in a low water level reactor scram.                                          |
|                                                                              |
| "The station has conducted a transient assessment of this incident. The      |
| preliminary root cause was identified as a procedural deficiency. The        |
| Turbine System Operating Procedure did not provide the appropriate guidance  |
| for preventing the bypass valves from opening. Additionally, the operators   |
| demonstrated a lack of integrated system knowledge and response regarding    |
| the turbine controls system.                                                 |
|                                                                              |
| "Subsequent reviews of the plant data revealed that the cool down rate       |
| exceeded the plant's Technical Specification limit of 100 degrees per hour.  |
| This occurred because of the low initial power level coupled with the bypass |
| valves not being closed in a timely manner. Engineering has assessed this    |
| condition and determined that the plant response was within our design       |
| bases. Additionally, the Post Transient Review Group (PTRG) identified a     |
| potential concern regarding the operation of the reactor low water level     |
| transmitters. One of the four reactor low water level scram switches did not |
| actuate. Even though the PTRG suspected this switch didn't actuate because   |
| the decrease in reactor water level wasn't sufficient due to the low initial |
| power level, this switch was subsequently tested and operated                |
| appropriately.                                                               |
|                                                                              |
| "Following completion of the required restart activities, the plant          |
| commenced startup activities at 2:57 EST on 11/16/00. In accordance with     |
| 10CFR50.73 a Licensee Event Report will be submitted to describe this        |
| incident, the root cause, and associated corrective actions."                |
|                                                                              |
| The licensee will inform the NRC resident inspector.  Notified               |
| R1DO(Barkley).                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37527       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 11/16/2000|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 05:10[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        11/16/2000|
+------------------------------------------------+EVENT TIME:        03:23[CST]|
| NRC NOTIFIED BY:  BRAD MOORE                   |LAST UPDATE DATE:  11/16/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|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                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP ON HIGH-HIGH STEAM GENERATOR WATER LEVEL FOLLOWING A  |
| MASTER STEAM GENERATOR FEEDWATER PUMP CONTROLLER FAILURE AND SLUGGISH        |
| CONTROLS AFTER SWITCHING TO MANUAL                                           |
|                                                                              |
| The master steam generator feedwater pump controller failed low and caused   |
| feedwater pump speeds to slow down.  (Both pumps dropped to 3,200 rpm.)  In  |
| an attempt to regain feedwater pump speed and steam generator water level in |
| manual, a high-high level was reached in the 2A steam generator.  This       |
| caused a turbine trip and subsequent reactor trip.  All control rods fully   |
| inserted.  Auxiliary feedwater actuation and feedwater isolation occurred as |
| expected.  All systems functioned as required.                               |
|                                                                              |
| It was reported that the controller was sluggish after manual control was    |
| taken and that operators were not able to terminate the rising level in the  |
| 2A steam generator before the high-high level trip setpoint was reached.     |
| The lowest steam generator water level attained was approximately 27%.  The  |
| low level trip occurs at 25%.  The cause of the controller failure is        |
| currently under investigation.                                               |
|                                                                              |
| The unit is currently stable in Hot Standby.  Pressurizer heaters and        |
| sprays, normal charging and letdown, and the reactor coolant pumps are       |
| currently being utilized for primary system pressure, level, and transport   |
| control.  Secondary steam is being dumped to the main condenser, and         |
| auxiliary feedwater is supplying water to the steam generators.  All         |
| containment parameters are normal.                                           |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37528       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/16/2000|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 13:06[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/16/2000|
+------------------------------------------------+EVENT TIME:        12:15[EST]|
| NRC NOTIFIED BY:  JAMES HURCHALLA              |LAST UPDATE DATE:  11/16/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 PRESSURIZER LEVEL INSTRUMENTATION MAY NOT MEET CABLE SEPARATION       |
| CRITERIA                                                                     |
|                                                                              |
| "During development of a cable separation modification package for the       |
| upcoming 2001 Unit 1 Outage SL1-17, a re-evaluation of the Unit 1            |
| Containment Shutdown Safety Assessment was performed. The re-evaluation      |
| identified a separation issue with the cables for pressurizer level          |
| instruments LT-1110X and LT-1110Y in the annulus area.  At certain           |
| locations, these cables are not separated as required by 10 CFR Part 50      |
| Appendix R, Section lll.G.2 as required by the plant design basis as         |
| delineated in the FSAR.                                                      |
|                                                                              |
| "Fire protection for nuclear plants is based on the defense in depth concept |
| with three primary barriers - prevention, detection and control, and         |
| protection of safe shutdown capabilities. The above concern is considered a  |
| degradation of the protection of safe shutdown capability. The affect of     |
| this concern on the fire protection program does not eliminate the ability   |
| to achieve safe shutdown. The remaining two 'defense in depth' barriers      |
| remain intact - (prevention of fires and prompt detection and control of     |
| fires that due occur). In an area such as containment (large volume, high    |
| ceilings, minimal ignition sources, limited combustibles, limited access,    |
| etc.) the potential for a fire of consequence during operation is highly     |
| unlikely. In the particular area described, the potential for a fire is even |
| more remote since the combustible loading is negligible. The location where  |
| the separation issue exists (at the end of the annulus area near the pipe    |
| chase) does not contain significant equipment, significant exposed           |
| combustible materials or significant ignition sources. The cable trays       |
| routed in this area (between radius lines 1 and 3) are relatively lightly    |
| loaded since most cables have previously exited the tray enroute to their    |
| respective equipment (e.g., only one tray continues past radius line 2 to    |
| radius line 1).                                                              |
|                                                                              |
| "The probability of a fire in Containment is very low. The probability of a  |
| fire causing significant damage such that required function is impaired is   |
| very low. Therefore, the equipment and system affected by this condition is  |
| considered degraded but operable. Based on the guidance provided in GL 91-18 |
| a reasonable assurance of safety is provided."                               |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37529       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  USAF RADIOISOTOPE COMMITTEE          |NOTIFICATION DATE: 11/16/2000|
|LICENSEE:  U.S. AIR FORCE                       |NOTIFICATION TIME: 21:32[EST]|
|    CITY:  SARASOTA                 REGION:  2  |EVENT DATE:        11/16/2000|
|  COUNTY:                            STATE:  FL |EVENT TIME:        17:20[EST]|
|LICENSE#:  42-23539-01AF         AGREEMENT:  Y  |LAST UPDATE DATE:  11/16/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MIKE ERNSTES         R2      |
|                                                |LINDA HOWELL         R4      |
+------------------------------------------------+E. WILLIAM BRACH     NMSS    |
| NRC NOTIFIED BY:  LT. COL. SWENSON             |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF TWO AMERICIUM-241 SOURCES (4 MICROCURIES EACH) DUE TO THE CRASH OF   |
| AN F-16 NEAR SARASOTA, FLORIDA                                               |
|                                                                              |
| An F-16 crashed near Sarasota, Florida which may have been carrying two (2)  |
| Am-241 sources used in the LANTIRN (Low Altitude Navigation Targeting        |
| Infrared for Night) pod.  The Air Force will followup to determine whether   |
| the sources were onboard and, if so, attempt recovery from the crash scene.  |
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