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Event Notification Report for August 16, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/15/2001 - 08/16/2001

                              ** EVENT NUMBERS **

38206  38209  38210  38211  

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|Power Reactor                                    |Event Number:   38206       |
+------------------------------------------------------------------------------+
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 08/13/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 21:31[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        08/13/2001|
+------------------------------------------------+EVENT TIME:        17:53[EDT]|
| NRC NOTIFIED BY:  V. FALLACARA                 |LAST UPDATE DATE:  08/15/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR SCRAM DURING LOGIC SYSTEM TESTING OF EMERGENCY BUS A5.    |
|                                                                              |
| Pilgrim Unit 1 scrammed from 100% during performance of Logic System Testing |
| of Emergency Bus A5.  This is the first time that  the Logic System Testing  |
| of Emergency Bus A5 had been performed at power. The test is performed once  |
| every 24 months and had just been rewritten to be performed at power.  The   |
| cause of the scram is under investigation at this time but the initiating    |
| transient was the loss of Emergency Bus A5.  All rods fully inserted into    |
| the core.   The plant is at 700 lbs. and a controlled depressurization is in |
| progress.  Plans are to cool down to less than or equal to 150 lbs. and      |
| repair the outboard RCIC steam isolation valve.                              |
|                                                                              |
| Due to deenergization of Emergency Bus A5, Recirculation Pump A tripped and  |
| there was a fast transfer of the swing bus (this was expected).  The         |
| licensee is looking into the transfer of the swing bus causing the trip of   |
| Recirculation Pump B.  Loss of both operating Recirculation Pumps at power   |
| will cause a reactor scram.    All systems operated properly.  The           |
| electrical grid is stable and all Emergency Core Cooling systems are fully   |
| operable if needed.  The Recirculation pumps will be restarted when the      |
| differential temperature between the top and bottom head are within          |
| specification.                                                               |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| **** UPDATE ON 08/14/01 AT 1338ET BY V. FALLACARA TAKEN BY MACKINNON ****    |
|                                                                              |
| This is a supplement report to detail additional information on the scram a  |
| Pilgrim, Unit 1 on 08/13/01.                                                 |
|                                                                              |
| Upon further evaluation of the event and the requirements of 10CFR50.72 and  |
| NUREG-1022,  Pilgrim is reporting the valid actuation of the following       |
| containment isolation groups immediately following the scram: Group 2        |
| (Secondary Isolations), Group 6 (Reactor Water Cleanup), and Reactor         |
| Building Isolation with initiation of Standby Gas Treatment Systems. These   |
| are expected occurrences in a post-scram transient due to reactor water      |
| level shrink below the Reactor Level Setpoint of + 12".                      |
|                                                                              |
| Further plant response issues which are currently under investigation        |
| include:                                                                     |
|                                                                              |
| Finalizing the cause of the "B" side RPS actuation.                          |
| Determining the cause of the loss of "B" Recirculation Pump.                 |
| Resolving a falsely pegged level indication on the "A" Reactor Water Level   |
| Indication.                                                                  |
| Determining the cause of the loss of 120 VAC bus Y-4.                        |
|                                                                              |
| An event analysis team has been formed to drive out all of these issues.     |
| R1DO (Ron Bellamy) notified.                                                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| ***** UPDATE FROM VINCENT FALLACARA TO LEIGH TROCINE RECEIVED AT 1420 ON     |
| 08/15/01 *****                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This is a supplemental report to further clarify information initially      |
| provided concerning logic system testing of the Division 1 Emergency Bus as  |
| it related to the 08/13/01 automatic shutdown."                              |
|                                                                              |
| "The initial information indicated that this was the first time this testing |
| had been performed at power and that the test had been rewritten to be       |
| performed at power."                                                         |
|                                                                              |
| "This initial information did not clearly describe the situation concerning  |
| this testing.  Emergency Bus Relay testing has been successfully performed   |
| at power in the past.  This test procedure was reformatted to delineate Tech |
| Spec required testing from non-Tech Spec required testing to reduce the      |
| unnecessary Diesel Generator unavailability time.  During reformatting, an   |
| error was introduced which left out a needed prerequisite to successfully    |
| complete the Tech Spec required testing of the A-EDG output breaker.  This   |
| is currently believed to be an initiating event that contributed to the      |
| 08/13/01 automatic shutdown."                                                |
|                                                                              |
| "At this time, Pilgrim is in Cold Shutdown.  The Events Analysis Team        |
| continues to investigate previously identified plant issues related to this  |
| shutdown."                                                                   |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R1DO (Bellamy).                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38209       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 08/15/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 06:30[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        08/15/2001|
+------------------------------------------------+EVENT TIME:        04:49[EDT]|
| NRC NOTIFIED BY:  JIM HICKEY                   |LAST UPDATE DATE:  08/15/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHARLIE PAYNE        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     M/R        Y       15       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 3 WAS MANUALLY TRIPPED DURING A LOAD REDUCTION DUE TO A LOSS OF         |
| CONDENSER VACUUM.                                                            |
|                                                                              |
| "During a Unit 3 load reduction, a manual reactor trip was initiated.  Plant |
| documents provide guidance for manually tripping the reactor.                |
|                                                                              |
| "If reactor power is greater than 10% and condenser vacuum decreases below   |
| 24.5" Hg with generator load less than 531 MWe, then the reactor is manually |
| tripped.                                                                     |
|                                                                              |
| "The balance-of-plant operator noted condenser vacuum at 24.2" Hg with       |
| reactor power at 15% and generator load at 30 MWe.  The Unit RCO with SRO    |
| concurrence manually tripped the reactor.                                    |
|                                                                              |
| "Systems which did not function as required:                                 |
|                                                                              |
| a.  N-35 Intermediate Range;  High Level Trip did not clear as expected.     |
| b.  N-36 Intermediate Range;  Spiking indication following reactor trip.     |
| c.  Rod Position Indicator E-9 indicates mid-scale approximately 117 steps   |
| (Rod Bottom light on)."                                                      |
|                                                                              |
| The licensee has the cause for the loss of condenser vacuum under            |
| investigation.  The licensee will inform the NRC resident inspector.         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38210       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 08/15/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 12:04[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        08/14/2001|
+------------------------------------------------+EVENT TIME:        16:44[EDT]|
| NRC NOTIFIED BY:  GREG MILLER                  |LAST UPDATE DATE:  08/15/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| POSITIVE, FOR-CAUSE, FITNESS-FOR-DUTY TEST                                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On August 14, 2001, at 1655 hours, a [non-licensed contract] supervisor     |
| tested positive for an illegal substance as a result of a for-cause test.    |
| Access to the protected area was suspended at 1659 hours on August 14, 2001. |
| A review of the individual's work activities was performed, and no deficient |
| work practices which could impact safety-related equipment/systems were      |
| identified.  The employee has been denied further access to the Fermi Energy |
| Center."                                                                     |
|                                                                              |
| Call the NRC operations officer for additional details.                      |
|                                                                              |
| The licensee notified the NRC resident inspector and NRC Region 3 office     |
| (Gary Pirtle).                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38211       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 08/15/2001|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 13:12[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        08/15/2001|
+------------------------------------------------+EVENT TIME:        05:50[EDT]|
| NRC NOTIFIED BY:  BREIDENBAUGH                 |LAST UPDATE DATE:  08/15/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       82       Power Operation  |82       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "An unexpected electrical breaker trip has caused a loss of power to the     |
| Technical Support Center (TSC).  On 08/15/01 at 0550, the Main Control Room  |
| was notified that the TSC, which is located in a building adjacent to the    |
| protected area, was without power."                                          |
|                                                                              |
| "Subsequent investigation revealed that the feed breakers supplying power to |
| the affected bus had tripped.  Further investigation is in progress to       |
| identify and repair any deficiencies.  In accordance with station            |
| procedures, contingency actions are in place should an event occur which     |
| required the use of the TSC.  Communication remains available from the       |
| TSC."                                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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