Event Notification Report for August 15, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/14/2001 - 08/15/2001
** EVENT NUMBERS **
38206 38207 38208 38209
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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: 08/14/2001|
| 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
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| 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. |
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|Power Reactor |Event Number: 38207 |
+------------------------------------------------------------------------------+
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| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 08/14/2001|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 12:07[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 08/14/2001|
+------------------------------------------------+EVENT TIME: 03:34[EDT]|
| NRC NOTIFIED BY: M. BROWNE |LAST UPDATE DATE: 08/14/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DEAD SEA TURTLE FOUND. |
| |
| A dead Kemp's Ridley sea turtle was found in the intake canal of Oyster |
| Creek early this morning. No tags present or obvious boat propeller wounds |
| on the sea turtle but it has several scutes with superficial scrapes near |
| carapace centerline and posterior notch. National Marine Fisheries Service |
| Northeast Region was notified. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 38208 |
+------------------------------------------------------------------------------+
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| FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 08/14/2001|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 20:16[EDT]|
| RXTYPE: [1] GE-1 |EVENT DATE: 08/14/2001|
+------------------------------------------------+EVENT TIME: 19:20[EDT]|
| NRC NOTIFIED BY: M. VAN ALST |LAST UPDATE DATE: 08/14/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SECURITY EVENT |
| |
| Security Officer's unescorted access was revoked. Compensatory action was |
| immediately taken upon discovery. Licensee is reviewing person's previous |
| work. |
| |
| Licensee will notify NRC Region 3 of this event. |
| |
| Contact the NRC Operation Center for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021