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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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
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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. |
| |
| ***** 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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