Event Notification Report for May 19, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/16/2003 - 05/19/2003
** EVENT NUMBERS **
39849 39851 39853 39854 39855 39856 39857
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|Power Reactor |Event Number: 39849 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/15/2003|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 05:27[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/15/2003|
+------------------------------------------------+EVENT TIME: 02:52[CDT]|
| NRC NOTIFIED BY: HALL |LAST UPDATE DATE: 05/16/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JOHNSON R4 |
|10 CFR SECTION: |MICHAEL CASE NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|RICHARD WESSMAN IRO |
|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 Standby |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR TRIP FROM 100% POWER ON BOTH UNITS DUE TO TURBINE TRIP ON BOTH |
| UNITS |
| |
| The licensee reported that a loss of power on the 345KV grid caused a |
| turbine trip on both units which resulted in a reactor trip from 100% on |
| both units. All rods fully inserted and no ECCS was actuated. Both units |
| are currently at Mode 3 in natural circulation and stable. The auxiliary |
| feed water systems started on both units to maintain steam generator levels. |
| The reactor coolant temperature is being controlled by using the steam |
| generator atmospheric relief valves. Since the safety systems were powered |
| by an alternate offsite power supply, the 4 emergency diesels did not auto |
| start, but they are operable. The licensee is investigating why they lost |
| the 345KV grid. |
| |
| |
| The NRC Resident Inspector was notified. |
| |
| *****UPDATE ON 5/16/03 AT 1500 EST FROM D. BUTLER TO R. LAURA***** |
| |
| "Status as of 10:30, 05/16/03 - Sequence of Events |
| |
| 1. Parker line experiences a `B' phase to ground fault at 02:52. |
| 2. CPSES [Comanche Peak Steam Electric Station] Parker feeder breaker 8040 |
| fails to trip as required. |
| |
| Primary and backup ground relaying do not actuate. No trip signal is sent to |
| the Parker breaker. |
| Should normal tripping have occurred, fault would likely have cleared and |
| event ended. |
| |
| East Bus backup timers are not initiated due to lack of Parker Breaker 8040 |
| trip signal. Operation of the |
| backup timers would have isolated the East bus. CPSES impact would likely |
| have been lowering one unit to |
| 50% power while operating the other unit at 100% power. |
| |
| 3. Parker line remains faulted with fault current being supplied from the |
| East bus, West bus and CPSES generation. |
| 4. Approximately 30 cycles into the fault, 345 Kv offsite feeds began to |
| trip via their own protective schemes. |
| 5. At approximately 1.3 seconds, Unit 1 and 2 Main Generator breakers trip |
| on generator backup Main transformer |
| neutral ground relaying. |
| 6. Unit 1 and 2 Main Generator lockout relays actuate on Load Rejection |
| protection. |
| 7. Unit 1 and Unit 2 Normal 6.9KV busses trip on Generator lockout signals. |
| 8. Unit 1 Normal busses slow transfer to Station Transformer 1 ST at |
| approximately 5 seconds. |
| Unit 2 two normal bus alternate feed 2ST has been de-energized from the 8080 |
| breaker blocking slow |
| transfer operation. |
| 9. Station Transformer 1 ST `C' phase time over current relaying operates |
| generating a 1 ST lockout signal. |
| 10. Unit 1 normal 6.9Kv bus alternate feeder breakers are tripped via the 1 |
| ST lockout signal. |
| Unit 1 and Unit 2 normal 6.9Kv busses are now de-energized. |
| 11. East and West busses are inspected by ONCOR and CPSES Maintenance. |
| Switchyard West bus is re- |
| energized from the Wolf Hollow Line. |
| 12. Station transformers 1ST and 2ST are re-energized and power restored to |
| Unit 1 and 2 Normal 6.9KV busses. |
| |
| "Troubleshooting |
| |
| "Primary Fault detection relay is tested and is found failed. The Fault |
| detector serves as a Supervisory relay during line faults. It serves as a |
| trip permissive, placing the trip circuits of the ground detection relaying |
| in service. Failure of the Fault Detector is the obvious cause of the |
| Primary relay protection scheme failure to operate. Backup Fault detection |
| relay is tested and is found to operate correctly. Failure of the backup |
| protection scheme is likely caused by the inconsistent operation of the |
| backup ground relay and failure of the CA unit of the Zone 1 relay." |
| |
| Notified R4DO (Johnson) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39851 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NATIONAL RESPONSE CENTER |NOTIFICATION DATE: 05/15/2003|
|LICENSEE: NORTH ANNA |NOTIFICATION TIME: 13:45[EDT]|
| CITY: KINGMAN REGION: 4 |EVENT DATE: 05/14/2003|
| COUNTY: SUMNER STATE: KS |EVENT TIME: 18:00[CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/16/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+TIM MCGINTY DIRO |
| NRC NOTIFIED BY: LYNN WARRICK |JANICE KROON EPA |
| HQ OPS OFFICER: ERIC THOMAS |DAVID WHITFILL STAT |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TRANSPORTATION INCIDENT |
| |
| The National Response Center sent a fax to the Operations Center regarding |
| the following transportation incident: |
| |
| A tractor trailer carrying the reactor vessel head from North Anna power |
| plant to EnviroCare in Clive, UT was sideswiped by a pickup truck being |
| driven by a drunk driver near Kingman, KS on Route 42. The pickup truck |
| passed the tractor trailer at approximately 80 mph, and proceeded down the |
| road, where it was involved in a traffic accident. The incidental impact |
| between the pickup and the tractor trailer caused a minor tear in the |
| protective tarp and plastic container containing the vessel head, along with |
| depositing some paint on the head itself. There was no apparent structural |
| damage to the vessel head, and no apparent radioactive release into the |
| atmosphere. |
| |
| The truck driver stopped his vehicle in Greensburg, Kansas to assess the |
| condition of the vessel head. The shipper is sending a representative to |
| inspect the packing material integrity. The state of Kansas will also be |
| sending a representative out to the scene to assist. |
| |
| *****UPDATE ON 5/16/03 AT 13:50 EST FROM CONNELLY TO LAURA***** |
| |
| Three independent radiological surveys conducted by the State of Kansas and |
| North Anna determined there was no spread of contamination and only minor |
| damage occurred to the shipping packaging for the vessel head. The minor |
| damage was repaired and the truck was released. |
| |
| Notified R4DO (W. Johnson), DIRO (McGinty) and NMSS (Essig). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39853 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/16/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:04[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/15/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/16/2003|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |SONIA BURGESS R3 |
| DOCKET: 0707002 |TOM ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MCCLEERY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|QSAF 72.75(c)(2) SAFETY EQUIP DISABLED/F| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY SYSTEM ACTUATION |
| |
| On 5/15/03 @1400 during pigtail disconnect, a small amount of particulate |
| fell from the pigtail. This particulate began to smoke resulting in a see |
| and flee. During the see and flee the gas release alarm was activated. The |
| alarm resulted in the actuation of a "Q" Safety system while in applicable |
| mode (mode III). The PSS Responded to the see and flee. The affected |
| cylinder was made inoperable. No spread of contamination outside already |
| posted area. Air sampling results are less than MDA. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39854 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/16/2003|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 12:53[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/16/2003|
+------------------------------------------------+EVENT TIME: 04:56[EDT]|
| NRC NOTIFIED BY: JOHN YADUSKY |LAST UPDATE DATE: 05/16/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|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 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SPECIFIED SYSTEM ACTUATION |
| |
| "On 5/16/03 with the reactor shutdown in MODE 3, an unplanned actuation of |
| Auxiliary Feedwater (AFW) system occurred during testing of the 'B' Main |
| Feed Pump (MFP). A trip of an uncoupled MFP generated a signal to start |
| both motor-driven AFW pumps during testing following maintenance. The 'A' |
| motor-driven AFW pump was already in service, so the 'B' AFW pump started on |
| receipt of the signal. Feed to the steam generators was always available, |
| even without the additional actuation of the AFW system. The purpose of the |
| actuation of AFW following a trip of the main feed system is to ensure |
| adequate flow to the steam generator. In this case, the main feed pump was |
| being tested and was not being used to provide flow to the steam generator. |
| Therefore the actuation was not required to provide any safety function. |
| The 'B' motor-driven AFW pump was secured within approximately two minutes |
| because the additional flow was not required. This condition is being |
| reported as an unplanned system actuation in accordance with 10 CFR |
| 50.72(b)(3)(iv)(A). |
| |
| "10 CFR 50.72 requires an 8-hour report for, 'Any event or condition that |
| results in valid actuation of any of the systems listed in paragraph |
| (b)(3)(iv)(B) of this section except when the actuation results from and is |
| part of a pre-planned sequence during testing or reactor operation.' In |
| this case, the AFW pump start signal due to trip of the last running MFP is |
| only applicable in MODES 1 and 2, and is not required in the current MODE of |
| plant operation (MODE 3). |
| |
| "The NRC Resident Inspector was notified." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39855 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 05/18/2003|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 04:27[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/17/2003|
+------------------------------------------------+EVENT TIME: 22:05[EDT]|
| NRC NOTIFIED BY: BRIAN BATES |LAST UPDATE DATE: 05/18/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |SONIA BURGESS R3 |
|10 CFR SECTION: |MICHAEL CASE NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling Shutdow|0 Refueling Shutdow|
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED CONDITION DUE TO CRACK INDICATIONS ON VESSEL HEAD |
| |
| "At 18:00 on 5/15/03, craze cracking indications were found on a Reactor |
| Pressure Vessel Head Penetration. At 22:05 on 5/17/03, it was determined |
| that this condition was reportable as a prompt eight-hour report under 10 |
| CFR 50.72(b)(3)(ii)(A). |
| |
| "During the Unit 2 reactor head inspection, five small, shallow indications |
| were found on the inside diameter of penetration #74. The indications are |
| closely spaced and are approximately 3/8 inch below the J-groove weld |
| region. Initial calculations showed a crack depth of 0.117 inches. All of |
| the indications are bounded within an area that is one inch wide by 2.6 |
| inches high. There was no through-wall leakage and the reactor coolant |
| pressure boundary remains intact. |
| |
| "These indications were previously identified during the last refueling |
| outage in February 2002. They were evaluated as acceptable to leave in |
| service for a full cycle at that time, and they have not shown any |
| significant growth since then. |
| |
| "The industry guidance on projected flaw growth rates has been revised since |
| these indications were discovered in 2002. As a result, the new projections |
| for these indications result in less than a full fuel cycle before reaching |
| the limit for remaining in service. Therefore, repairs will be needed. |
| Current plans are to perform an excavation of the affected area, under |
| existing code guidance." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39856 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/18/2003|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 21:58[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/18/2003|
+------------------------------------------------+EVENT TIME: 18:07[EDT]|
| NRC NOTIFIED BY: RANDY WILSON |LAST UPDATE DATE: 05/18/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROBERT HAAG R2 |
|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 28 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RPS ACTUATION WHILE CRITICAL |
| |
| "On 5/18/03 with the reactor at 28 percent power in MODE 1, an unplanned |
| actuation of the reactor protection system occurred. At 1807 the reactor |
| was automatically tripped from a turbine trip - reactor trip signal. All |
| systems functioned as required and no other safety systems were actuated. |
| The operations staff responded to the event in accordance with applicable |
| plant procedures. The plant stabilized at normal operating no-load Reactor |
| Coolant System temperature and pressure following the reactor trip. The |
| cause of the turbine trip is under investigation. |
| |
| "This condition is being reported as an unplanned reactor protection system |
| actuation in accordance with 10 CFR 50.72(b)(2)(IV)(B) and 10 CFR |
| 50.72(b)(3)(iv)(A)." |
| |
| All rods fully inserted and decay heat is being removed via the PORV's. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39857 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/19/2003|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 05:57[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/19/2003|
+------------------------------------------------+EVENT TIME: 04:24[EDT]|
| NRC NOTIFIED BY: MARTIN MANPENFEL |LAST UPDATE DATE: 05/19/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN MCDERMOTT R1 |
|10 CFR SECTION: |TERRY REIS NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|RICHARD WESSMAN IRO |
|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 3 Startup |0 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM RESULTING IN PRIMARY CONTAINMENT AND REACTOR |
| BUILDING ISOLATIONS |
| |
| At 0424 EDT, during startup operations, the Main Turbine Bypass valves |
| unexpectedly opened and depressurized the reactor vessel. After |
| depressurization, the reactor level increased due to swell and caused an |
| automatic reactor scram. Additionally, there was a Reactor Building |
| Isolation Signal and Group I, II, and VI Primary Containment Isolation |
| Signal generated. Immediately after the automatic scram, five control rods |
| failed to insert into the core. Plant operations personnel performed |
| actions in accordance with their Emergency Operating Procedures to drive the |
| control rods into the core. According to the licensee, adequate shutdown |
| margin was always maintained. |
| |
| The plant electrical system is stable with plant equipment being powered |
| from offsite and the startup transformer. Reactor pressure and level are |
| being maintained via steam line drains to the main condenser. |
| |
| Troubleshooting of the Main Turbine Bypass valves/control system is in |
| progress. |
| |
| The licensee will be notifying the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021