Event Notification Report for March 10, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/07/2003 - 03/10/2003
** EVENT NUMBERS **
39526 39575 39630 39643 39644 39645 39646 39647 39648 39649 39650 39651
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39526 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/20/2003|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:13[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/20/2003|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: JAMES WITTER |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN ROGGE R1 |
|10 CFR SECTION: |MOHAMED SHANBAKY R1 |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| SERVICE WATER SYSTEM VALVE PIT PIPING PENETRATION SEAL |
| |
| "On 1/20/2003 at 1430 hours, the Beaver Valley Power Station control room |
| was notified by Engineering that a penetration seal previously installed in |
| a wall which separates two service water system valve pits may have not been |
| adequate. A review of the supporting analysis shows that this penetration |
| seal may not be qualified to withstand the hydraulic pressure which could |
| result from a postulated internal flooding event occurring due to a service |
| water system pipe failure filling the valve pit and its above compartment |
| prior to operator intervention. A failure of this seal during a postulated |
| internal flooding event may result in the loss of motor operated valve |
| movement in both trains of the service water system that would be needed |
| following a design basis accident (DBA). |
| |
| "This design basis calculation and the penetration seal capability are |
| continuing to be evaluated. However, this seal could potentially have |
| prevented the service water system from meeting single failure criterion |
| during a postulated service water system pipe failure. Therefore, Technical |
| Specification (TS) 3.7.4.1 was entered due to less than two trains of |
| service water system being operable as a conservative decision based upon |
| the limited information immediately available to show acceptable seal |
| integrity at the postulated conditions. The TS Action requires restoration |
| of two independent service water system trains within 72 hours. Actions are |
| in progress to install a qualified seal which will prevent the unacceptable |
| flooding conditions from being able to occur. |
| |
| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an |
| unanalyzed condition that significantly degraded plant safety since this |
| seal has been installed for five months and may have invalidated the |
| independence between the two service water system trains. The NRC resident |
| has been notified of the degraded condition." |
| |
| * * * RETRACTION RECEIVED AT 1002 EST ON 3/07/2003 BY WITTER TO CROUCH * * * |
| |
| |
| "Beaver Valley Power Station (BVPS) Unit No. 2 retracts the notification |
| made on 01/20/2003 at 20:13 hrs [EST] regarding the event reported under 10 |
| CFR 50.72(b)(3)(ii)(B) [ENS #39526]. The previous notification identified a |
| potential issue with a seal penetration which may have invalidated the |
| independence between two Service Water System trains. |
| |
| "Subsequent analysis of the event identified that the installed penetration |
| seal between the two Service Water System valve pits would have been capable |
| of performing its intended safety function. Therefore, the separation and |
| independence between the two Service Water System trains, as required by |
| Technical Specification 3.7.4.1, would have been satisfied. |
| |
| "Given that both trains of the Service Water System were able to perform |
| their safety functions, this was not a condition that significantly degraded |
| plant safety." |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39575 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MA RADIATION CONTROL PROGRAM |NOTIFICATION DATE: 02/10/2003|
|LICENSEE: PERKINELMER LIFE SCIENCES |NOTIFICATION TIME: 14:29[EST]|
| CITY: BOSTON REGION: 1 |EVENT DATE: 07/18/2002|
| COUNTY: STATE: MA |EVENT TIME: [EST]|
|LICENSE#: 00-3200 AGREEMENT: Y |LAST UPDATE DATE: 03/07/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GLENN MEYER R1 |
| |DON COOL EO NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CARPENITO | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIALLY MISSING PHOSPHORUS-32 SHIPPING PACKAGES |
| |
| Single packages containing P-32 (~14 day half-life) were destined for four |
| different out-of-state locations (in CA, KS, NY and TX). Intended shipping |
| dates were July 18, August 5 and August 6, 2002. Carrier reported packages |
| potentially missing within 2-3 days after intended shipping dates. The |
| per-package activities ranged from 250 microcuries to 1 millicurie. All |
| subject radioactive material contents are presently well past ten |
| half-lives. After several months of shipper-carrier joint investigation, the |
| cause(s) remain undetermined. Actions have been taken by shipper and carrier |
| to prevent recurrence. |
| |
| * * * * UPDATE RECEIVED BY RIPLEY FROM CARPENITO 1448 EST ON 03/07/03 VIA |
| FAX |
| |
| "Five additional single-package shipments (four P-32 and one I-125), |
| destined for five different locations, shipped August 27, October 17, |
| November 4 and 26, and December 13, 2002, were reported to MARCP as missing |
| on 2/14/03. The per-package activities ranged from 250 to 500 microcuries |
| of P-32 and 50 microcuries I-125. All subject packages were shipped before |
| the shipper and carrier corrective actions had been implemented in late |
| December 2002. No packages shipped since the corrective actions have been |
| implemented have been reported to MARCP as missing." |
| |
| Notified NMSS EO (Reamer) and R1 DO (Shanbaky) |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39630 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/02/2003|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 10:43[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/02/2003|
+------------------------------------------------+EVENT TIME: 03:35[CST]|
| NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT MEASURED LEAKAGE EXCEEDS THE ALLOWED LEAKAGE. |
| |
| During routine scheduled LLRT (Local Leak Rate Testing) of Penetration |
| X-214, HPCI (High Pressure Coolant Injection) Exhaust Discharge to the |
| Torus, leakage was unable to be quantified. Additionally, of the two |
| isolation check valves in the line, the licensee could not determine which |
| one was leaking. As such, Primary Containment Allowed Leakage (La) is |
| unable to be verified to be less than allowed. |
| |
| The plant was in Mode 4 (Cold S/D) for a scheduled refueling outage with |
| temperature being maintained between 130 and 145 degrees Fahrenheit and |
| Primary Containment not required at the time of discovery. The plant will |
| remain in cold shutdown until repairs are completed. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * * RETRACTION RECEIVED AT 1326 EST ON 03/07/03 BY BLAIR TO RIPLEY * * * |
| * |
| |
| "On 3/2/03 at 0943 CST, Cooper Nuclear Station made an 8 hour 50.72 |
| non-emergency notification to the NRC. This was done due to the failure of |
| Local Leak Rate Testing (LLRT) involving the High Pressure Coolant Injection |
| (HPCI) exhaust discharge to the Suppression Chamber. Leakage was unable to |
| be quantified. Additionally, of the two isolation check valves in the line, |
| testing was unable to determine which one was leaking. |
| |
| "Based on indications of leakage during the LLRT, maintenance activities |
| were started on one of the valves (HPCI-15CV). Upon removal of the |
| HPCI-15CV bonnet it was noticed that the valve was not properly seated. |
| Engineering is continuing to evaluate this condition. To facilitate |
| continuing troubleshooting HPCI-15CV was manually closed by pushing the disk |
| into the valve seat. The bonnet was re-installed and the LLRT was repeated. |
| The other check valve in this line (HPCI-44) was not touched or manipulated |
| during the period of time between successive LLRT's. |
| |
| "The results of the repeat LLRT were well within acceptance criteria limits |
| demonstrating that HPCI-44 was properly performing its containment isolation |
| function. Since HPCI-44 was working properly, the conditions that required |
| an 8 hour 50.72 notification no longer apply. The penetration was always |
| capable of performing the containment isolation function. |
| |
| "The NRC Resident Inspector was notified." |
| |
| Notified R4 DO (D. Powers). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39643 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 19:17[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 14:40[EST]|
| NRC NOTIFIED BY: ROBERT KIDDER |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JOHN DAVIDSON IAT |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 83 Power Operation |83 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 1- HOUR SAFEGUARD REPORT |
| |
| Discovery of criminal act involving individual granted access to the site. |
| Immediate compensatory measures taken upon discovery. Contact the |
| Headquarters Operations Officer for details. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39644 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 15:46[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 14:39[EST]|
| NRC NOTIFIED BY: JOHN CHUNIS |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: |CHRISTOPHER GRIMES NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO |
| |MIKE EACHES FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PLANT DECLARED UNUSUAL EVENT DUE TO REACTOR TRIP WITH LEAKAGE FROM CHARGING |
| SYSTEM |
| |
| A reactor automatic trip was received at 1439 EST. The cause of the trip is |
| unknown and investigation continues, although reactor protection system |
| testing was in progress at the time of the trip. All systems responded |
| normally with the exception of the charging system. The licensee declared |
| an unusual event at 1516 EST due to charging pump discharge relief valves |
| lifting thereby creating leakage into the auxiliary building. |
| Preliminarily, the cause of the relief valve discharge was blockage in the |
| normal charging line downstream. Charging flow was reestablished via the |
| alternate flowpath. A minimal radioactive release from the auxiliary |
| building ventilation resulted from the charging system leakage. |
| |
| The NRC Resident Inspector was notified. State and local officials were |
| notified and the licensee issued a press release. |
| |
| * * * UPDATE 0420EST ON 3/8/03 FROM ROBERT MALONEY TO S.SANDIN * * * |
| The licensee terminated the Unusual Event at 0146EST after Unit 2 entered |
| mode 4. The licensee informed state/local agencies and the NRC resident |
| inspector. Notified R1DO(Shanbaky), EO(Grimes) and FEMA(Stinedurf). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39645 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 21:32[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 20:49[EST]|
| NRC NOTIFIED BY: ROBERT WHITE |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: |JOSEPH HOLONICH IRO |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |CHRISTOPHER GRIMES NRR |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |FEMA WATCH OFFICER FEMA |
|ADEV 50.72(b)(1) DEVIATION FROM T SPEC | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO INABILITY TO REACH HOT SHUTDOWN WITHIN TECH |
| SPEC ACTION STATEMENT TIME LIMIT |
| |
| The licensee declared an unusual event at 2049 EST due to the inability to |
| reach Mode 4 within the Technical Specification action statement time limit |
| of 2049 EST for charging pumps inoperable. The charging pumps were declared |
| inoperable as a result of system complications associated with the reactor |
| trip and charging system leakage occurring at 1439 EST 3/7/03 (see Event # |
| 39644). |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE 0420EST ON 3/8/03 FROM ROBERT MALONEY TO S.SANDIN * * * |
| The licensee terminated the Unusual Event at 0146EST after Unit 2 entered |
| mode 4. The licensee informed state/local agencies and the NRC resident |
| inspector. Notified R1DO(Shanbaky), EO(Grimes) and FEMA(Stinedurf). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39646 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 22:06[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 13:31[CST]|
| NRC NOTIFIED BY: BRYAN KELLEY |LAST UPDATE DATE: 03/07/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS R4 |
|10 CFR SECTION: | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 88 Power Operation |88 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OPEN AUXILIARY BUILDING DOOR COULD HAVE CAUSED A LOSS OF SECONDARY |
| CONTAINMENT FUNCTION |
| |
| "At 1622 CST on 3/7/03, a Condition Report was written to identify that |
| Auxiliary Building door PW-95-02 was open because a door assist device |
| malfunction prevented closure of the door. This condition existed from 1331 |
| until 1449 on 3/7/03. |
| |
| "This condition could have resulted in a loss of function of the Secondary |
| Containment since Standby Gas Treatment system may not have been able to |
| draw down pressure in the Auxiliary Building to the required vacuum." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39647 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/08/2003|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 01:58[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 23:55[EST]|
| NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 03/08/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAROLYN EVANS 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 22 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC DIESEL ACTUATION CAUSED BY LOSS OF GENERATION EXCITATION TRIP |
| |
| "During planned Unit Two manual scram in preparation for refueling outage, |
| all four Emergency Diesel Generators received an auto start signal. Auto |
| start signal was generated from a Primary Generator Lockout caused by a Loss |
| of Generator ExcitatIon Trip. A 1/2 Group 1 signal was also received during |
| the shutdown due to a steam flow trip unit failure, which has been repaired. |
| All other systems operated as designed, scram actions completed, plant |
| stable. The Loss of Excitation Trip should have been blocked by main |
| generator PCB openings. Investigation currently underway to determine cause |
| of Loss of Excitation Trip malfunction." |
| |
| There was no loss of power. The busses were not loaded after all four |
| diesels started. The diesels operated normally and have been returned to a |
| standby lineup. All other systems operated as required. |
| |
| The Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39648 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/09/2003|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 04:08[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/09/2003|
+------------------------------------------------+EVENT TIME: 03:12[EST]|
| NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 03/09/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION |
| |
| "On 3/9/03 at 0140 the Main Control Room was notified that an ambulance was |
| requested at the site. A contract pipe fitter working in Primary |
| Containment on unit 2 experienced heat stress. Site EMT's stabilized the |
| individual and he was transported to a local hospital for treatment. The |
| individual was not contaminated. The ambulance left site at 0216, and the |
| Pennsylvania Emergency Management Agency was notified at 0312. Due to |
| notification to another government agency, this event is reportable under |
| 10CFR50.72(b)(2)(xi)." |
| |
| The Licensee notified the State of Pennsylvania and will notify the NRC |
| Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39649 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/09/2003|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 12:08[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/08/2003|
+------------------------------------------------+EVENT TIME: 22:18[EST]|
| NRC NOTIFIED BY: GRANT FERNSLER |LAST UPDATE DATE: 03/09/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY 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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY ASSESSMENT CAPABILITY FOR GREATER THAN 8 HOURS |
| |
| "On 3/9/03 the Main Control Room was notified that the Unit 2 SPDS [Safety |
| Parameter Display System] computer was not updating properly. A review into |
| the history identified that the SPDS computer had stopped updating at 22:18 |
| on 3/8/03. The computer group attempted to reset the SPDS computer to |
| correct the condition. The reset was successful and all indication returned |
| to normal. |
| |
| "Since the Unit 2 SPDS computer system was unavailable for greater than 8 |
| hours, this is considered a Loss of Emergency Assessment Capability and |
| therefore reportable under 10CFR50.72(b)(3)(xiii)." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39650 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 00:46[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/09/2003|
+------------------------------------------------+EVENT TIME: 20:47[CST]|
| NRC NOTIFIED BY: JONATHAN PIERCE |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY INJECTION SYSTEM ACTUATION AND CAUSE UNDER INVESTIGATION |
| |
| "At 20:47 on 3/9/03, Unit 2 experienced a Safety Injection while the plant |
| was stable at NOP(2235 psig)/NOT |
| (567 degrees) in Mode 3. All systems actuated as designed. An operator was |
| operating the 'B' S/G PORV shortly |
| before the event occurred. All MSIVs were closed for ongoing work on the |
| main turbine. The Sequence of |
| events report showed all 3 channels of steam pressure spiking low on the 'B' |
| Steam Generator as the cause of the event. Initial look at trends on the |
| integrated computer system showed [that] steam pressure channels did not |
| lower to a point to cause the safety injection. An Event Review Team is |
| being formed to investigate this event. |
| |
| "A Reactor Coolant System PORV opened due to high pressure when the Spray |
| valves closed due to the Instrument Air isolation (due to phase 'A') with |
| the Pressurizer Heaters in manual. The Pressurizer heaters were secured and |
| Reactor coolant System pressure stabilized. All ESF systems actuated as |
| designed. The following systems actuated: Auxiliary Feedwater, Safety |
| Injection, Phase 'A', Control Room Envelope and Fuel Handling Building HVAC |
| systems, Essential Cooling Water, Component Cooling Water, Emergency Diesel |
| Generators and ESF sequencers." |
| |
| There was no safety injection since pressure was maintained above 2199 psi |
| during the transient (Hi Head is 1700 psi). Heat removal is being performed |
| through S/G PORVs and Unit 2 is currently stable at Mode 3. |
| |
| The Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39651 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 03:45[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 00:12[EST]|
| NRC NOTIFIED BY: JOHN RODEN |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |STEPHEN CAHILL R2 |
|10 CFR SECTION: |CAROLYN EVANS R2 |
|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 N Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP ON GENERATOR DIFFERENTIAL RELAY |
| ACTUATION |
| |
| "At 0012 EST on March 10, 2003, with Watts Bar Unit 1 in Mode 1 at 100% |
| power, the reactor tripped due to an automatic signal. All plant safety |
| systems were in service at the time to the trip, except for the 2B-B diesel |
| generator which was out of service for scheduled maintenance, and all |
| [safety systems] responded as designed. All control rods inserted as |
| required and the Auxiliary Feedwater System [AFW] initiated as expected. |
| |
| "The reactor trip resulted from a turbine trip signal that was generated as |
| a result of a main generator/transformer differential electrical relay |
| actuation. The plant is currently stable in Mode 3 and will remain in this |
| Mode until completion of the investigation." |
| |
| AFW was removed from operation and the main feed pumps have resumed normal |
| feed to the Steam Generators. The Licensee notified the NRC Resident |
| Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021