U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/27/2000 - 06/28/2000
** EVENT NUMBERS **
37061 37087 37112 37117 37118 37119 37120 37121 37122 37123 37125
37126
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37061 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/06/2000|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 12:47[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 06/06/2000|
+------------------------------------------------+EVENT TIME: 10:20[EDT]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE |
| |
| After completion of HPCI pump surveillance testing, a check for freedom of |
| movement and proper reset action of the overspeed trip tappet was performed. |
| As a result of this check, an adjustment was found to be necessary for the |
| turbine stop valve reset time. Attempts to make this adjustment resulted in |
| inoperability of the reset function of the overspeed trip. HPCI was |
| declared inoperable and Technical Specification limiting condition for |
| operation 3.5E(3) was entered. HPCI will still start if called upon but if |
| it trips on overspeed HPCI will become inoperable. |
| |
| Reactor Core Isolation Cooling, Emergency Diesel Generators, and all other |
| Emergency Core Cooling Systems are fully operable if needed. The electrical |
| grid is stable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE 1252EDT ON 6/27/00 FROM DAVID HALLONQUIST TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "This notification serves as retraction of a prior 10 CFR 50.72 notification |
| regarding High Pressure Coolant Injection (HPCI) operability. The original |
| notification is NRC event report number 37061 and was reported on 6/6/00. |
| |
| "At that time, during routine surveillance testing, it was discovered that |
| the HPCI over-speed trip did not reset without additional operator action. |
| The event was reported because the cause for the failure to reset had not |
| been determined and, therefore, it was not known whether the condition could |
| have challenged HPCI ability to perform its intended function. |
| |
| "Subsequent engineering review identified that the failure to automatically |
| reset had been caused by inappropriate test methods. It was also determined |
| that the over-speed trip reset concern would not have affected HPCI system |
| ability to meet its design function for high pressure injection. |
| |
| "In addition, the HPCI over-speed reset is NOT a safety function of the VY |
| safety system. As addressed in the VY licensing basis, the reset is required |
| if the HPCI system had already malfunctioned. The identified condition, |
| therefore, would not have impacted system operability. |
| |
| "Based on the above, the 50.72 notification is retracted." |
| |
| The licensee will inform the NRC Resident Inspector. Notified R1DO(Morris). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37087 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/15/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:54[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 06/15/2000|
+------------------------------------------------+EVENT TIME: 19:15[CDT]|
| NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE DUE TO INCOMPLETE POST |
| MODIFICATION TESTING OF IT'S ASSOCIATED DIESEL GENERATOR |
| |
| "At 1915 on 6/15/00 a Engineering review of a plant modification to the |
| Division 3 Diesel Generator (DG) determined that the Post Modification |
| Testing did not verify proper operation of the Loss of Off-Site Power (LOOP) |
| circuitry. This modification had only been performed to Division 3 DG and |
| therefore Division 1 and 2 DG's are not affected. Division 3 DG provides |
| power to the High Pressure Core Spray (HPCS) pump. The failure of Division 3 |
| DG to operate during a LOOP would have prevented HPCS from operating. The |
| loss of a single train safety system such as HPCS is reportable under |
| 10CFR50.72(b)(2)(iii)(D)." |
| |
| The plant modification involved rewiring the electrical circuit to correct |
| for a degraded voltage condition and was completed on 1/24/99. Post |
| modification testing was completed on 1/31/99. HPCS has been declared |
| inoperable but is available, if needed, pending completion of additional |
| testing. The licensee will inform the NRC Resident Inspector. |
| |
| * * * UPDATE 2115EDT ON 6/27/00 FROM CHEAR TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "Further review of this issue has determined that Division 3 Diesel |
| Generator (DG) output breaker control circuit has been operable since |
| installation of the modification and the plant was never in a condition that |
| alone could have prevented fulfillment of the safety function. Therefore, |
| Clinton Power Station is retracting Event Notification # 37087." |
| |
| The licensee informed the NRC Resident Inspector. Notified R3DO(Leach). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37112 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 06/25/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 20:27[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/25/2000|
+------------------------------------------------+EVENT TIME: 17:45[CDT]|
| NRC NOTIFIED BY: BURKETT |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) 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 Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT MADE NOTIFICATION TO THE NATIONAL RESPONSE CENTER AND THE ILLINOIS |
| EMERGENCY MANAGEMENT AGENCY OF AN OIL SPILL. |
| |
| These notifications were made due to a small quantity of oil in the runoff |
| ditch. The quantity of oil is estimated to be 5 gallons and was due to an |
| overflow of their lube oil separator. Cleanup efforts are in progress. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE ON 6/27/00 AT 1240 EDT BY CAL WALRATH TO FANGIE JONES * * * |
| |
| The licensee made a press release and notified the NRC Resident Inspector |
| and the state and local authorities of the press release. |
| |
| The operations officer notified the R3DO (Melvyn Leach). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37117 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/26/2000|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 19:23[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/26/2000|
+------------------------------------------------+EVENT TIME: 18:53[EDT]|
| NRC NOTIFIED BY: RICK O'CONNOR |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |SCOTT MORRIS R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT MANUALLY TRIPPED FOLLOWING A LOSS OF THE "A" MAIN FEEDWATER PUMP (MFP) |
| |
| AT 1900EDT ON 6/26/00, THE UNIT EXPERIENCED A PLANT SETBACK TO 55% POWER |
| FOLLOWING THE LOSS OF THE "A" MFP. OPERATORS INSERTED A MANUAL REACTOR TRIP |
| AS STEAM GENERATOR LEVELS APPROACHED THE LOW LEVEL TRIP SETPOINT. ALL |
| SYSTEMS FUNCTIONED AS REQUIRED WITH ALL CONTROL RODS FULLY INSERTING. |
| EMERGENCY FEEDWATER (EFW) ACTUATED AS EXPECTED. THE MAIN CONDENSER IS |
| AVAILABLE ACCEPTING DECAY HEAT VIA STEAM BYPASS. NO PRIMARY/SECONDARY |
| SAFETIES/RELIEFS LIFTED DURING THE TRANSIENT. ALL THREE OFFSITE POWER |
| SOURCES ARE AVAILABLE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND WILL ISSUE A PRESS |
| RELEASE. |
| |
| ********** UPDATE AT 0015 ON 06/27/00 FROM DAMON RITTER TO LEIGH TROCINE |
| ********** |
| |
| The licensee updated this event notification to document an abnormal |
| post-trip response and to correct the event time. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "Subsequent to the trip, one channel of intermediate and source range |
| nuclear instrumentation did not energize. The cause is under investigation. |
| [The licensee stated that this did not place the unit in a limiting |
| condition for operation because there was still one channel in operation.] |
| Additionally, the event time for the event notification is corrected. The |
| reactor trip was initiated at 1853 [on] 26 June 2000 [in lieu of 1900]." |
| |
| The licensee plans to notify the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Morris). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37118 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/26/2000|
| UNIT: [1] [2] [] STATE: NJ |NOTIFICATION TIME: 22:17[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/26/2000|
+------------------------------------------------+EVENT TIME: 20:58[EDT]|
| NRC NOTIFIED BY: S. SAUER |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |SCOTT MORRIS R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 92 Power Operation |92 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF A SIGNIFICANT PORTION OF OFFSITE EMERGENCY SIRENS |
| |
| "NOTIFIED BY EMERGENCY PLANNING PERSONNEL THAT AS OF 2058[EDT] ON 6/26/00, |
| NINETEEN [19] OFFSITE SIRENS HAD BEEN LOST. AS OF 2158[EDT] EFFORTS TO |
| RESTORE ARE STILL IN PROGRESS. OF THE NINETEEN [19], SIXTEEN [16] ARE IN |
| DELAWARE AND THREE [3] ARE IN NEW JERSEY. THE NINETEEN [19] SIRENS |
| REPRESENTS LOSS OF GREATER THAN 25% OF THE TOTAL OF SEVENTY-ONE [71] |
| SIRENS." |
| |
| THE LICENSEE COULD NOT IDENTIFY THE CAUSE, HOWEVER, THEY ARE CURRENTLY |
| EXPERIENCING ADVERSE WEATHER. THIS REPORT ALSO AFFECTS THE HOPE CREEK |
| STATION. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| ********** UPDATE AT 0043 ON 06/27/00 FROM STEVE SAUER TO LEIGH TROCINE |
| ********** |
| |
| At 2340 on 06/26/00, the licensee was notified that the bulk of the offsite |
| emergency sirens (all but three) had been restored to service. |
| |
| The licensee plans to notify the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Morris). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37119 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 01:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 06/26/2000|
+------------------------------------------------+EVENT TIME: 23:22[EDT]|
| NRC NOTIFIED BY: MARK ABRAMSKI |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |SCOTT MORRIS R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATIONS DUE TO THE TRIPPING |
| OF ELECTRICAL PROTECTION ASSEMBLIES (EPA) AND SUBSEQUENT HALF SCRAM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The unit experienced a loss] of [the] 'A' [reactor protection system |
| (RPS)] bus[. Output] EPAs tripped causing [this 120-volt AC] bus to |
| de-energize. This caused the reactor building ventilation to isolate[,] |
| both [standby gas treatment systems (SBGT)] to start[, and the] 'A' |
| [hydrogen/oxygen (H2/O2)] monitor to trip (PCIS valves). [The reactor water |
| cleanup (RWCU)] system tripped on low flow due to 12MOV-15 closure (PCIS |
| valve)." |
| |
| The licensee stated that there was nothing unusual or not understood and |
| that all systems functioned as required. The licensee also stated that the |
| cause of this event is currently under investigation. The EPAs tripped |
| under normal supply, and the RPS motor-generator set was functioning |
| properly. There were no maintenance or surveillance activities underway at |
| the time of the event. |
| |
| The reactor building and H2/O2 analyzers have since been un-isolated. SBGT |
| is currently under normal operation and is being used for venting. RWCU has |
| not yet been restored to normal. |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37120 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/27/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:36[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/26/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:40[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/27/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT) |
| |
| The following text is a portion of a facsimile received from Portsmouth |
| personnel: |
| |
| "At 1240 hours on 06/26/00, it was discovered that a Nuclear Criticality |
| Safety Approval (NCSA) requirement had not been met during sampling and |
| batching operations in the X-710 building. The contents of four polybottles |
| were batched into two five-gallon containers without adequate documentation |
| showing that the sampling data was for Nuclear Criticality Safety purposes. |
| A review of the sample results indicated that all the results did not meet |
| the NCSA requirements for independent measurements. This violated |
| NCSA-PLANT053.A03 requirement #13 which states, 'The results of sample |
| analysis or NDA (Non-Destructive Assay) measurements shall not be used for |
| NCS purposes if the documentation does not show that the results were |
| determined as NCS significant results.' (Basis: The measurements and |
| analysis must be performed to independent criteria to be acceptable for NCS |
| purposes.)" |
| |
| "Two independent measurements of mass of the batching material are required |
| to ensure double contingency. Only one independent measurement of mass was |
| available. The other measurement did not meet independent criteria per NCSA |
| requirements. The absence of a second independent measurement constituted a |
| loss of one control of the double contingency principle." |
| |
| "A second independent measurement was performed, and compliance was |
| reestablished with NCSA-PLANT053.A03 at 1557 hours on 06/26/00." |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: The safety significance of this event is |
| very low. The total U235 involved in each of the two batches [is] 0.2154 |
| grams and 2.1868 grams, respectively. To re-establish NCS compliance, |
| repeat NCS measurements for each batch were performed to confirm that the |
| total mass meets the requirements of NCSA-PLANT013, Batching Solutions and |
| Solids." |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): Prior to batching the contents in accordance with |
| NCSA-PLANT013, documentation of analysis results are checked to ensure that |
| the measurements were handled as 'NCS Significant' and independently |
| analyzed in accordance with NCSA-PLANT053. Without independent results, a |
| single measurement error could result in more than a safe mass being batched |
| into a container. If this mass were then subject to the correct geometry, |
| moderation, and reflection conditions, a criticality could occur." |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| Mass is the only controlled parameter. Two independent measurements of mass |
| are required to ensure double contingency. Since independence of NDA mass |
| measurements is called into question, only one independent estimate of mass |
| is available. The absence of a second independent NDA mass measurement |
| represents a loss of one double contingency control." |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): The total U235 involved in each |
| of the two batches [is] 0.2154 grams and 2.1865 grams, respectively. |
| Uranium mass is measured in batching operations to ensure the U235 mass in |
| the final container is less than 350 grams U235 which is less than half the |
| minimum critical mass at 100% enrichment and optimum moderation, geometry, |
| and reflection conditions." |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: Nuclear criticality safety controls |
| include independent mass measurements of U235. Failure to ensure that NCS |
| significant measurements were used lead to a potential failure of the |
| measurements." |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| A second independent NDA measurement was performed to verity total mass of |
| U235 (<1 gram per bucket/container). Compliance with NCSA-Plant053.A03 was |
| re-established at 1557 hours based on the results of the NDA measurements." |
| |
| Portsmouth personnel notified the NRC resident inspector and the site |
| Department of Energy manager. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37121 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2 REGION: 4 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 11:57[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 06/27/2000|
+------------------------------------------------+EVENT TIME: 05:30[PDT]|
| NRC NOTIFIED BY: DAVE SWANK |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| MAIN STEAM ISOLATION VALVES (MSIVs) ISOLATED DUE TO SPURIOUS GROUP 1 |
| ISOLATION SIGNAL |
| |
| "This event is being reported per 10CFR50.72(b)(2)(ii). |
| |
| "At 0530 hours the MSIVs inadvertently isolated due to a spurious group 1 |
| primary containment isolation valve logic (NS4) signal. |
| |
| "In support of required surveillance testing of RPS EPA breakers, RPS 'B' |
| bus had been transferred to normal from its alternate power supply. NS4 'B' |
| isolation logic was inadvertently not reset as part of the restoration |
| following this power supply transfer. When bus RPS 'A' was de-energized as |
| part of the planned transfer to the alternate power supply it caused the NS4 |
| 'A' isolation logic relays to de-energize and resulted in a closure signal |
| to all MSIVs. All eight MSIVs closed as expected. |
| |
| "The plant was in Mode 4 at approximately 180þF at the time of the event. |
| Shutdown cooling had been removed from service in preparation for the power |
| supply transfer. Following reset of the NS4 isolation logic. shutdown |
| cooling was restored with the reactor coolant temperature at approximately |
| 187þF. The MSIVs may be re-opened as needed," |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37122 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 12:04[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 06/27/2000|
+------------------------------------------------+EVENT TIME: 09:30[EDT]|
| NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |SCOTT MORRIS R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (NJ DEP) NOTIFIED OF |
| EFFLUENT DISCHARGE TEMPERATURE VIOLATION |
| |
| ON 6/26/00 AT 1844EDT AND 1859EDT, EFFLUENT DISCHARGE TEMPERATURE WAS |
| MEASURED AT 106.62 AND 106.60 DEGREES F. THIS EXCEEDS THE LIMIT OF 106 +0.5 |
| DEGREES F WHICH REQUIRES NOTIFICATION TO NJ DEP. CORRECTIVE ACTION TAKEN |
| INCLUDED LOWERING POWER TO REDUCE EFFLUENT TEMPERATURE. THE LICENSEE ALSO |
| INTENDS TO CHECK THE ALARM SETPOINTS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37123 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 14:17[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/27/2000|
+------------------------------------------------+EVENT TIME: 14:00[EDT]|
| NRC NOTIFIED BY: DENNIS BEMIS |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |SCOTT MORRIS R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE DUE TO PLANNED MAINTENANCE |
| |
| "PLANNED LOSS OF POWER TO THE NEWINGTON SIREN ACTIVATION CONTROL REPEATER |
| FOR GREATER THAN 1 HOUR. POWER SHOULD BE RESTORED WITHIN 1-2 HOURS. THE |
| EOF LOST CAPABILITY TO ALL 94 SIRENS TO BE ACTIVATED. EACH LOCAL COMMUNITY |
| STILL HAD THE ABILITY TO ACTIVATE THEIR RESPECTIVE SIRENS." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37125 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2 REGION: 4 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 20:35[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 06/27/2000|
+------------------------------------------------+EVENT TIME: 15:29[PDT]|
| NRC NOTIFIED BY: OJ BROOKS |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| MAIN STEAM ISOLATION VALVES CLOSED |
| |
| "The Main Steam Isolation Valves closed due to Low Vacuum closure isolation |
| signal. The low vacuum isolation logic had not been completely bypassed as |
| required by PPM 3.2.1, prior to breaking main condenser vacuum. |
| |
| "The RPV is in Shutdown Cooling at 137þF cooling down to a band of 100 to |
| 120þF. Shutdown cooling was not impacted by the isolation." |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37126 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 06/27/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 22:00[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 06/27/2000|
+------------------------------------------------+EVENT TIME: 21:25[EDT]|
| NRC NOTIFIED BY: DOUG SCHROEDER |LAST UPDATE DATE: 06/27/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY SIRENS DUE TO ADVERSE WEATHER |
| |
| "At 2125 Notified by Emergency Preparedness that Chatam County lost all |
| Siren Capability for a period of 8 minutes due to a lightning strike. Siren |
| capability has been restored." |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
