Event Notification Report for November 8, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/07/2000 - 11/08/2000
** EVENT NUMBERS **
37425 37474 37487 37498 37499 37500 37501 37502
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|Power Reactor |Event Number: 37425 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/12/2000|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 19:05[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/12/2000|
+------------------------------------------------+EVENT TIME: 18:59[EDT]|
| NRC NOTIFIED BY: YOUNG |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SPRAY ADDITIVE TANK 31 INOPERABLE DURING MAINTENANCE |
| |
| On July 21, 2000, the Spray Additive Tank 31 Outlet Isolation Valve |
| (SI-1841) was shut for approximately eight and one half-hours, to perform |
| maintenance on one of the downstream automatic Sodium Hydroxide isolation |
| valves. This would have effectively prevented Sodium Hydroxide from being |
| sprayed into Containment if the Spray Pumps had been required. This is not |
| in accordance with Tech Spec 3.3.B.1.a and the associated Bases which |
| requires the Spray Additive Tank to be operable above Cold Shutdown. |
| |
| Therefore, isolation of this tank could have potentially placed the |
| Containment Spray System outside of its design basis; however, the |
| investigation of this event is ongoing. |
| |
| This event was discovered by the System Engineer while performing a periodic |
| review of system unavailability (time) in accordance with the Maintenance |
| Rule. |
| |
| The NRC Resident Inspector will be notified. |
| |
| *** UPDATE AT 1537 ON 11/07/00 FROM TRACY SUDOKO TO LEIGH TROCINE *** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This notification is an update to Event No. 37425. [Indian Point 3] |
| reported, on 10/12/00, that the Containment Spray (CS) System NaOH Spray |
| Additive Tank (SAT) outlet isolation valve (SI-1841) was shut for |
| approximately eight and one-half hours on 07/21/00 to perform preventative |
| maintenance on a downstream automatic NaOH SAT isolation valve. This report |
| was made because this event placed the CS system outside of its design basis |
| as per 10 CFR 50.72(b)(1)(ii)(B)." |
| |
| "The Technical Specification (TS) provides no allowed outage time for the |
| SAT, so a TS-required shutdown should have been initiated, and the plant |
| [should have been shut down] within 4 hours. Further review of the |
| Emergency Plan Action Levels (EAL), specifically EAL 7.1.1, determined that |
| [a Notification of Unusual Event (NUE)] is required to be declared if the |
| plant is not brought to the required operating mode within the TS [limiting |
| condition for operation (LCO)] action statement time. Entry into an NUE was |
| not made when the event occurred on 07/21/00." |
| |
| The licensee plans to notify the NRC resident inspector as well as |
| applicable state and local agencies. The NRC operations officer notified |
| the R1DO (Michele Evans), NRR EO (Tad Marsh), IRO (Joe Giitter), and FEMA |
| (Tony Cegielsky). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37474 |
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+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/30/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:26[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/29/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:54[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/07/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |DAVID HILLS R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEITH VANDERPOOL | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR GASEOUS DIFFUSION PLANT REPORT |
| |
| "At approximately 1954 hours, 10/29/00, operations personnel investigated a |
| LAW CADP smoke head alarm. While investigating the alarm for smoke head SXE |
| 2786 for LAW 2A compressor the operations personnel did not identify any |
| visible release but smelled HF in the area. The 'SEE & FLEE' emergency |
| procedures were immediately implemented. The affected LAW station withdrawal |
| loop was in standby at the time of the alarm. Results of all surveys |
| performed during the emergency response were less than MDA. At 2102 hours, |
| an all clear was granted on the emergency response. PORTS is reporting this |
| alarm as a valid actuation of a 'Q' Safety System. |
| |
| "This is reportable to the NRC as a valid actuation of a 'Q' Safety System |
| in accordance with Safety Analysis Report, section 6.9 (24-HOUR REPORT)." |
| |
| *** UPDATE/RETRACTION AT 1639 ON 11/07/00 FROM ERIC SPAETH TO LEIGH TROCINE |
| *** |
| |
| The following text is a portion of a facsimile received from Portsmouth |
| personnel: |
| |
| "An engineering evaluation performed following the event determined that the |
| small leak, which caused the smoke head actuation, originated from the LAW |
| 1A compressor. This compressor had been shutdown for several weeks prior to |
| the event for maintenance. Engineering determined that the compressor had |
| been purged to a UF6 negative and subsequently pressurized to atmosphere to |
| allow work to be performed. The compressor was in Mode IV (Shutdown) when |
| the smoke head actuation occurred." |
| |
| "Based on the above, the plant conditions that the CADP smoke detection |
| system was designed to protect against were not present when the small leak |
| occurred, and this event may be retracted." |
| |
| Portsmouth personnel notified the NRC resident inspector. The NRC |
| operations officer notified the R3DO (Wright) and NMSS EO (Brach). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37487 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 11/04/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 08:27[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 11/04/2000|
+------------------------------------------------+EVENT TIME: 08:22[EST]|
| NRC NOTIFIED BY: THOMAS VEITCH |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE EOF DUE TO PLANNED MAINTENANCE |
| |
| "LOSS OF POWER TO THE EMERGENCY OPERATIONS FACILITY. THIS IS A PREPLANNED |
| MAINTENANCE ACTIVITY ON BREAKER H2110. THE REMOVAL OF THIS BREAKER CAUSES |
| THE FACILITY (EOF) TO LOSE POWER AND IS, THEREFORE, 'POTENTIALLY' |
| UNAVAILABLE FOR GREATER THAN 90 MINUTES. THE TOTAL ESTIMATED DURATION OF |
| THE ACTIVITY IS 8 HOURS." |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 1040EST ON 11/7/00 FROM BRUCE LUTHANEN TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "Event Notification 37487 is hereby retracted, This notification reported |
| the unavailability of the Emergency Operations Facility (EOF) due to an |
| electrical maintenance activity that removed power from the EOF, as required |
| by plant operating procedures. |
| |
| "The guidance for the one-hour call reporting criteria was obtained from a |
| plant instruction which specifically stated that a one-hour-call to the NRC |
| shall be made 'if, in the judgment of the Control Room Shift Supervisor, |
| equipment failure or extensive maintenance activities have or will render |
| one or more of the Perry onsite ERFs [Emergency Response Facilities] |
| unavailable..' |
| |
| "10 CFR 50.72(b)(1)(v) requires one-hour, non-emergency notification for |
| 'any event that results in a major loss of emergency assessment capability, |
| offsite response capability, or communications capability (e.g. significant |
| portion of control room indication, Emergency Notification System or offsite |
| notification system.)' |
| |
| "The EOF electrical maintenance was a planned, scheduled activity. The |
| Alternate Emergency Operations Facility was available during this time to |
| provide redundancy of all required EOF features dealing with emergency |
| assessment and offsite communication. This capacity was never lost or |
| degraded, and so the criteria for reporting were not met. There is no |
| corresponding section under 10 CFR 50.73, and so an LER is not required." |
| |
| The licensee informed the NRC resident inspector. Notified R3DO(Wright). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37498 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 05:30[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/07/2000|
+------------------------------------------------+EVENT TIME: 02:31[EST]|
| NRC NOTIFIED BY: PETE ORPHANOS |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) ISOLATED AND INOPERABLE DUE TO FAILED |
| STEAM LEAK DETECTION SYSTEM TEMPERATURE ELEMENT |
| |
| "On November 7, 2000 at 0231[EST] Limerick Generating Station received a |
| High Pressure Coolant Injection (HPCI) System isolation due to a failed |
| Steam Leak Detection System temperature element. Outboard isolation valves |
| HV-055-2F003, HV-055-2F100, HV-055-2F041 and HV-055-2F042 received isolation |
| commands. The system isolated as designed. Investigation [into] the cause |
| of the failed temperature element is ongoing. The HPCI system remains |
| isolated and inoperable." |
| |
| Unit 2 is in a 14-day LCO A/S. Other ECCS equipment has been verified |
| operable. The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37499 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 06:35[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/07/2000|
+------------------------------------------------+EVENT TIME: 05:10[CST]|
| NRC NOTIFIED BY: JIM HUNTER |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEDICATED TELEPHONE SYSTEM FOR STATE NOTIFICATIONS INOPERABLE |
| |
| During testing of the Emergency Notification Network (ENN) to the states of |
| Georgia and Alabama, the system failed producing a constant hum on the |
| speaker in the control room. The licensee notified their Birmingham office |
| to initiate repairs. There is currently no estimate available for |
| restoration. The licensee informed the affected states via commercial |
| telephone and will inform the NRC resident inspector. |
| |
| * * * UPDATE 0919EST ON 11/7/00 FROM ROBERT FUCICH TO S. SANDIN * * * |
| |
| The licensee returned the ENN system to service as of 0744EST and will |
| inform the NRC resident inspector. Notified R2DO(Bonser). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37500 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 12:23[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/06/2000|
+------------------------------------------------+EVENT TIME: 12:49[CST]|
| NRC NOTIFIED BY: DON POPP |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSITIVE FOR-CAUSE TEST FOR ALCOHOL REPORTED IN ACCORDANCE WITH 10 CFR |
| 26.73.a(2)(ii) |
| |
| A contract supervisor was determined to be under the influence of alcohol |
| during a for-cause test. The individual's site access was suspended, and |
| the individual was subsequently terminated. (Contact the NRC operations |
| officer for addition details.) |
| |
| The licensee notified the NRC resident inspector and plans to notify the NRC |
| Region 3 office. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37501 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 16:55[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/07/2000|
+------------------------------------------------+EVENT TIME: 15:01[EST]|
| NRC NOTIFIED BY: RUSS GUMBERT |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHELE EVANS 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FEEDWATER ISOLATION DUE TO CYCLING OF A BOILER FEED (BF) VALVE AND THE |
| SUBSEQUENT STEAM GENERATOR WATER LEVEL PERTURBATION |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The] 21 steam generator level rose to the high-high level trip setpoint of |
| 67% narrow range level at which time a feedwater isolation signal was |
| generated. This is an [engineered safety feature (ESF)] actuation. The |
| plant is in Mode 4 at 332�F reactor coolant system temperature with [four] |
| reactor coolant pumps in service. Steam generator levels were being |
| maintained by intermittent feed with the main feed system and auxiliary feed |
| system in standby. Temperature control is via steam dumps to [the] |
| condenser. The 21 through 24BF13s and BF40s went closed. With the |
| exception of [the] 21BF19, the 22 through 24BF19s were already closed. The |
| 21BF19 went closed due to the high-high level. The condition was caused by |
| cycling open of [the] 21BF19 during troubleshooting of position indication. |
| [The] feedwater isolation is currently reset, and steam generator levels are |
| being maintained with main feed as prior to the event. No other steam |
| generator levels were effected, and 21 steam generator level is returned to |
| the pre-event level of [approximately] 40% narrow range." |
| |
| The licensee stated that all systems functioned as required. |
| |
| The licensee plans to notify the NRC resident inspector and the Lower |
| Alloways Creek Township. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37502 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 18:18[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 11/07/2000|
+------------------------------------------------+EVENT TIME: 14:00[EST]|
| NRC NOTIFIED BY: RICKY E. RAWLS |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING THE DISCOVERY OF A DEAD SEA TURTLE IN THE |
| INTAKE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The unit] was operating 100% with all [systems] normal for MODE 1. |
| Maintenance was pulling an intake structure BAR rack in preparation for |
| routine cleaning when the crew noticed a partially decomposed sea turtle |
| floating to the surface. The dead sea turtle was retrieved and sent to the |
| National Marine Fisheries Service (NMFS) for analysis." |
| |
| "NMFS has previously conducted an endangered species Act consultation with |
| the NRC and FPC. This consultation resulted in the establishment of sea |
| turtle protection criteria under a Biological Opinion and an Incidental Take |
| Statement. This turtle discovery is within the sea turtle protection |
| criteria established by the NMFS with FPC. A written report will be |
| submitted to NMFS." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
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