Event Notification Report for September 14, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/13/1999 - 09/14/1999
** EVENT NUMBERS **
36068 36122 36135 36150 36151 36152 36153 36154 36155 36156 36157 36158
36159 36160
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36068 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/25/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 04:29[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/25/1999|
+------------------------------------------------+EVENT TIME: 01:48[EDT]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KATHLEEN MODES 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
+------------------------------------------------------------------------------+
| UNEXPECTED HIGH PRESSURE COOLANT INJECTION SYSTEM SUCTION SWAPOVER DURING |
| ROUTINE EMERGENCY DIESEL GENERATOR TESTING |
| |
| While using the "Diesel Generator Undervoltage Test Auto Start Switch" to |
| start the 'B' emergency diesel generator as part of a routine surveillance |
| test, an unexpected high pressure coolant injection system suction swapover |
| occurred, and three valves actuated to swap the suction from the condensate |
| storage tank (normal) to the torus. Apparently, a low spike was received on |
| both the DC1 system and condensate storage tank level when the "Diesel |
| Generator Undervoltage Test Auto Start Switch" was operated. After the |
| condensate storage tank and torus levels were verified to be normal, the |
| licensee swapped the high pressure coolant injection suction back to its |
| normal lineup. The licensee is currently investigating the cause of this |
| transient. |
| |
| The 'B' emergency diesel generator started as expected. |
| |
| The licensee plans to notify the NRC resident inspector and the State of |
| Vermont. |
| |
| * * * RETRACTION 1205 9/13/1999 FROM DENNIS MAY TAKEN BY STRANSKY * * * |
| |
| "Section 3.3.2 of NUREG 1022, rev. 1, states, 'Usually, the staff would not |
| consider this [reporting criterion] to include single component actuations |
| because single components of complex systems, by themselves, usually do not |
| mitigate thc consequences of significant events.' |
| |
| "VY evaluated the conditions that were present at the time of the automatic |
| transfer. VY concluded that the automatic transfer occurred independent of |
| the EDG start. The transfer occurred due to a spurious low condensate |
| storage tank level indication spike, not an ESF initiating signal. A single |
| component, the HPCI CST Suction Isolation Valve responded to that spurious |
| signal. The two Torus (Suppression Pool) suction isolation valves then |
| responded as designed to the CST Suction isolation valve 'not full open' |
| indication. The CST suction was immediately capable of being reopened, were |
| it to have been needed. |
| |
| "The 'not reportable' conclusion is based upon thc fact that the cited |
| action, the automatic closure of the HPCI CST Suction Isolation Valve, and |
| the appropriate opening of the Torus Suction isolation valves, would not |
| mitigate the consequences of an event. Therefore, this is not a condition |
| requiring an ENS notification or an LER relative to ESF actuations." |
| |
| The NRC resident inspector has been informed of this retraction by the |
| licensee. Notified R1DO (Della Greca). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36122 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FOXBORO COMPANY |NOTIFICATION DATE: 09/03/1999|
|LICENSEE: FOXBORO COMPANY |NOTIFICATION TIME: 14:00[EDT]|
| CITY: FOXBORO REGION: 1 |EVENT DATE: 09/03/1999|
| COUNTY: STATE: MA |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 09/13/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE (FAX) NRR |
| |TAD MARSH NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GEORGE JOHNSON | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEFECTIVE RELAYS PROVIDED TO FOXBORO BY VENDOR |
| |
| Foxboro Co., has identified a potential failure with N-2A0-L2C-R and/or |
| 2A0-L2C-R Contact Output Isolator cards. The subject cards may contain |
| N0152CK relays supplied by Communications Instruments Inc. which may have |
| been manufactured utilizing a repair residual on the contact armature plate. |
| As a result, relays utilizing this repair residual have contacts that may |
| not return to their normal de-energized position when the relay is |
| de-energized (a condition known as contact hang-up). |
| |
| Extensive analysis performed on a number of relays confirmed that |
| utilization of this repair residual prevented the return of the contact |
| armature (and contacts) to the normally de-energized position when the relay |
| coil was de-energized after an energization period of at least one hour. |
| Further analysis performed by the supplier of the relay confirmed the |
| presence of this repair residual as the root cause for the relay failures. |
| The supplier has determined that during assembly of the relays, this |
| unauthorized repair procedure may have been utilized on 5 to 6 percent of |
| the relays manufactured since manufacturing week 9834. Utilization of the |
| repair residual has been halted by the manufacturer of the relay. |
| |
| ***Update on 09/13/99 at 1325 ET by George Johnson taken by MacKinnon**** |
| |
| "Subsequent investigate analysis and an audit performed at the supplier's |
| manufacturing facility, has determined that the utilization of Mylar repair |
| residuals is present is present on relays displaying a manufacturer's date |
| code of 9806 to 9933. |
| |
| "As we were investigating the Mylar problem, we identified another potential |
| defect of substandard solder joints. Relays that were supplied with |
| substandard (poorly wetted) solder joints could lead to cracked, or in |
| extreme cases, intermittent solder connections. This potential defect |
| could present itself as an intermittent connection to the common relay |
| contact. Foxboro has determined that relays manufactured between 9801 and |
| 9936 could display this potential defect. |
| |
| "Foxboro is taking immediate corrective action to rectify the situation and |
| will notify all Nuclear Utilities that have purchased this product from |
| Foxboro during the time period affected and provide replacement relays" |
| R1DO (Neil Della Greca) and NRR (Vern Hodge) notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36135 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: METOREX |NOTIFICATION DATE: 09/08/1999|
|LICENSEE: METOREX |NOTIFICATION TIME: 11:10[EDT]|
| CITY: EWING REGION: 1 |EVENT DATE: 09/08/1999|
| COUNTY: STATE: NJ |EVENT TIME: [EDT]|
|LICENSE#: 29-30342-01 AGREEMENT: N |LAST UPDATE DATE: 09/13/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |TOM MOSLAK R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOHN PATTERSON | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PACKAGE CONTAINING RADIOACTIVE SOURCES LOST DURING SHIPMENT |
| |
| Mr. Patterson of Metorex contacted the NRC Headquarters Operations Center to |
| report that a package containing a device with two radioactive sources (60 |
| mCi of Cm-244 and 30 mCi of Am-241) has been lost during shipment by Federal |
| Express. The package left Metorex on 8/3/99, but failed to arrive at |
| Envirosafe Services of Oregon, OH as of 8/26/99. The package was last |
| scanned by Federal Express on 8/16/99 in Northwood, OH. The licensee has |
| been in contact with the RSO for Federal Express (Dr. Roy Parker) regarding |
| this shipment. |
| |
| * * * UPDATE AT 1006 EDT ON 9/13/99 BY JOHN PATTERSON TO FANGIE JONES * * * |
| |
| The missing package has been located by Federal Express and will be |
| delivered to Envirosafe Services. Region 1 (Pam Henderson) has been |
| notified by Metorex. The NRC operations officer notified R1DO (Niel Della |
| Greca) and NMSS EO (Wayne Hodges). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36150 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/12/1999|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 16:17[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/12/1999|
+------------------------------------------------+EVENT TIME: 15:30[EDT]|
| NRC NOTIFIED BY: RICHARD TRUAX |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 85 Power Operation |85 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE TSC DUE TO BREAKER FAILURE. |
| |
| During planned electrical switching at the Unit 1 training center a breaker |
| failed to close causing a loss of power to the Unit 1 training center which |
| provides power to the Technical Support Center (TSC). This resulted in a |
| loss of assessment capability from the TSC . Assessment capability is still |
| available from the main control room and Emergency Operation Facility. |
| |
| The licensee is investigating the cause of the breaker failure. |
| |
| The NRC resident will be notified. |
| |
| * * * UPDATE AT 0155 EDT ON 9/13/99 BY ED EILOLA TO FANGIE JONES * * * |
| |
| Repairs were made and power was restored to the TSC at 0145 EDT on 9/13/99. |
| The licensee intends to notify the NRC Resident Inspector. The NRC |
| operations officer notified the R1DO (Tom Moslak). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36151 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 11:26[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 08:30[EDT]|
| NRC NOTIFIED BY: CALVIN WARD |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO PUMPING SETTLING PONDS IN PREPARATION FOR |
| HURRICANE |
| |
| The licensee pumped the settling ponds to the plant discharge canal in |
| preparation for hurricane Floyd. No discharge limits were exceeded, but the |
| Florida Department of Environmental Protection was notified as required by |
| Saint Lucie's National Pollution Discharge Elimination System Permit. |
| |
| The licensee notified the NRC Resident Inspector as well as the state |
| agency. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36152 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OAKLAND GENERAL HOSPITAL |NOTIFICATION DATE: 09/13/1999|
|LICENSEE: OAKLAND GENERAL HOSPITAL |NOTIFICATION TIME: 14:10[EDT]|
| CITY: Madison Heights REGION: 3 |EVENT DATE: 09/13/1999|
| COUNTY: STATE: MI |EVENT TIME: 12:00[EDT]|
|LICENSE#: 21-11494-01 AGREEMENT: N |LAST UPDATE DATE: 09/13/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MONTY PHILLIPS R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM MARSH | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SURFACE CONTAMINATION OF DELIVERED PACKAGE EXCEEDED LIMITS. |
| |
| |
| Syncor delivered a package containing one 15 mCi iodine-131 capsule to |
| Oakland General Hospital, Madison Heights, MI, at approximately 1200 ET. |
| Radiation surveys of the package were within limits, but a wipe of the |
| package reading was 3000 dpm (limit is 2200 dpm). The licensee used a well |
| counter and determined that the surface contamination was from |
| technetium-99m The licensee contacted Syncor and informed them of the hot |
| package. The licensee said that the package will be left in the hot lab and |
| they will either decontaminate the package or will let the Tc-99m surface |
| contamination decay to acceptable limits by itself. The licensee said that |
| nobody at their hospital were contaminated by the package and that they will |
| survey the area where the Syncor delivery man passed through. |
| |
| NRC Region 3 (Bob Gattone) was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36153 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 14:50[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |GARY SHEAR 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 85 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE DURING SURVEILLANCE TESTING. |
| |
| During performance of a calibration/functional surveillance test of the HPCI |
| equipment room temperature instrumentation, the trip unit being tested |
| failed upscale. A step in the surveillance procedure places a keylock |
| switch in the TEST position, preventing a HPCI system Channel A isolation |
| and HPCI Turbine Trip. The Trip unit was declared inoperable. |
| |
| The licensee's Technical Specification require that the inoperable |
| instrument channel be restored to Operable status in 6 hours or the Action |
| to close the affected system isolation valves within 1 hour and declare the |
| affected system inoperable. |
| |
| On September 13, 1999 at 1411 EDT hours, the affected HPCI isolation valves |
| were isolated and the HPCI system was declared inoperable. All Emergency |
| Core Cooling Systems, Emergency Diesel Generators, and RCIC are fully |
| operable if needed. |
| |
| Efforts to replace the failed trip unit are in progress. |
| |
| The NRC Resident Inspector was notified of this event by the Licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36154 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TACOM - ROCK ISLAND |NOTIFICATION DATE: 09/13/1999|
|LICENSEE: TACOM - ROCK ISLAND |NOTIFICATION TIME: 16:49[EDT]|
| CITY: Barstow REGION: 4 |EVENT DATE: 09/08/1999|
| COUNTY: STATE: CA |EVENT TIME: 20:00[PDT]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 09/13/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |GARY SHEAR R3 |
+------------------------------------------------+WAYNE HODGES NMSS |
| NRC NOTIFIED BY: TIM MOHS | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBDB 30.50(b)(4)(ii) DAMAGED LNM/CONTAINER | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FIRE CONTROL DEVICES USED FOR AIMING A 198 HOWITZER WERE DAMAGED CAUSING A |
| RELEASE OF TRITIUM AND CONTAMINATION OF THE FIRE CONTROL DEVICES. |
| |
| On September 8, 1999 at approximately 2000 PDT a 198 Howitzer was damaged. |
| Some of the fire control devices used for aiming the Howitzer were damaged. |
| It is estimated that between 3 to 4 curies of tritium were released from the |
| damaged fire control devices. A survey was performed on the damaged fire |
| control devices and surface contamination on the damaged fire control |
| devices from tritium was a couple of million disintegrations per minute. Ten |
| Marines from camp Pendleton who cleaned up the contamination were bioassayed |
| after the cleanup. The bioassay results on these individuals are still |
| pending. The contaminated fire control devices are now located at the US |
| Marine Corp Logistic Base located outside of Barstow, California. The |
| Howitzer was damaged on Interstate 15 just outside of Barstow, California. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36155 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 17:08[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 16:50[EDT]|
| NRC NOTIFIED BY: MATUSZEWSKI |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |ROBERT HAAG R2 |
|10 CFR SECTION: |JOSEPH GIITTER IRO |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |KEN CIBOCH FEMA |
| |FRANK CONGEL IRO |
| |ELINOR ADENSAM NRR |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO ENTERING EAL 12A (NATURAL PHENOMENON - |
| HURRICANE WARNING CONFIRMED). |
| |
| |
| The licensee entered an Unusual Event per Emergency Action Level 12A. All |
| emergency diesel generators are fully operable and the electrical grid is |
| stable. All emergency core cooling systems are fully operable except for |
| CCW heat exchanger "3B". Heat Exchanger "3B" will be restored to service |
| soon. The state of Florida and surrounding counties have been informed of |
| the Unusual Event classification. |
| |
| The NRC Resident Inspector will be informed by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36156 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 17:30[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 17:13[EDT]|
| NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |ROBERT HAAG R2 |
|10 CFR SECTION: |JOSEPH GIITTER IRO |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |DAN SULLIVAN FEMA |
| |FRANK CONGEL IRO |
| |ELINOR ADENSAM NRR |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO ENTERING EAL 5B ITEM 1 (CONFIRMED HURRICANE |
| WARNING IN EFFECT) |
| |
| The licensee entered an Unusual Event per Emergency Action Level 5B item 1. |
| All emergency diesel generators are fully operable and the electrical grid |
| is stable. All emergency core cooling systems are fully operable. The state |
| was notified of the Unusual Event classification. Local counties will be |
| notified of the Unusual Event classification by the state of Florida. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36157 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 18:20[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 16:30[EDT]|
| NRC NOTIFIED BY: BARNES |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 98 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO THE STATE OF GEORGIA ENVIRONMENTAL PROTECTION |
| DIVISION |
| |
| At approximately 1630 hours a notification was made to the State of Georgia |
| Environmental Protection Division regarding the exceedance of the |
| instantaneous and two hour release rate for residual chlorine from the site |
| during plant service water chlorination. An investigation is in progress |
| to determine the cause. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36158 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 18:59[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 18:05[EDT]|
| NRC NOTIFIED BY: MIKE VASELY |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|NINF INFORMATION ONLY |JOSEPH GIITTER IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT CLASSIFICATION SHOULD HAVE BEEN DECLARED FOR INDIAN POINT T |
| UNIT 2 REACTOR TRIP WITH A LOSS OF OFFSITE POWER EVENT # 36104 WHICH |
| OCCURRED ON 08/31/99. |
| |
| The following is a 1 hour notification pursuit to 10 CFR 50.72 (a). |
| |
| During post event review for the 08/31/99 reactor trip and subsequent loss |
| of offsite power, it has been determined that the plant met the conditions |
| of the notification of an unusual event at approximately 1446 hours, because |
| the existing undervoltage conditions on bus 6A would have prevented the |
| licensee from restoring offsite power within 15 minutes. Although offsite |
| power was available, the licensee did not have the ability to energize the |
| 480V Buses from this source within the emergency action level action time. |
| All buses except 6A were energized by emergency diesel generators. This |
| report implements the guidance provided for a missed report as described in |
| NUREG 1022 Rev. 1. |
| |
| Emergency Planning Department personnel are notifying State and Local |
| Authorities. |
| |
| The NRC Resident Inspector was notified of this event. |
| |
| See Indian Point Unit 2 event # 36104 for event description. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36159 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/13/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 20:11[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 09/13/1999|
+------------------------------------------------+EVENT TIME: 18:24[EDT]|
| NRC NOTIFIED BY: BRIAN SULLIVAN |LAST UPDATE DATE: 09/13/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOSEPH GIITTER IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 50 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM ON A LOSS OF CONDENSER VACUUM FROM 34% REACTOR POWER. |
| |
| The licensee was initially holding reactor power at 50% for preparation of |
| performing backwash of the main condensers. A work order had been opened |
| up earlier to perform work on the augmented offgas system. While holding |
| reactor power at 50%, the licensee began to lose condenser vacuum. |
| Condenser vacuum was initially at 28". The licensee entered Abnormal |
| Operating Procedure 2.4.36 (Loss of Condenser Vacuum). Reactor power was |
| manually decreased to reduce the heat load on the main condenser in order to |
| decrease the rate at which main condenser vacuum was decreasing. At 24" of |
| condenser vacuum, the reactor was manually scrammed (at 22" of vacuum, an |
| automatic turbine trip/reactor scram would have occurred). All control rods |
| inserted; however, the licensee lost rod position indication for eight |
| control rods following the scram. This loss of control rod position |
| indication has occurred before. |
| |
| Due to the loss of rod position indication, the licensee entered Emergency |
| Operating Procedure 2 (Failure to Scram). The licensee remained in EOP-2 |
| for about 3 minutes before control rod position indication was regained for |
| the eight affected control rods. The licensee reported that the rod |
| position indication system will sometimes lose position indication if the |
| control rods are inserted beyond the 00 position. The licensee was aware |
| that the unit was subcritical because neutron monitoring average power range |
| monitor (APRM) downscale alarms were received. After confirming that all |
| control rods were fully inserted into the core (one rod was at position 02) |
| the licensee exited EOP-2 and entered EOP -1 (Reactor Scram). When reactor |
| vessel water level was restored to its normal band, EOP-1 was exited. |
| |
| Following the scram, reactor vessel water level decreased to just below +12 |
| inches, which initiated a Group 2 (containment isolation), Group 6 (reactor |
| water cleanup isolation) and a reactor building isolation signal. Reactor |
| vessel water level is being maintained between +20 and +40 inches (top of |
| active fuel is -125 inches) using a reactor feedwater pump. Offsite power |
| fast transferred as expected and is supplying electrical power to the plant |
| house loads. No safety relief valves opened and the emergency core cooling |
| systems and emergency diesel generators are fully operable if needed. |
| |
| The licensee suspects that work on the augmented offgas system could have |
| caused the loss of condenser vacuum. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36160 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: BNFL FUEL |NOTIFICATION DATE: 09/14/1999|
|LICENSEE: BNFL FUEL |NOTIFICATION TIME: 05:16[EDT]|
| CITY: SPRINGFIELDS REGION: |EVENT DATE: 08/12/1999|
| COUNTY: ENGLAND STATE: |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SHEAR R3 |
| |KEVIN RAMSEY (FAX) NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HOWARD WHITTAKER | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT - CYLINDER NOT IN COMPLIANCE WITH ANSI 14.1 SENT TO |
| PADUCAH |
| |
| "A full 48Y cylinder containing natural UF6 was sent to USEC at Paducah from |
| BNFL Springfields in May 1997. On August 12, 1999, whilst preparing the |
| cylinder for feeding, USEC personnel discovered that the cylinder was not in |
| compliance with ANSI 14.1. The cylinder nameplate was stamped with a water |
| capacity of 4019 Kgs equivalent to 142.1 cubic feet. The current standard |
| of ANSI 14.1 requires a minimum volume of a 48Y cylinder to be 4037 Kgs |
| water equivalent to 142.7 cubic feet. Since this cylinder does not comply |
| with the ANSI standard it cannot be fed to the Paducah Gaseous Diffusion |
| Plant. |
| |
| "It is our understanding that the USA Code of Federal Regulations 10 CFR |
| Part 21 requires the receiver of a basic component that has a defect or |
| deviates from a specification, to notify the supplier of the component of |
| the defect or deviation. We have received a formal notification from the |
| Paducah Plant of a deviation from the technical specification for UF6 |
| cylinders. |
| |
| "10 CFR Part 21 requires the supplier of the basic component to complete an |
| evaluation / failure to comply associated with safety hazards as soon as |
| practical, and in all cases within 60 days of discovery to identify any |
| defect etc that could create a substantial safety hazard if it remained |
| uncorrected. |
| |
| "We therefore have accepted our responsibility for reporting the deviation |
| to the NRC and to conduct the evaluation as per the requirements of 10 CFR |
| Part 21." |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021