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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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."                                                                    |
+------------------------------------------------------------------------------+