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Event Notification Report for November 8, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/07/2000 - 11/08/2000

                              ** EVENT NUMBERS **

37425  37474  37487  37498  37499  37500  37501  37502  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37425       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 10/12/2000|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 19:05[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        10/12/2000|
+------------------------------------------------+EVENT TIME:        18:59[EDT]|
| NRC NOTIFIED BY:  YOUNG                        |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SPRAY ADDITIVE TANK 31 INOPERABLE DURING MAINTENANCE                         |
|                                                                              |
| On July 21, 2000, the Spray Additive Tank 31 Outlet Isolation Valve          |
| (SI-1841) was shut for approximately eight and one half-hours, to perform    |
| maintenance on one of the downstream automatic Sodium Hydroxide isolation    |
| valves.  This would have effectively prevented Sodium Hydroxide from being   |
| sprayed into Containment if the Spray Pumps had been required.  This is not  |
| in accordance with Tech Spec 3.3.B.1.a and the associated Bases which        |
| requires the Spray Additive Tank to be operable above Cold Shutdown.         |
|                                                                              |
| Therefore, isolation of this tank could have potentially placed the          |
| Containment Spray System outside of its design basis; however, the           |
| investigation of this event is ongoing.                                      |
|                                                                              |
| This event was discovered by the System Engineer while performing a periodic |
| review of system unavailability (time) in accordance with the Maintenance    |
| Rule.                                                                        |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| *** UPDATE AT 1537 ON 11/07/00 FROM TRACY SUDOKO TO LEIGH TROCINE ***        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This notification is an update to Event No. 37425.  [Indian Point 3]        |
| reported, on 10/12/00, that the Containment Spray (CS) System NaOH Spray     |
| Additive Tank (SAT) outlet isolation valve (SI-1841) was shut for            |
| approximately eight and one-half hours on 07/21/00 to perform preventative   |
| maintenance on a downstream automatic NaOH SAT isolation valve.  This report |
| was made because this event placed the CS system outside of its design basis |
| as per 10 CFR 50.72(b)(1)(ii)(B)."                                           |
|                                                                              |
| "The Technical Specification (TS) provides no allowed outage time for the    |
| SAT, so a TS-required shutdown should have been initiated, and the plant     |
| [should have been shut down] within 4 hours.  Further review of the          |
| Emergency Plan Action Levels (EAL), specifically EAL 7.1.1, determined that  |
| [a Notification of Unusual Event (NUE)] is required to be declared if the    |
| plant is not brought to the required operating mode within the TS [limiting  |
| condition for operation (LCO)] action statement time.  Entry into an NUE was |
| not made when the event occurred on 07/21/00."                               |
|                                                                              |
| The licensee plans to notify the NRC resident inspector as well as           |
| applicable state and local agencies.  The NRC operations officer notified    |
| the R1DO (Michele Evans), NRR EO (Tad Marsh), IRO (Joe Giitter), and FEMA    |
| (Tony Cegielsky).                                                            |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37474       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/30/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 12:26[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/29/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        19:54[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/07/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |DAVID HILLS          R3      |
|  DOCKET:  0707002                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEITH VANDERPOOL             |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR GASEOUS DIFFUSION PLANT REPORT                                       |
|                                                                              |
| "At approximately 1954 hours, 10/29/00, operations personnel investigated a  |
| LAW CADP smoke head alarm. While investigating the alarm for smoke head SXE  |
| 2786 for LAW 2A compressor the operations personnel did not identify any     |
| visible release but smelled HF in the area. The 'SEE & FLEE' emergency       |
| procedures were immediately implemented. The affected LAW station withdrawal |
| loop was in standby at the time of the alarm. Results of all surveys         |
| performed during the emergency response were less than MDA. At 2102 hours,   |
| an all clear was granted on the emergency response. PORTS is reporting this  |
| alarm as a valid actuation of a 'Q' Safety System.                           |
|                                                                              |
| "This is reportable to the NRC as a valid actuation of a 'Q' Safety System   |
| in accordance with Safety Analysis Report, section 6.9 (24-HOUR REPORT)."    |
|                                                                              |
| *** UPDATE/RETRACTION AT 1639 ON 11/07/00 FROM ERIC SPAETH TO LEIGH TROCINE  |
| ***                                                                          |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth      |
| personnel:                                                                   |
|                                                                              |
| "An engineering evaluation performed following the event determined that the |
| small leak, which caused the smoke head actuation, originated from the LAW   |
| 1A compressor.  This compressor had been shutdown for several weeks prior to |
| the event for maintenance.  Engineering determined that the compressor had   |
| been purged to a UF6 negative and subsequently pressurized to atmosphere to  |
| allow work to be performed.  The compressor was in Mode IV (Shutdown) when   |
| the smoke head actuation occurred."                                          |
|                                                                              |
| "Based on the above, the plant conditions that the CADP smoke detection      |
| system was designed to protect against were not present when the small leak  |
| occurred, and this event may be retracted."                                  |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector.  The NRC           |
| operations officer notified the R3DO (Wright) and NMSS EO (Brach).           |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37487       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 11/04/2000|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 08:27[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/04/2000|
+------------------------------------------------+EVENT TIME:        08:22[EST]|
| NRC NOTIFIED BY:  THOMAS VEITCH                |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE EOF DUE TO PLANNED MAINTENANCE                          |
|                                                                              |
| "LOSS OF POWER TO THE EMERGENCY OPERATIONS FACILITY.  THIS IS A PREPLANNED   |
| MAINTENANCE ACTIVITY ON BREAKER H2110.  THE REMOVAL OF THIS BREAKER CAUSES   |
| THE FACILITY (EOF) TO LOSE POWER AND IS, THEREFORE, 'POTENTIALLY'            |
| UNAVAILABLE FOR GREATER THAN 90 MINUTES.  THE TOTAL ESTIMATED DURATION OF    |
| THE ACTIVITY IS 8 HOURS."                                                    |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
|                                                                              |
| * * * UPDATE  AT 1040EST ON 11/7/00 FROM BRUCE LUTHANEN TO S. SANDIN * * *   |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "Event Notification 37487 is hereby retracted, This notification reported    |
| the unavailability of the Emergency Operations Facility (EOF) due to an      |
| electrical maintenance activity that removed power from the EOF, as required |
| by plant operating procedures.                                               |
|                                                                              |
| "The guidance for the one-hour call reporting criteria was obtained from a   |
| plant instruction which specifically stated that a one-hour-call to the NRC  |
| shall be made 'if, in the judgment of the Control Room Shift Supervisor,     |
| equipment failure or extensive maintenance activities have or will render    |
| one or more of the Perry onsite ERFs [Emergency Response Facilities]         |
| unavailable..'                                                               |
|                                                                              |
| "10 CFR 50.72(b)(1)(v) requires one-hour, non-emergency notification for     |
| 'any event that results in a major loss of emergency assessment capability,  |
| offsite response capability, or communications capability (e.g. significant  |
| portion of control room indication, Emergency Notification System or offsite |
| notification system.)'                                                       |
|                                                                              |
| "The EOF electrical maintenance was a planned, scheduled activity. The       |
| Alternate Emergency Operations Facility was available during this time to    |
| provide redundancy of all required EOF features dealing with emergency       |
| assessment and offsite communication. This capacity was never lost or        |
| degraded, and so the criteria for reporting were not met. There is no        |
| corresponding section under 10 CFR 50.73, and so an LER is not required."    |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R3DO(Wright).    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37498       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 11/07/2000|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 05:30[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        11/07/2000|
+------------------------------------------------+EVENT TIME:        02:31[EST]|
| NRC NOTIFIED BY:  PETE ORPHANOS                |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) ISOLATED AND INOPERABLE DUE TO FAILED |
| STEAM LEAK DETECTION SYSTEM TEMPERATURE ELEMENT                              |
|                                                                              |
| "On November 7, 2000 at 0231[EST] Limerick Generating Station received a     |
| High Pressure Coolant Injection (HPCI) System isolation due to a failed      |
| Steam Leak Detection System temperature element. Outboard isolation valves   |
| HV-055-2F003, HV-055-2F100, HV-055-2F041 and HV-055-2F042 received isolation |
| commands. The system isolated as designed.  Investigation [into] the cause   |
| of the failed temperature element is ongoing. The HPCI system remains        |
| isolated and inoperable."                                                    |
|                                                                              |
| Unit 2 is in a 14-day LCO A/S.  Other ECCS equipment has been verified       |
| operable.  The licensee informed the NRC resident inspector.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37499       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 11/07/2000|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 06:35[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        11/07/2000|
+------------------------------------------------+EVENT TIME:        05:10[CST]|
| NRC NOTIFIED BY:  JIM HUNTER                   |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEDICATED TELEPHONE SYSTEM FOR STATE NOTIFICATIONS INOPERABLE                |
|                                                                              |
| During testing of the Emergency Notification Network (ENN) to the states of  |
| Georgia and Alabama, the system failed producing a constant hum on the       |
| speaker in the control room.  The licensee notified their Birmingham office  |
| to initiate repairs.  There is currently no estimate available for           |
| restoration.  The licensee informed the affected states via commercial       |
| telephone and will inform the NRC resident inspector.                        |
|                                                                              |
| * * * UPDATE 0919EST ON 11/7/00 FROM ROBERT FUCICH TO S. SANDIN * * *        |
|                                                                              |
| The licensee returned the ENN system to service as of 0744EST and will       |
| inform the NRC resident inspector.  Notified R2DO(Bonser).                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37500       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/07/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 12:23[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/06/2000|
+------------------------------------------------+EVENT TIME:        12:49[CST]|
| NRC NOTIFIED BY:  DON POPP                     |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSITIVE FOR-CAUSE TEST FOR ALCOHOL REPORTED IN ACCORDANCE WITH 10 CFR       |
| 26.73.a(2)(ii)                                                               |
|                                                                              |
| A contract supervisor was determined to be under the influence of alcohol    |
| during a for-cause test.  The individual's site access was suspended, and    |
| the individual was subsequently terminated.  (Contact the NRC operations     |
| officer for addition details.)                                               |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the NRC |
| Region 3 office.                                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37501       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 11/07/2000|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 16:55[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/07/2000|
+------------------------------------------------+EVENT TIME:        15:01[EST]|
| NRC NOTIFIED BY:  RUSS GUMBERT                 |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FEEDWATER ISOLATION DUE TO CYCLING OF A BOILER FEED (BF) VALVE AND THE       |
| SUBSEQUENT STEAM GENERATOR WATER LEVEL PERTURBATION                          |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The] 21 steam generator level rose to the high-high level trip setpoint of |
| 67% narrow range level at which time a feedwater isolation signal was        |
| generated.  This is an [engineered safety feature (ESF)] actuation.  The     |
| plant is in Mode 4 at 332F reactor coolant system temperature with [four]   |
| reactor coolant pumps in service.  Steam generator levels were being         |
| maintained by intermittent feed with the main feed system and auxiliary feed |
| system in standby.  Temperature control is via steam dumps to [the]          |
| condenser.  The 21 through 24BF13s and BF40s went closed.  With the          |
| exception of [the] 21BF19, the 22 through 24BF19s were already closed.  The  |
| 21BF19 went closed due to the high-high level.  The condition was caused by  |
| cycling open of [the] 21BF19 during troubleshooting of position indication.  |
| [The] feedwater isolation is currently reset, and steam generator levels are |
| being maintained with main feed as prior to the event.  No other steam       |
| generator levels were effected, and 21 steam generator level is returned to  |
| the pre-event level of [approximately] 40% narrow range."                    |
|                                                                              |
| The licensee stated that all systems functioned as required.                 |
|                                                                              |
| The licensee plans to notify the NRC resident inspector and the Lower        |
| Alloways Creek Township.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37502       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 11/07/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 18:18[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        11/07/2000|
+------------------------------------------------+EVENT TIME:        14:00[EST]|
| NRC NOTIFIED BY:  RICKY E. RAWLS               |LAST UPDATE DATE:  11/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING THE DISCOVERY OF A DEAD SEA TURTLE IN THE     |
| INTAKE                                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The unit] was operating 100% with all [systems] normal for MODE 1.         |
| Maintenance was pulling an intake structure BAR rack in preparation for      |
| routine cleaning when the crew noticed a partially decomposed sea turtle     |
| floating to the surface.  The dead sea turtle was retrieved and sent to the  |
| National Marine Fisheries Service (NMFS) for analysis."                      |
|                                                                              |
| "NMFS has previously conducted an endangered species Act consultation with   |
| the NRC and FPC.  This consultation resulted in the establishment of sea     |
| turtle protection criteria under a Biological Opinion and an Incidental Take |
| Statement.  This turtle discovery is within the sea turtle protection        |
| criteria established by the NMFS with FPC.  A written report will be         |
| submitted to NMFS."                                                          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+