Event Notification Report for June 30, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/29/2000 - 06/30/2000

                              ** EVENT NUMBERS **

37075  37130  37131  37132  37133  37134  37135  37136  37137  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37075       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 06/09/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 20:00[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        06/09/2000|
+------------------------------------------------+EVENT TIME:        18:30[EDT]|
| NRC NOTIFIED BY:  FRANK CIGANIK                |LAST UPDATE DATE:  06/29/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS MOSLAK        R1      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LICENSEE MAY HAVE EXCEEDED LICENSED THERMAL POWER LIMIT                      |
|                                                                              |
| While reviewing the plants thermal performance, Oyster Creek discovered that |
| the plant was potentially operating above the Technical Specification        |
| licensed thermal limit.  Based on a comparison of the various inputs to the  |
| plant's thermal heat balance, it appears that the total feedwater flow       |
| venturi is reading non-conservatively (lower than actual) in comparison to   |
| the summation of the individual feedwater strings flows.  As a result of     |
| this disparity, the plant's Engineering Staff has tentatively concluded that |
| the heat balance is non-conservatively calculating 5 MWth less than actual   |
| based on the lower flow reading.                                             |
|                                                                              |
| The plant's Technical Specification steady-state thermal power limit is 1930 |
| MWth. Oyster Creek has administratively limited thermal power to 1920 MWth   |
| until this situation can be fully analyzed. The plant's Engineering Staff is |
| presently developing a plan to confirm this information and initiate the     |
| appropriate corrective actions to resolve this disparity.                    |
|                                                                              |
| This condition has been determined reportable under the plant's Technical    |
| Specifications Section 2.E (24 Hour Notification) which requires             |
| notification of the NRC for all Technical Specification violations. The      |
| plant's Technical Specifications require maintaining core thermal power less |
| than 1930 MWth under steady-state conditions and the plant might have been   |
| operated for prolonged periods at as high as 1935 MWth. The safety           |
| significance of this discrepancy is minimal because the plant's licensing    |
| bases includes a 2% error margin which was never challenged.                 |
|                                                                              |
| * * * RETRACTION 1623 6/29/2000 FROM FULLER TAKEN BY STRANSKY * * *          |
|                                                                              |
| "After further review, it has been determined that Oyster Creek Nuclear      |
| Generating Station did not operate above the licensed limit of 1930 MWt, and |
| we are retracting the notification made on 6/9/00. We determined that the    |
| mismatch between the computer generated heat balance and the manual heat     |
| balance was due to a feedwater heater leak, and not due to degradation of    |
| the final feedwater venturi. The feedwater heater leak will be repaired at   |
| the earliest opportunity during the upcoming scheduled refueling outage. As  |
| a result, Oyster Creek Nuclear Generating Station has removed the            |
| administrative thermal power limit of 1915 MWt, and has returned to full     |
| power."                                                                      |
|                                                                              |
| The NRC resident inspector will be informed of this retraction. Notified     |
| R1DO (Rogge).                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37130       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SIEMENS POWER CORPORATION            |NOTIFICATION DATE: 06/29/2000|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 00:55[EDT]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        06/28/2000|
|           FABRICATION & SCRAP RECOVERY         |EVENT TIME:        21:15[PDT]|
|           COMMERICAL LWR FUEL                  |LAST UPDATE DATE:  06/29/2000|
|    CITY:  RICHLAND                 REGION:  4  +-----------------------------+
|  COUNTY:  BENTON                    STATE:  WA |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1227              AGREEMENT:  Y  |GAIL GOOD            R4      |
|  DOCKET:  07001257                             |JOHN HICKEY          NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  LOREN MAAS                   |PETER PRESCOTT       RCT     |
|  HQ OPS OFFICER:  DOUG WEAVER                  |GABRINI              DOE     |
+------------------------------------------------+TURMAN               NRC     |
|EMERGENCY CLASS:          ALE                   |                             |
|10 CFR SECTION:                                 |                             |
|AAEC                     EMERGENCY DECLARED     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ALERT DECLARED - OFFSITE FIRE                                                |
|                                                                              |
| RANGE FIRE ON AND ADJACENT TO THE HANFORD NUCLEAR RESERVATION HAS PROMPTED   |
| BENTON COUNTY EMERGENCY MANAGEMENT, IN CONJUNCTION WITH LOCAL LAW            |
| ENFORCEMENT, TO REQUIRE A PRECAUTIONARY EVACUATION OF THE HORN RAPIDS        |
| TRIANGLE INDUSTRIAL AREA IN WHICH THE SIEMENS FUEL FABRICATION PLANT IS      |
| LOCATED.   THE PLANT PRODUCTION HAS BEEN SHUT DOWN.  ESSENTIAL PLANT         |
| PERSONNEL ARE ONSITE.   BASED ON DISTANCE AND CURRENT WIND DIRECTION, THE    |
| PLANT IS NOT THREATENED.                                                     |
|                                                                              |
| * * * UPDATE AT 0451 ON 6/29/00 BY PROBASCO, RECEIVED BY WEAVER * * *        |
|                                                                              |
| THE ALERT WAS TERMINATED AT 0150 PDT BECAUSE THE FIRE HAS MOVED FURTHER AWAY |
| FROM THE SITE AND IS CONTINUING TO MOVE IN THAT DIRECTION.                   |
|                                                                              |
| NRC NOTIFIED RDO (GOOD); EO (HICKEY); IRO (MILLER); FEMA (STEINDURF); DOE    |
| (STAMBAUGH); NRC (TURMAN)                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37131       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/29/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 09:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/28/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:32[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/29/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MELVYN LEACH         R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TONY HUDSON                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT                                                |
|                                                                              |
| Loss of one of two criticality controls was lost in Drum Room of the C-331   |
| building.  The controlled parameter is moderation.  The temperature control  |
| was lost when the door to the room was left open, this allowed the room      |
| temperature to drop below the NCSA specified limit of 105 F (the lowest      |
| temperature reached was 103 F).   The other controlled parameter, pressure,  |
| was maintained throughout this event.                                        |
|                                                                              |
| The cause of the door being left open is under investigation.  The plant     |
| notified the NRC resident inspector.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37132       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 06/29/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 09:50[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        06/29/2000|
+------------------------------------------------+EVENT TIME:        06:22[PDT]|
| NRC NOTIFIED BY:  MIKE KELLER                  |LAST UPDATE DATE:  06/29/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY CALL RELATED TO BRUSH FIRE                                          |
|                                                                              |
| This is a courtesy call regarding a brush fire located in the vicinity of    |
| the Columbia Generating Station located within the Department of Energy      |
| (DOE) Hanford Area in South Eastern portion Washington State.  Columbia      |
| Generating Station is monitoring a brush fire (30,000 to 40,000 acres)       |
| located 2 to 4 miles west of the station. Currently the local Benton County  |
| Emergency Operations Center (EOC) and the DOE EOC are coordinating fire      |
| fighting efforts.                                                            |
|                                                                              |
| Current weather forecast anticipate winds climbing to 30 knots with          |
| continued hot & dry weather.  At present the access roads to the station     |
| remain open with the DOE restricting access to essential personnel only.     |
| The DOE has indicated that later this morning a substantial increase in      |
| federal fire fighting assets will be available to fight the fire.            |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37133       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/29/2000|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 12:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/28/2000|
+------------------------------------------------+EVENT TIME:        16:53[CDT]|
| NRC NOTIFIED BY:  JIM MORRIS                   |LAST UPDATE DATE:  06/29/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PLANT FOUND TO BE IN A CONDITION OUTSIDE OF TECHNICAL SPECIFICATIONS         |
|                                                                              |
| "On June 28, 2000, at 1653 hours, it was determined that Containment         |
| Penetration M-85 was not properly isolated in accordance with Technical      |
| Specification 3.6.3.                                                         |
|                                                                              |
| "On December 25, 1999, the 2A RCS Hot Leg Primary Sampling system Inside     |
| Containment Isolation Valve FV-4454 was declared inoperable and was          |
| deenergized in the closed position to comply with Technical Specification    |
| 3.6.3 Action b.                                                              |
|                                                                              |
| "In order to perform a stroke test on valve FV-4454, on June 12, 2000, at    |
| 1246 hours, the associated Outside                                           |
| Containment Isolation Valve FV-4456 was deenergized in the closed position   |
| to comply with Technical                                                     |
| Specification 3.6.3 Action b, and subsequently on June 13, 2000, at 1012     |
| hours, the equipment clearance order for FV-4454 was lifted and the valve    |
| was energized. However, the associated Post Accident Sampling System Outside |
| Containment Isolation Valve FV-2455/2455A for Penetration M-85 was not       |
| deactivated in the closed position as required.                              |
|                                                                              |
| "This condition was discovered on June 28, 2000, at 1653 hours, during       |
| testing and valve line-up verification on the Post Accident Sampling System. |
| Although not deenergized, valve FV-2455/2455A is a normally closed valve and |
| flow through the penetration has occurred briefly during Post Accident       |
| Sampling System testing.                                                     |
|                                                                              |
| "On June 28, 2000, at 1700 hours, Inside Containment Isolation Valve FV-4454 |
| was deenergized in the closed                                                |
| position in order to restore compliance with Technical Specification 3.6.3   |
| Action b.                                                                    |
|                                                                              |
| "This notification is being made pursuant to Operating License NPF-80        |
| Condition 2.G for operation or condition                                     |
| prohibited by Technical Specifications."                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37134       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  METOREX, INC.                        |NOTIFICATION DATE: 06/29/2000|
|LICENSEE:  METOREX, INC                         |NOTIFICATION TIME: 12:15[EDT]|
|    CITY:  EWING                    REGION:  1  |EVENT DATE:        06/28/2000|
|  COUNTY:                            STATE:  NJ |EVENT TIME:             [EDT]|
|LICENSE#:  29-30342-01           AGREEMENT:  N  |LAST UPDATE DATE:  06/29/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN ROGGE           R1      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAKE COPLAND                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SOURCE RECEIVED WITH SURFACE CONTAMINATION                                   |
|                                                                              |
| The licensee reported that a gauge containing a 40 mCi Fe-55 source (S/N     |
| 6674LG) was received with surface contamination (based upon wipe samples)    |
| calculated to be 1.37 �Ci. The licensee reported that no contamination was   |
| detected on the outside of the shipping package. The source had been shipped |
| to the licensee from AK Steel in Ashland, KY. The licensee has contacted the |
| shipper.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37135       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 06/29/2000|
|LICENSEE:  RADIOGRAPHIC SPECIALISTS, INC.       |NOTIFICATION TIME: 16:51[EDT]|
|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        06/27/2000|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CDT]|
|LICENSE#:  L02742                AGREEMENT:  Y  |LAST UPDATE DATE:  06/29/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GAIL GOOD            R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS (FACSIMILE)    |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| The film badge of a radiographer for Radiographic Specialists, Houston, TX,  |
| received an exposure of 5.755R during the period from 5/10/00-6/9/00. The    |
| licensee reported that the individual may have left the film badge clipped   |
| to his shirt in a high radiation area. The State of Texas is investigating   |
| the incident.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37136       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 06/29/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 17:06[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        06/29/2000|
+------------------------------------------------+EVENT TIME:        16:44[EDT]|
| NRC NOTIFIED BY:  GOODLAVAGE                   |LAST UPDATE DATE:  06/29/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT OUTSIDE DESIGN BASIS DUE TO 10 CFR PART 50 APPENDIX R ISSUE             |
|                                                                              |
| "10 CFR 50, Appendix R, Section (III)(L)(5) requires that alternate and      |
| dedicated shutdown facilities have the means to achieve and maintain cold    |
| shutdown condition within 72 hours. TMI committed to this requirement.       |
|                                                                              |
| "Review of current analysis has determined that the commitment to achieve    |
| cold shutdown within 72 hours cannot be met. At 1644 on 6/29/00, this        |
| condition has been determined to be reportable under 10 CFR 50.72            |
| (b)(1)(ii)(B), which says 'any event or condition during operation that      |
| results in the condition of the nuclear power plant, including its principal |
| safety barriers, being seriously degraded or results in the nuclear power    |
| plant being in a condition that is outside of the design basis of the        |
| plant.' It has been determined that the equipment is operable, but in a      |
| nonconforming condition since the 10 CFR 50 Appendix R requirement to        |
| achieve cold shutdown within 72 hours cannot be achieved."                   |
|                                                                              |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37137       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 06/30/2000|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 00:28[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/29/2000|
+------------------------------------------------+EVENT TIME:        21:12[EDT]|
| NRC NOTIFIED BY:  REINSBURROW                  |LAST UPDATE DATE:  06/30/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        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       92       Power Operation  |92       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - FAILURE OF A WARNING SIREN                            |
|                                                                              |
| During normal plant operations, a spurious and sustained actuation of siren  |
| #7 of the Off Site Emergency Warning System occurred.  The actuation was not |
| as a result of personnel actions.  Local government agencies were notified.  |
| The affected siren actuated at 2112 and was deactivated at 2201.  The area   |
| covered by the siren has been placed on backup route alerting.               |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
+------------------------------------------------------------------------------+


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