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Event Notification Report for June 18, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/17/1999 - 06/18/1999

                              ** EVENT NUMBERS **

35790  35833  35835  35836  35837  35838  35839  35840  35841  35842  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35790       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/03/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/02/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/17/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  THOMAS WHITE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour   |
| report)                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified  |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems  |
| in C-337 and 1 system in C-333, such that the ability of the sprinklers to   |
| flow sufficient water was called into question.  Subsequently, these         |
| sprinkler systems were declared inoperable, and TSR-required actions         |
| establishing roving fire patrols were initiated.  This deficiency was        |
| detected during scheduled system inspections conducted by Fire Protection    |
| personnel.  Currently, functionality of the sprinkler heads has not been     |
| fully evaluated by Fire Protection personnel, and the remaining cascade      |
| buildings are currently being inspected, and if necessary, this report will  |
| be updated to identify any additional areas.                                 |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| The NRC resident inspector has been notified of this event.                  |
|                                                                              |
| ******************** UPDATE RECEIVED AT 1022 EDT ON 06/04/99 FROM CAGE TO    |
| TROCINE *******************                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "Two sprinkle heads on system D-1 in C-337 and two sprinkler heads on system |
| 27 in C-335 were identified to also be corroded.  These were identified to   |
| the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, and determined   |
| to require an update to this report by the PSS.                              |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| Paducah personnel notified the NRC resident inspector of this update.  The   |
| NRC operations officer notified the R3DO (Hills) and NMSS EO (Combs).        |
|                                                                              |
| *********** UPDATE RECEIVED AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER  |
| ***********                                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 |
| in C-333 were identified to also be corroded.  The PSS was notified of this  |
| condition at 1300 CDT on 06/17/99 and determined that an update to this      |
| report was required."                                                        |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| Paducah personnel notified the NRC resident inspector of this update.  The   |
| NRC operations officer notified the R3DO (Madera).                           |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35833       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 19:01[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        15:40[PDT]|
| NRC NOTIFIED BY:  BARBARA HANSEN-HARRIS        |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT                                                     |
|                                                                              |
| Unescorted access granted inappropriately, immediate compensatory measures   |
| taken upon discovery.  The licensee notified the NRC Resident Inspector.     |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
|                                                                              |
| * * * RETRACTION 1215 6/17/99 FROM BARBARA HANSEN-HARRIS TAKEN BY STRANSKY * |
| * *                                                                          |
|                                                                              |
| After discussion with the Region IV security inspector, the licensee has     |
| determined that this event is loggable, and not reportable.  The NRC         |
| resident inspector will be informed by the licensee.  Notified R4DO          |
| (Pellet).                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35835       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 09:06[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        08:26[EDT]|
| NRC NOTIFIED BY:  DOUGLAS PETERSON             |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| A CONTRACTOR HAD HIS SITE ACCESS REVOKED DUE TO A  DISCOVERY MADE RELATING   |
| TO HIS PREVIOUS WORK HISTORY.  THE LICENSEE WILL NOTIFY THE NRC RESIDENT     |
| INSPECTOR.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35836       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 12:01[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        10:15[EDT]|
| NRC NOTIFIED BY:  PETER GARDNER                |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT ESF ACTUATION.                                                   |
|                                                                              |
| During preparations for overspeed surveillance testing of the D23 diesel     |
| generator an inadvertent 'C' emergency service water pump start signal was   |
| received causing the pump to start.  The cause of the event was personnel    |
| error by an I&C technician during installation of a speed signal generator.  |
| The speed tachometer was being calibrated and was set at 900 rpm when the    |
| speed signal generator used for overspeed testing was hooked up.  Normally   |
| the calibration would be complete and the signal generator set at zero rpm   |
| prior to hookup.  All systems responded as expected.                         |
|                                                                              |
| The NRC resident inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35837       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/17/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:15[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/16/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:31[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/17/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN MADERA          R3      |
|  DOCKET:  0707002                              |FREDRICK COMBS       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  WILLIAM POERTNER             |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:                                |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ACTUATION OF A "Q" SAFETY SYSTEM.                                            |
|                                                                              |
| At 1631 hours on 6/16/99, operations personnel responded to a high voltage   |
| outleakage smokehead alarm at the X-333 Low Assay Withdrawal (LAW) condenser |
| accumulator area.  Operators responded per alarm response procedures and     |
| checked for outleakage and observed smoke at Instrument Control Panel (ICP)  |
| Number 13.  Operators immediately evacuated the area, called 911, and        |
| initiated a building recall.                                                 |
|                                                                              |
| The Emergency Response Organization (ERO) responded and monitored air        |
| quality for hydrogen fluoride, airborne radioactivity, and surveyed for      |
| surface contamination.  All sample results were less than minimum detectable |
| activity.  Investigation determined that a Dalton fitting in ICP#13 was      |
| cross threaded and was considered a possible source of the outleakage.       |
|                                                                              |
| This is reportable as a valid actuation of a "Q" safety system in accordance |
| with Safety Analysis Report, Section 6.9 (24-Hour Report).                   |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35838       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 17:27[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        13:37[CDT]|
| NRC NOTIFIED BY:  DON SMITH                    |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|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                                   
+------------------------------------------------------------------------------+
| INADVERTENT ESF ACTUATION.                                                   |
|                                                                              |
| During the performance of a scheduled surveillance 2-SR-3.3.5.1.2(ATU        |
| C)/Core and Containment Cooling Systems Analog Trip Unit Functional Test,    |
| Relay 2-RLY-073-23A-K36 was required to have inhibits (boots) installed to   |
| prevent HPCI valves (PCIS GP-4 isolation) from actuating due to a simulated  |
| high steam flow condition.  At 1337 CDT on June 17, 1999, Unit 2 received a  |
| group 4 HPCI isolation during the performance of step 7.15.15 of the         |
| surveillance procedure.  The licensee determined that the wrong contacts had |
| been inhibited allowing the actuation to occur.  The inhibits were removed   |
| and the PCIS GP-4 isolation was reset at 1402 CDT returning HPCI to an       |
| operable condition.                                                          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35839       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 18:16[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        16:30[EDT]|
| NRC NOTIFIED BY:  G FIEDLER                    |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THREE OF FOUR MAIN STEAM RELIEF VALVES (MSRV) CONEX CONNECTORS INSTALLED     |
| BACKWARDS.                                                                   |
|                                                                              |
| While shutdown the licensee determined that 3 of 4 MSRV's had the conex      |
| connectors installed backwards.  The connectors provide the environmental    |
| qualification seal to the pilot solenoid valve.  ADS may not have functioned |
| under elevated drywell temperature conditions.                               |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35840       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/17/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 21:01[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        17:22[CDT]|
| NRC NOTIFIED BY:  S MARIK                      |LAST UPDATE DATE:  06/17/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION.                                                               |
|                                                                              |
| At 1722 CDT the 2D primary containment vacuum breaker 2PC001D went from the  |
| closed (normal) position to an indicated dual position.  The valve is        |
| actuated by a differential pressure between the suppression chamber and the  |
| drywell air space and is designed to open at 0.5 psid or less.  Differential |
| pressure at 1722 CDT was 0.23 psid.  An operator was dispatched and the      |
| containment vacuum breaker was manually cycled.  After being manually cycled |
| the containment vacuum breaker returned to the closed position.  The         |
| licensee subsequently satisfactorily performed an operability test on the    |
| containment vacuum breaker.                                                  |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35841       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 06/18/1999|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 01:41[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        22:40[EDT]|
| NRC NOTIFIED BY:  BRUCE HOWARD                 |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INFORMATION CALL - A FIRE ON OWNER CONTROLLED PROPERTY                       |
|                                                                              |
| A fire of yet undetermined origin was discovered by a janitor at             |
| approximately 2240 hours, Thursday, June 17, in a temporary office trailer,  |
| north of the Palisades Training Building. The trailer complex is located     |
| one-half mile from the operating plant. There was no impact to the Training  |
| Building or the plant's operation, and the plant remained at full power.     |
|                                                                              |
| The control room was notified after discovery of the blaze. The control room |
| dispatched the plant's fire brigade and Covert Fire and Ambulance department |
| to the scene. The plant fire brigade began immediate setup of hoses and      |
| began initial fire fighting until the Covert Fire department arrived, some   |
| 15 minutes later.                                                            |
|                                                                              |
| Cause of the fire has not been determined. An investigation will be          |
| initiated. There were no injuries and no one was in the trailer office at    |
| the time.                                                                    |
|                                                                              |
| A safety inspection will be conducted today of all plant offices and         |
| trailers for potential fire hazards.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35842       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/18/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:48[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/18/1999|
+------------------------------------------------+EVENT TIME:        02:50[CDT]|
| NRC NOTIFIED BY:  JIM SPIELER                  |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION - VACUUM BREAKER                                               |
|                                                                              |
| At 0250 CDST 2PC001D, the 2D Primary Containment Vacuum Breaker went from    |
| the (normal) closed position to an indicated dual position.  Locally it was  |
| determined that the valve was just cracked open.  The valve is designed to   |
| open when Suppression chamber pressure is approximately 0.5 psig greater     |
| than Drywell pressure.  When the vacuum breaker opened the aforementioned    |
| differential pressure was approximately 0.2 psid.  The vacuum breaker was    |
| closed by an Equipment Attendant and then cycled per LOS-PC-M2 "Unit 2       |
| Drywell-Suppression Pool Vacuum Breaker Operability Test for Condition 1,2   |
| and 3" to verify proper operation. The valve cycled satisfactorily.          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| NOTE:  THIS  IS SIMILAR TO EVENT 35840.                                      |
+------------------------------------------------------------------------------+