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Event Notification Report for July 19, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/16/1999 - 07/19/1999

                              ** EVENT NUMBERS **

35922  35923  35924  35925  35926  35927  35928  35929  35930  35931  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35922       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 07/15/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 16:45[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        07/15/1999|
+------------------------------------------------+EVENT TIME:        14:44[EDT]|
| NRC NOTIFIED BY:  KATHLEEN BRESLIN             |LAST UPDATE DATE:  07/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP FROM 100% POWER DURING RPS      |
| TESTING.                                                                     |
|                                                                              |
| THE McGUIRE UNIT 2 REACTOR TRIPPED FROM 100% POWER.  THE TRIP INVOLVED AN    |
| AUTOMATIC ACTUATION OF THE REACTOR PROTECTION SYSTEM (RPS).  INVESTIGATION   |
| OF THE CAUSE OF THE REACTOR TRIP IS IN PROGRESS AND IS BELIEVED TO BE FROM   |
| 'A' TRAIN SOLID STATE PROTECTION SYSTEM (SSPS) TESTING.  THE '2A' AUXILIARY  |
| FEEDWATER  PUMP DID NOT START AUTOMATICALLY AND WAS MANUALLY STARTED.        |
|                                                                              |
| UNIT 2 IS CURRENTLY STABLE IN MODE 3.  NO PRIMARY OR SECONDARY POWER         |
| OPERATED RELIEF VALVES OR SAFETY VALVES LIFTED DURING THE TRANSIENT.  ALL    |
| CONTROL RODS FULLY INSERTED.  THE MAIN FEEDWATER SYSTEM HAS BEEN RESTORED    |
| WITH DECAY HEAT BEING REJECTED TO THE MAIN CONDENSER.  THE EMERGENCY DIESEL  |
| GENERATORS ARE AVAILABLE, IF NEEDED.  THE LICENSEE INFORMED THE NRC RESIDENT |
| INSPECTOR.                                                                   |
|                                                                              |
| * * * UPDATE AT 0730 EDT ON 7/16/99 BY THAD REAMES TO FANGIE JONES * * *     |
|                                                                              |
| The cause of the reactor trip was determined to be a turbine trip while      |
| reactor power was greater than 48%.  The turbine trip was due to testing     |
| that was being performed on the '2A' reactor trip breaker after it had been  |
| replaced.  The test caused the turbine trip signal because the new reactor   |
| trip breaker had a bad set of contacts in it.  The '2A' reactor trip breaker |
| has been replaced and verified operable.                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The Headquarters          |
| Operations Officer notified the R2DO (Ann Boland).                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35923       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MD RADIOLOGICAL HEALTH PROGRAM       |NOTIFICATION DATE: 07/16/1999|
|LICENSEE:  KCI TECHNOLOGIES                     |NOTIFICATION TIME: 10:44[EDT]|
|    CITY:  LAYTONSVILLE             REGION:  1  |EVENT DATE:        07/15/1999|
|  COUNTY:  MONTGOMERY                STATE:  MD |EVENT TIME:        15:30[EDT]|
|LICENSE#:  MD-05-150-01          AGREEMENT:  Y  |LAST UPDATE DATE:  07/16/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN WHITE           R1      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DONNA GAINES                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED TROXLER MOISTURE/DENSITY GAUGE                                       |
|                                                                              |
| The state of Maryland reported that a Troxler moisture/density gauge, model  |
| number 3411B and serial number 11038, was damaged (run over) at  the Oaks    |
| Sanitary Landfill in Laytonsville, MD on 7/15/99.  The state responded to    |
| the scene along with the licensee's Radiation Safety Office (KCI             |
| Technologies of Baltimore, MD).  The gauge was damaged.  The source was in   |
| the shielded position. The gauge was surveyed and it was determined that the |
| shielding had not been compromised.  The gauge was returned to the           |
| licensee's facility in Baltimore and will be shipped to Troxler for          |
| disposal.                                                                    |
|                                                                              |
| There were no personnel overexposures or contaminations, and the source was  |
| still intact.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35924       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 07/16/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 13:24[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/16/1999|
+------------------------------------------------+EVENT TIME:        12:45[EDT]|
| NRC NOTIFIED BY:  VINCENT FALLACARA            |LAST UPDATE DATE:  07/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           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                                   
+------------------------------------------------------------------------------+
| LICENSEE IDENTIFIED DURING OPERATOR REQUALIFICATION A CONDITION WHICH PLACES |
| THE UNIT OUTSIDE THE DESIGN BASES.                                           |
|                                                                              |
| "PDC99.05 (EDG breaker logic modification) could prevent B6 [swing bus] from |
| automatically re-energizing during a LOCA coincident with degraded voltage.  |
|                                                                              |
| "A LOCA with degraded voltage will delay the de-energization of the 480V     |
| load centers BI and B2.  The EDG's will start immediately on the LOCA signal |
| and the new design will have the EDG 10 second timer working in parallel     |
| with the degraded voltage 10 second timer.  Once the degraded voltage relay  |
| times out the 4KV buses A5 and A6 will be isolated and the EDGs will load    |
| within a couple of seconds.  This time will not allow the B6 transfer        |
| breaker time to precharge and thus leave bus B6 de-energized.                |
|                                                                              |
| "The problem was identified during review of [Problem Report] PR99.9417.     |
|                                                                              |
| "[The cause of the problem was that ] the design did not consider the        |
| pre-charging time of the B6 feeder breakers.                                 |
|                                                                              |
| "[Corrective actions taken included a determination that ] the EDG,          |
| emergency distribution system and ECCS systems are operable.  The basis for  |
| operability identified in Engineering Evaluation EE98-54 (operability        |
| evaluation OP98-34) still apply."                                            |
|                                                                              |
| The corrective action includes verifying grid stability and, if a degraded   |
| voltage condition exists, starting the stations EDGs and realigning the      |
| power supplies for the safeguards buses.  The licensee informed the NRC      |
| Resident Inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35925       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TVA                                  |NOTIFICATION DATE: 07/16/1999|
|LICENSEE:  TVA                                  |NOTIFICATION TIME: 15:41[EDT]|
|    CITY:  CHATTANOOGA              REGION:  2  |EVENT DATE:        07/11/1999|
|  COUNTY:  HAMILTON                  STATE:  TN |EVENT TIME:        18:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  07/16/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANN BOLAND           R2      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARCIA COOPER                |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TVA TESTING AND MAINTENANCE DIVISION LOCATED IN CHATTANOOGA, TN, REPORTED    |
| THAT A HANDHELD X-MET ANALYZER CONTAINING 40 MILLICURIES OF IRON-55 AND 10   |
| MILLICURIES OF CADMIUM-109 WAS INADVERTENTLY LEFT UNATTENDED ON A LOADING    |
| DOCK BETWEEN APPROXIMATELY 1000-1100 EDT ON 7/10/99 THROUGH 1800-2000 EDT ON |
| 7/11/99.   THERE WAS NO INDICATION OF TAMPERING, CONTAMINATION OR PERSONNEL  |
| OVEREXPOSURE INVOLVED.   THIS DEVICE IS USED FOR METAL IDENTIFICATION AND    |
| FALLS UNDER A GENERAL LICENSE.  THIS REPORT WAS CONSERVATIVELY MADE UNDER    |
| 10CFR20.2201(a).                                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35926       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 07/16/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        07/16/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  07/16/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |RONALD GARDNER       R3      |
|  DOCKET:  0707002                              |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RON CRABTREE                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR REPORT INVOLVING COURTESY NOTIFICATION TO OSHA FOLLOWING AN EMPLOYEE  |
| WORK INJURY.                                                                 |
|                                                                              |
| "On 7/16/99 at 1028 hours, it was reported to Emergency Responders that an   |
| employee had been injured by an electrical flash while performing            |
| Preventative Maintenance on a 480volt system.  Emergency Medical             |
| Technicians/Paramedics responded to the scene and treated/stabilized         |
| employee and transported the employee to an area hospital for further        |
| treatment.  At approximately 1600 hours, The PORTS ES&H Manager made a       |
| courtesy notification to OSHA regarding this injury/accident.  This          |
| notification to another government agency is reportable to NRC as a          |
| four-hour notification report."                                              |
|                                                                              |
| The NRC Resident Inspector and DOE Site Representative were informed.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35927       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 07/16/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 19:25[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/16/1999|
+------------------------------------------------+EVENT TIME:        19:12[EDT]|
| NRC NOTIFIED BY:  CHARLES TRIPLETT             |LAST UPDATE DATE:  07/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|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       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO THE LOSS OF BOTH A     |
| BATTERY CHARGER AND ITS ASSOCIATED RECTIFIER.                                |
|                                                                              |
| "WHILE TESTING #2 EMERGENCY DIESEL GENERATOR, THE SUPPLY BREAKER FROM THE    |
| NORMAL 4KV BUS TRIPPED OPEN ON AN OVERCURRENT SIGNAL.  THE #2 EMERGENCY      |
| DIESEL GENERATOR WAS TRIPPED DUE TO INDICATED LOW EXCITATION VOLTAGE.  THIS  |
| LED TO A LOSS OF POWER TO THE DF EMERGENCY BUS.  NUMBER 2 AND 4 BATTERY      |
| CHARGERS BECAME INOPERABLE AND ENTRY INTO TECH SPEC 3.0.3 ACTION STATEMENT   |
| OCCURRED.  TECH SPEC REQUIRED SHUTDOWN WAS INITIATED AT 1912[EDT].           |
| INVESTIGATION IS CONTINUING TO DETERMINE CAUSE OF BREAKER TRIP."             |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| * * * UPDATE 2108EDT ON 7/16/99 FROM CHARLES TRIPLETT TO S. SANDIN * * *     |
|                                                                              |
| THE LICENSEE IS UPDATING THIS REPORT TO INCLUDE AN ESF ACTUATION OF THE #2   |
| EMERGENCY DIESEL GENERATOR.                                                  |
|                                                                              |
| "AFTER BEING MANUALLY TRIPPED AT 1729[EDT] DUE TO INDICATED LOW EXCITATION   |
| VOLTAGE, THE #2 EMERGENCY DIESEL GENERATOR SUBSEQUENTLY RESTARTED            |
| AUTOMATICALLY AT 1812[EDT] WHEN DIESEL GENERATOR AUTO/LOCAL CONTROL SWITCH   |
| WAS TAKEN TO THE LOCAL POSITION.  THE DIESEL OUTPUT BREAKER CONTROL SWITCH   |
| WAS IN PULL-TO-LOCK AND DID NOT RECLOSE.  INVESTIGATION INTO THE CAUSE OF    |
| THE AUTO START IS CONTINUING.                                                |
|                                                                              |
| "UPDATING [THIS REPORT], THE DE-ENERGIZED DF EMERGENCY BUS HAS BEEN          |
| RE-ENERGIZED AND BOTH BATTERY CHARGERS ARE CHARGING [THEIR] RESPECTIVE       |
| BATTERIES.  THE BATTERIES ARE INOPERABLE DUE TO LOW PILOT CELL VOLTAGE AND   |
| [THE] PLANT SHUTDOWN CONTINUES."                                             |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.  NOTIFIED R1DO(WHITE).     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35928       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 07/17/1999|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 06:16[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        07/17/1999|
+------------------------------------------------+EVENT TIME:        04:49[CDT]|
| NRC NOTIFIED BY:  DOUG SMITH                   |LAST UPDATE DATE:  07/17/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC START OF AUX BUILDING SPECIAL VENT SYSTEM                          |
|                                                                              |
| The auxiliary building special vent system received an automatic start       |
| signal from a spike on radiation monitor 1R30 (aux building vent gas         |
| radiation monitor). Redundant radiation monitor 1R37 did not show any change |
| in radiation levels. The licensee will investigate the cause of the spike on |
| monitor 1R30.                                                                |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35929       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 07/17/1999|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 11:30[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        07/17/1999|
+------------------------------------------------+EVENT TIME:        08:45[EDT]|
| NRC NOTIFIED BY:  ALAN HALL                    |LAST UPDATE DATE:  07/17/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE AGENCY CONCERNING DEAD LOGGERHEAD TURTLE FOUND |
| IN THE INTAKE CANAL.                                                         |
|                                                                              |
| THE STATE OF FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) WAS        |
| NOTIFIED OF A LOGGERHEAD TURTLE MORTALITY AT ST. LUCIE PLANT INTAKE CANAL.   |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35930       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 07/17/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:26[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/17/1999|
+------------------------------------------------+EVENT TIME:        20:21[EDT]|
| NRC NOTIFIED BY:  JIM TURNER                   |LAST UPDATE DATE:  07/17/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       64       Power Operation  |63       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO INADEQUATE ALLOWABLE   |
| TIME TO COMPLETE REPAIRS.                                                    |
|                                                                              |
| "UNIT 2 IS SHUTTING DOWN PER TECHNICAL SPECIFICATION 3.8.1.1.  THE 2-2       |
| EMERGENCY DIESEL GENERATOR WAS DECLARED INOPERABLE AT 2157 HOURS, 7/14/99,   |
| DUE TO HEAT EXCHANGER FOULING.  WHILE PERFORMING POST MAINTENANCE TESTING AT |
| 1729 [HOURS], 7/16/99, THE 2DF BUS WAS LOST APPARENTLY CAUSED BY A 2-2       |
| DIESEL GENERATOR MALFUNCTION.  THERE IS NOT ADEQUATE ALLOWABLE OUTAGE TIME   |
| REMAINING TO REPAIR AND TEST THE DIESEL GENERATOR, SO THE TECHNICAL          |
| SPECIFICATION REQUIRED SHUTDOWN IS STARTING."                                |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| HOO NOTE:  SEE EVENT #35927 FOR ADDITIONAL INFORMATION.                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35931       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 07/18/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 20:41[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        07/18/1999|
+------------------------------------------------+EVENT TIME:        18:07[EDT]|
| NRC NOTIFIED BY:  BOB BOYER                    |LAST UPDATE DATE:  07/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TWO OF THREE OPERATING REACTOR CONTAINMENT BUILDING (RCB) FANS UNEXPECTEDLY  |
| TRIPPED DURING TROUBLESHOOTING OF ENGINEERED SAFEGUARDS ACTUATION SIGNAL     |
| (ESAS) RELAYS BY A CONTROL ROOM OPERATOR (CRO).                              |
|                                                                              |
| "A CRO was checking the ESAS relays for noise, humming or signs of           |
| overheating after the relays had been exercised as a result of de-energizing |
| VBB for 1B Inverter restoration.  While trying to identify a humming relay   |
| the CRO touched what he thought was the frame of relay 1X1A RCB, but what he |
| touched actuated the relay contacts.  This caused AH-E-1B and AH-E-1C to     |
| trip.                                                                        |
|                                                                              |
| "The crew restarted AH-E-1B and AH-E-1C and followed Alarm response B-1-5    |
| '480V ES Motor Trip.'  Electrical prints (209-570 and 209-592) were referred |
| to and showed that the relay is a normally de-energized relay.  It sends a   |
| signal to the 1S and 1T 480V under voltage circuit, DH-V-4B to open and      |
| AH-E-1B/C to trip.  The UV relays were verified to have not actuated and     |
| they were manually reset as a precautionary measure.  DH-V-4B was verified   |
| still closed.                                                                |
|                                                                              |
| "It is believed since the CRO only slightly moved the relay and AH-E-1B/C    |
| contacts are normally closed when the relay is de-energized and the other    |
| three relays are normally open, that the movement was enough to break the    |
| closed contacts but not enough to make up the open contacts."                |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
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