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Event Notification Report for June 28, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/25/1999 - 06/28/1999

                              ** EVENT NUMBERS **

35790  35856  35860  35861  35862  35863  35864  35865  35866  35867  35868  35869 
35870  35871  35872  35873  35874  

+------------------------------------------------------------------------------+
|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:  06/25/1999|
|    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 one 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).                           |
|                                                                              |
| * * * UPDATE AT 1440 ON 06/18/99 FROM UNDERWOOD TAKEN BY STRANSKY * * *      |
|                                                                              |
| "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in  |
| C-333 were identified to have corrosion.  The PSS was notified of this       |
| condition at 1350 CDT on 06/18/99.  The area of the fire patrol for system   |
| C-15 was expanded to include the two heads identified as corroded.  The one  |
| head on system B-8 was in the area already being patrolled.  The PSS         |
| determined that an update to this report was required."                      |
|                                                                              |
| The NRC resident inspector has been informed of this update.  The NRC        |
| operations officer notified R3DO (Madera).                                   |
|                                                                              |
| * * * UPDATE 1315 6/25/1999 FROM WALKER TAKEN BY STRANSKY * * *              |
|                                                                              |
| "Two sprinkler heads on system D-8 and three sprinkler heads on system D-7   |
| in C-337 were identified to have corrosion.  The PSS was notified of the     |
| condition on system D-8 at 0125 on 6/25/99 and at 1019 on 6/25/99 for system |
| D-7.  Both systems were immediately declared inoperable and LCO fire patrol  |
| actions were implemented.  It was determined that an update to this report   |
| was required."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this update.  Notified R3DO  |
| (Jordan).                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35856       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. VETERANS ADMINISTRATION         |NOTIFICATION DATE: 06/24/1999|
|LICENSEE:  DURHAM VA HOSPITAL                   |NOTIFICATION TIME: 15:00[EDT]|
|    CITY:  DURHAM                   REGION:  2  |EVENT DATE:        05/28/1999|
|  COUNTY:                            STATE:  NC |EVENT TIME:        12:00[EDT]|
|LICENSE#:  32-01134-01           AGREEMENT:  Y  |LAST UPDATE DATE:  06/25/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |AL BELISLE           R2      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LYNN McGUIRE                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF IODINE-125 SEEDS INTO SANITARY SEWER                                 |
|                                                                              |
| "On May 28, 1999, two I-125 sources, with a combined activity of 0.584 mCi,  |
| were lost from the Medical Center.  The seeds had been implanted into a      |
| patient's prostate earlier in the day.  The patient had been instructed to   |
| save his urine so that any seeds passed in the urine could be recovered.  An |
| instruction sheet was posted on the door, directing that all urine, trash    |
| and linen be saved, and nurses had been trained for the procedure.  A nurse  |
| called nuclear medicine to report that two seeds were in the urine           |
| container.  When nuclear medicine personnel arrived to recover the seeds,    |
| the urine had been flushed into the sanitary sewer by another staff member   |
| on the floor.                                                                |
|                                                                              |
| "The toilet and urine container were surveyed with a portable low-energy     |
| gamma detector, and no residual activity was detected.  The sources are      |
| presumed to have gone into the sewer, and assuming the seeds remain covered  |
| by water, no significant exposure is expected to any individual member of    |
| the public.  On June 1, 1999, the loss of the sources was reported by phone  |
| to the VA National Health Physics Program.                                   |
|                                                                              |
| "In order to prevent recurrence of this type of incident, the nurses on ward |
| 7A have been retrained in the proper procedures.  In the future, implant     |
| patient rooms will be posted with larger signs saying 'hold urine, trash,    |
| linen'."                                                                     |
|                                                                              |
| * * * UPDATE AT 0950 EDT ON 6/25/99 BY KELLY MAYO TO FANGIE JONES * * *      |
|                                                                              |
| Corrected reporting criteria from 10 CFR 20.2201(a)(1)(i) to 10 CFR          |
| 20.2201(a)(1)(ii) as the activity was more than 10 times the limit, but less |
| than 1000 times the limit.  Notified the R2DO (Al Belisle) and NMSS (Larry   |
| Camper)..                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35860       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 14:32[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        10:23[CDT]|
| NRC NOTIFIED BY:  RICK PEARSON                 |LAST UPDATE DATE:  06/25/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - CONTROL ROOM VENTILATION SYSTEM INOPERABLE DUE TO A BROKEN DOOR LATCH      |
| MECHANISM -                                                                  |
|                                                                              |
| AT 1023 CDT ON 06/25/99, WITH BOTH UNITS AT 100% POWER, THE LICENSEE         |
| DISCOVERED THAT PERSONNEL ENTRY DOOR #158 TO CONTROL ROOM CHILLER ROOM #122  |
| HAD A BROKEN LATCH MECHANISM ON IT.  THIS CONSTITUTES A BREACH OF THE        |
| CONTROL ROOM SPECIAL VENTILATION SYSTEM AND THUS, BOTH TRAINS OF THE CONTROL |
| ROOM SPECIAL VENTILATION SYSTEM ARE INOPERABLE (TECH SPEC 3.13.A.1).         |
|                                                                              |
| AT 1121 CDT ON 06/25/99, PLANT TECHNICIANS REPAIRED THE BROKEN DOOR LATCH    |
| MECHANISM AND DECLARED THE VENTILATION SYSTEM OPERABLE.                      |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35861       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 15:23[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        14:30[EDT]|
| NRC NOTIFIED BY:  STEVE MAREK                  |LAST UPDATE DATE:  06/25/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |ROBERT DENNIG        NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|AENS 50.72(b)(1)(v)      ENS INOPERABLE         |CANUPP               FEMA    |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF TELEPHONE SERVICE                      |
|                                                                              |
| "At 1430, Fermi 2 determined that the Emergency Notification System (ENS)    |
| phones were not available. The local telephone company notified Fermi 2 that |
| an offsite fiber optic cable was cut. Additionally, local phone service to   |
| Monroe County, including the Monroe County Sheriffs Department is            |
| unavailable. Security radio communication to the Monroe County Sheriff is    |
| available and has been verified. RERP phone service to locations outside     |
| Monroe County is available.                                                  |
|                                                                              |
| "This report is being made in accordance with 10CFR50.72(b)(1)(v), as an     |
| event that results in a major loss of emergency response assessment          |
| capability, or communications capability.                                    |
|                                                                              |
| "At 1508, an Unusual Event was declared due to notification that the         |
| Emergency Call Out System (ECOS) may also be impaired, due to the loss of    |
| local phones."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
|                                                                              |
| * * * UPDATE 1844 6/25/99 FROM MAREK TAKEN BY STRANSKY * * *                 |
|                                                                              |
| The Unusual Event was terminated at 1838 after the ENS and offsite telephone |
| service were restored.  The licensee will inform the NRC resident inspector  |
| of this update.  Notified R3DO(Jordan), NRR EO (Hannon), FEMA (Sullivan).    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35862       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ABB COMBUSTION ENGINEERING           |NOTIFICATION DATE: 06/25/1999|
|LICENSEE:  ABB COMBUSTION ENGINEERING           |NOTIFICATION TIME: 16:34[EDT]|
|    CITY:  WINDSOR                  REGION:  1  |EVENT DATE:        06/25/1999|
|  COUNTY:                            STATE:  CT |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  06/25/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GLENN MEYER          R1      |
|                                                |VERN HODGE (via fax) NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  IAN RICKARD                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING ABB 4kV CIRCUIT BREAKERS                     |
|                                                                              |
| The following text is excerpted from a facsimile received in the Operations  |
| Center:                                                                      |
|                                                                              |
| "The defect concerns ABB 1200A 4KV Vacuum Breakers delivered to Baltimore    |
| Gas and Electric Company's Calvert Cliffs Nuclear Power Plant. Specifically, |
| the defect concerns the breaker performing a trip free operation when a      |
| close signal is received by the breaker. This defect results in the breaker  |
| failing to remain in the closed position. The defect could lead to           |
| non-conservative failure of not starting certain plant equipment upon demand |
| such as an Emergency Core Cooling Pump."                                     |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35863       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 18:52[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        09:30[CDT]|
| NRC NOTIFIED BY:  RICK HUBBARD                 |LAST UPDATE DATE:  06/27/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PERSONNEL OVEREXPOSURE                                                       |
|                                                                              |
| A worker received internal contamination resulting in an estimated total     |
| effective dose equivalent (TEDE) of 14.5 rem (145 mSv).  The individual had  |
| been involved in decontamination activities on the 1974' elevation of the    |
| auxiliary building, in the valve gallery of the Boron Thermal Regeneration   |
| System room.  Upon exiting the area, significant contamination was detected  |
| on the individual's face (up to 80,000 dpm on the right side of the face).   |
| The individual was decontaminated and a whole body count was performed.  The |
| whole body count indicated the presence of cobalt-58 contamination in the    |
| individual's gastrointestinal tract.  Whole body counts were given to other  |
| individuals who had been working in the same area, but no additional         |
| internal contamination was discovered.                                       |
|                                                                              |
| The licensee has issued a stop work order for all work areas with            |
| contamination levels in excess of 50,000 dpm, except those with specific     |
| approval from the Radiation Protection Manager.  The licensee is also        |
| forming an Incident Investigation Team to determine the root cause of this   |
| event.  The NRC resident inspector has been informed of this event by the    |
| licensee.                                                                    |
|                                                                              |
|                                                                              |
| * * * UPDATE AT 0920 ON 6/26/99, BY HUBBARD TAKEN BY WEAVER * * *            |
| The licensee has notified the State of this event and also issued a press    |
| release.   HOO notified  R4DO (Tapia).                                       |
|                                                                              |
| * * * COMMISSIONERS ASSISTANTS BRIEFING 2000 6/26/99 * * *                   |
|                                                                              |
| A Commissioners Assistants briefing was held regarding this event.           |
| Participants: NRR (Donahue, Richards, Zwolinski), Region IV (Brockman,       |
| Brush, Hackney, Good, Ricketson, Henderson, Graves-briefer), NMSS (Cool),    |
| OCA (Madden), OPA (Gilliland), OSP (Sollenberger), EDO (Knapp, Lange), IRO   |
| (Giitter), Chm Jackson (Johnson), Comm Merrifield (McCabe), Comm Dicus       |
| (Lubenau), Comm McGaffigan (Crockett), Comm Diaz (Castleman).                |
|                                                                              |
| * * * RETRACTED AT 1751 EDT ON 6/27/99 BY  RICK HUBBARD TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| Further reviews of this event identified a  significant error in the         |
| original dose calculations which were the basis of the report.  The error    |
| was in the use of a software generated activity rather than actual activity, |
| a matter of using the wrong column's information in the calculations.  Using |
| the correct value, the internal exposure is estimated to be 2 mRem. The      |
| external exposure received by the individual on that work activity was 5     |
| mRem. The assigned total effective dose equivalent (TEDE) is a  combination  |
| of the internal and external exposures.  Therefore,  when corrected, the     |
| TEDE is estimated to be approximately 7 mRem versus the 14.5 Rem reported on |
| June 25, 1999.                                                               |
|                                                                              |
| The exposure of the individual involved in the June 25 decontamination       |
| evolution was well below regulatory limits and, therefore, does not meet the |
| reporting requirements.  Therefore, Event Notification # 35863 is being      |
| retracted.                                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector for the Wolf Creek          |
| Generating Station and will also notify the State of Kansas and the media.   |
| The Headquarters Operations Officer notified the R4DO (Joseph Tapia).        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35864       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 18:57[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        17:45[CDT]|
| NRC NOTIFIED BY:  ARTHUR WEMETT                |LAST UPDATE DATE:  06/25/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF LICENSEE  TO SUBMIT CHANGES TO LICENSING BASIS FOR NRC REVIEW     |
|                                                                              |
| On 6/25/99, the NRC notified the licensee that the use of equipment failure  |
| probabilities (TORMIS) in the assessment of tornado and missile effects on   |
| the emergency feedwater (EFW) system constitutes a change to the licensing   |
| and design bases of the system.  Such changes to the licensing and design    |
| bases constitute an Unreviewed Safety Question (USQ) and require formal NRC  |
| review and approval in accordance with 10 CFR 50.90.  The licensee has       |
| decided not to contest the conclusion by the NRC.                            |
|                                                                              |
| An engineering evaluation had previously been performed to postulate the     |
| effects of tornado winds and missiles on the EFW pump turbine steam supply   |
| piping and steam exhaust stack.  The evaluation concluded that the results   |
| were acceptable, based on criteria provided in NRC Regulatory Guide 1.117.   |
| Based upon this evaluation, the licensee has concluded that the EFW system   |
| is operable with respect to its design basis functions, including the        |
| effects of tornado winds and missiles.                                       |
|                                                                              |
| The licensee plans to submit a formal license amendment request in           |
| accordance with 10 CFR 50.90 to incorporate the use of TORMIS.  The NRC      |
| resident inspector has been informed of this notification by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35865       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 22:30[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        19:28[EDT]|
| NRC NOTIFIED BY:  R. PIZARRO                   |LAST UPDATE DATE:  06/25/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE                                              |
|                                                                              |
| The licensee declared the high pressure coolant injection (HPCI) system      |
| inoperable after the manual/automatic flow controller (E41-R614) was found   |
| to be indicating full downscale.  The cause of the problem is currently      |
| under investigation.  The licensee entered Technical Specification 3.5.1.c,  |
| and verified that all other emergency core cooling systems are operable.     |
| Although the HPCI flow controller would be unable to automatically control   |
| system flow, the licensee believes that operators would be able to control   |
| system flow manually, if needed.                                             |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35866       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 06/25/1999|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 23:08[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/25/1999|
+------------------------------------------------+EVENT TIME:        20:30[EDT]|
| NRC NOTIFIED BY:  DAN ETHERIDGE                |LAST UPDATE DATE:  06/25/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|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        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATOR DECLARED INOPERABLE                               |
|                                                                              |
| "The Diesel Generator Fuel Oil System is designed to provide the required    |
| amount of diesel fuel to operate the EDGs on each unit for a minimum of      |
| seven days at the full load capacity of the generators. Two fuel oil         |
| transfer pumps are provided for each EDG to transfer diesel fuel from the    |
| storage tank to the fuel oil day tank. From each day tank, the fuel oil      |
| flows by gravity into the suction of the engine-driven fuel pump. The pump   |
| provides nine gpm at 35 psig and discharges through a duplex fuel oil filter |
| into the two fuel oil supply manifolds.                                      |
|                                                                              |
| "Some of the fuel oil which flows from the supply manifold into the          |
| injection pump is not delivered to the spray nozzle. This excess fuel oil    |
| circulates through the injection pump, cooling the injection pump, and       |
| providing lubrication for the fuel oil side of the pump. The fuel oil then   |
| flows to the return manifold. To maintain a fixed pressure in the supply     |
| manifold, a relief valve at the end of each supply manifold (SV-200 set at   |
| 25 psig) bypasses fuel oil to the return manifold.                           |
|                                                                              |
| "On 6/25/99, during routine inspection of the fuel oil lines, it was         |
| discovered that SV-200 on one of the Unit 1 EDGs was installed backwards,    |
| effectively blocking the safety valve from relieving excess pressure on the  |
| supply manifold. This configuration may have existed since initial           |
| construction. The EDG has been operated successfully many times with this    |
| condition, but uncertainty about the ability to operate for 7 days,          |
| especially at low loads, has caused the EDG to be declared inoperable and    |
| prompted this 4 hour NRC notification. The EDG remains available and will be |
| repaired at the earliest opportunity."                                       |
|                                                                              |
| The licensee will inform the NRC resident inspector of this notification.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35867       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 06/26/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 05:28[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/26/1999|
+------------------------------------------------+EVENT TIME:        04:03[EDT]|
| NRC NOTIFIED BY:  DOUGLAS AMTSFIELD            |LAST UPDATE DATE:  06/26/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI INOPERABLE                                                              |
|                                                                              |
| On 6-26-99, at 0403 the unit 2 HPCI System was declared inoperable following |
| performance of a routine test on the HPCI drain pot orifice. The purpose of  |
| the test is to verify flow through the HPCI turbine exhaust drain pot        |
| discharge line flow orifice. At the time of the failure HPCI was operable.   |
| The HPCI system was conservatively declared inoperable due to the potential  |
| for the exhaust line to fill.  The licensee notified the NRC resident        |
| inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35868       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/26/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 10:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/26/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/26/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTIFICATION OF ANOTHER FEDERAL AGENCY                                       |
|                                                                              |
| The licensee notified the DOE of an event in the X-705 building annex        |
| cylinder cleaning area.  While attempting to clean an empty 8" cylinder it   |
| was discovered that the cylinder would not fit into the cadmium shield.  It  |
| was later discovered that the NCSA had been based on a cylinder design which |
| was slightly smaller than the older cylinder which caused the problem.    A  |
| new NCSA will be performed.                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35869       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 06/26/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 13:18[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        06/26/1999|
+------------------------------------------------+EVENT TIME:        10:08[EDT]|
| NRC NOTIFIED BY:  BLAIR                        |LAST UPDATE DATE:  06/26/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KURT COWGILL         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                                   
+------------------------------------------------------------------------------+
| EDG STARTED AND LOADED DUE TO LOSS OF AUXILIARY TRANSFORMER                  |
|                                                                              |
| At 1008, the '1B' 230 kV auxiliary transformer failed for unknown reasons.   |
| The '1A' emergency diesel generator (EDG) automatically started and loaded   |
| to its associated 4kV emergency bus.  The unit is currently stable at 100%   |
| power.  The licensee stated that EDG will remain loaded to its emergency bus |
| until the auxiliary transformer can be restored to service.  The NRC         |
| resident inspector has been informed of this event by the licensee.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35870       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/26/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:49[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/25/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        20:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/26/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 REPORT                                                    |
|                                                                              |
| "ON 6/25/99 PLANT PERSONNEL PERFORMING A WALKDOWN OF X-744L (STOREROOM) TO   |
| ENSURE COMPLIANCE WITH NCSA-PLANT046 'CONTAMINATED METAL' DISCOVERED PALLETS |
| OF VACUUM PUMPS (3-4 pumps) STACKED FOUR TO A PALLET ON STORAGE RACKS WITHIN |
| A CONTAMINATION STORAGE AREA. THE PUMPS ARE CONTAMINATED BUT THERE IS NO     |
| DOCUMENTATION IMMEDIATELY AVAILABLE IDENTIFYING THE URANIUM CONCENTRATION IN |
| THESE PUMPS. THIS BUILDING HAS PREVIOUSLY BEEN SCANNED BY THE APPLIED        |
| NUCLEAR TECHNOLOGY GROUP FOR NDT ANALYSIS OF THE MATERIAL. WITHOUT THIS      |
| DOCUMENTATION READILY AVAILABLE THE NCSA REQUIRES THE MATERIAL TO BE SPACED  |
| AT A MINIMUM TWO FOOT EDGE-TO-EDGE SPACING. THIS IS A VIOLATION OF ONE       |
| CONTROL (SPACING) OF THE DOUBLE CONTINGENCY MATRIX. THE OTHER CONTROL VOLUME |
| WAS MAINTAINED."                                                             |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35871       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/26/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 19:04[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/26/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        05:33[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/26/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DALE NOEL                    |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MOTOR STOP BUTTON FAILED TO FUNCTION AS DESIGNED                             |
|                                                                              |
| "ON 6/26/99 AT 0533 HOURS, THE X-333 PROCESS BUILDING AREA CONTROL ROOM      |
| (ACR) #1 MOTOR STOP BUTTON FAILED TO FUNCTION AS DESIGNED WHEN CALLED UPON   |
| TO SHUTDOWN MOTORS ON CELL 33-5-10 (CASCADE OPERATIONAL MODE Ill). THIS      |
| REPRESENTS THE FAILURE OF TECHNICAL SAFETY REQUIREMENT (TSR) SURVEILLANCE    |
| 2.2.3.14.3 FOR CASCADE D.C. CONTROL POWER WHICH STATES: 'UTILIZE THE ACR     |
| MOTOR STOP BUTTON FOR EACH SCHEDULED CELL TRIP. MONITOR EXPECTED CELL BLOCK  |
| VALVE CLOSURE AND ANY RECYCLE VALVE ACTUATION.' OPERATIONS PERSONNEL         |
| IMMEDIATELY UTILIZED AN ALTERNATE MEANS LOCATED AT THE CELLS LOCAL CONTROL   |
| CENTER (LCC) TO TRIP CELL 33-5-10 MOTORS.                                    |
|                                                                              |
| "THIS EVENT IS REPORTABLE DUE TO A SAFETY SYSTEM COMPONENT (SSC) REQUIRED BY |
| THE TSR NOT BEING AVAILABLE OR OPERABLE AND NO REDUNDANT EQUIPMENT WAS       |
| AVAILABLE TO PERFORM THE REQUIRED SAFETY FUNCTION.                           |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35872       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/27/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 14:00[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/27/1999|
+------------------------------------------------+EVENT TIME:        11:00[CDT]|
| NRC NOTIFIED BY:  ROBERT BRINKLEY              |LAST UPDATE DATE:  06/27/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR PROTECTION SYSTEM ACTUATION RESULTING IN REACTOR TRIP                |
|                                                                              |
| The unit had a reactor trip from OTDeltaT, all control rods fully inserted.  |
| Auxiliary Feedwater, an Engineered Safety Features (ESF) system,             |
| automatically started on low steam generator level and feedwater isolation,  |
| as expected.  The pressurizer power operated relief valves lifted on the     |
| reactor trip and then reseated.  Also, some steam generator safeties lifted  |
| momentarily and reseated, the steam dumps to the condenser are operating to  |
| remove excess energy.  The plant is stable in Hot Standby.                   |
|                                                                              |
| All systems functioned as required, the only unexpected action was the trip  |
| of both main feedwater pumps on overspeed during the transient.  The cause   |
| of the reactor trip is being investigation, a turbine trip is suspected.     |
| The trip of the feed pumps is also under review.                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35873       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 06/27/1999|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 18:21[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        06/27/1999|
+------------------------------------------------+EVENT TIME:        16:55[CDT]|
| NRC NOTIFIED BY:  VAUDY HOLLEY                 |LAST UPDATE DATE:  06/27/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE COMMUNICATION SYSTEM - TONE ALERT RADIO                      |
|                                                                              |
| After thunderstorms moved through the area of the plant, the licensee        |
| discovered that communications with the meteorological tower had been lost   |
| and the tone alert radio system was unavailable for greater than 15 minutes, |
| part of the public communication (warning) system.                           |
|                                                                              |
| Workers have been called in to investigate and repair the systems that have  |
| been lost.                                                                   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35874       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/28/1999|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 03:55[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/28/1999|
+------------------------------------------------+EVENT TIME:        03:00[EDT]|
| NRC NOTIFIED BY:  FRANK GORLEY                 |LAST UPDATE DATE:  06/28/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS 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 Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL                           |
|                                                                              |
| The reactor automatically scrammed on low reactor vessel water level because |
| of maintenance activities on the 'B' level keep fill system.  Operators      |
| venting the keep fill system unintentionally vented the 'B' reference leg    |
| because the isolation valve between the two system is apparently leaking.    |
| This venting caused level instruments using the 'B' reference leg to         |
| indicate high.  The mismatch on level indicators caused the feed system to   |
| switch to the 'B' leg (which happened to be the failed system).  This        |
| resulted in a decrease in feed flow and an actual decrease in reactor vessel |
| water level.                                                                 |
|                                                                              |
| The decrease in reactor water level caused a reactor scram and High Pressure |
| Coolant Injection (HPCI) initiation.  Reactor Core Isolation Cooling (RCIC)  |
| did not initiate because it uses the 'B' reference leg as an input.          |
| All control rods fully inserted.  The plant is stable in mode 3.  Water      |
| level has been restored to the normal band and is being maintained by the    |
| feed system.   The recirculating pumps are operating and no safety relief    |
| valves lifted.  The lowest indicated level was -45".                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+