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Event Notification Report for June 17, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/16/1999 - 06/17/1999

                              ** EVENT NUMBERS **

35823  35826  35827  35828  35829  35830  35831  35832  35833  35834  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35823       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/15/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 04:02[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/14/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:56[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/16/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN MADERA          R3      |
|  DOCKET:  0707002                              |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC 91-01 BULLETIN  REPORT INVOLVING NCSA VIOLATION                  |
|                                                                              |
| "On 6/14/99 at 1756, the Plant Shift Superintendent's office was notified by |
| operations personnel that a Nuclear Criticality Safety Approval (NCSA) was   |
| not being maintained in the X-333 process building.  Operations personnel    |
| discovered that a converter classified as UH (uncomplicated handling) being  |
| stored on the cell floor had a cover missing from an opening. The NCSA for   |
| this operation, PLANT062.A00, has a requirement which states in part,        |
| 'Openings/penetrations shall be covered to minimize the potential for        |
| moderator collection and moist air exposure.'                                |
|                                                                              |
| "The Nuclear Criticality Safety (NCS) staff determined that this incident    |
| caused a loss of control such that only one double contingency control       |
| remained in place."                                                          |
|                                                                              |
| Operations personnel will inform the DOE Site Representative and has         |
| informed the NRC Resident Inspector.                                         |
|                                                                              |
| * * * UPDATE AT 0402 BY SPAETH, TAKEN BY WEAVER * * *                        |
|                                                                              |
| On 6/15/99, at 1123 while continuing an NCS walkdown, an additional NCSA     |
| non-compliance was discovered.  A Recycle Cooler stored on the cell floor    |
| had a cover missing from an opening. The Recycle Cooler is classified as UH. |
| Compliance was restored within four hours.                                   |
|                                                                              |
| The licensee notified the NRC resident inspector.  The HOO notified the RDO  |
| (Madera); NMSS EO (Piccone).                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35826       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/15/1999|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 23:51[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/15/1999|
+------------------------------------------------+EVENT TIME:        21:24[EDT]|
| NRC NOTIFIED BY:  BARRY COLEMAN                |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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     M/R        Y       41       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 41% POWER.                                         |
|                                                                              |
| Operators manually scrammed the reactor from 41% power because of lowering   |
| vacuum in the main condenser.   Operators first noticed lowering vacuum at   |
| around 2000 and worked unsuccessfully to fix the problem until the reactor   |
| was eventually scrammed at 2124.  The cause of the loss of vacuum was a      |
| faulty steam jet air ejector.  The turbine was manually tripped after the    |
| scram.  Reactor water level lowered to -20 inches during the transient and   |
| caused an automatic group II isolation.                                      |
|                                                                              |
| Several complications arose during the plant response to this transient.     |
| The 4160 Volt electrical buses 2C and 2D did not switch to their alternate   |
| power supply as expected.  This caused the loss of the recirculation pump    |
| oil pumps and the resultant loss of the recirculation pumps.  These buses    |
| have been restored and recirculation pumps restarted.  Restoring one of the  |
| recirculation pumps resulted in a transient on Unit 1 as described in the    |
| update below.                                                                |
|                                                                              |
| The outboard MSIVs were manually closed because of low condenser vacuum and  |
| loss of the condensate system.  The inboard 2B MSIV did not auto close as    |
| expected when vacuum reached 10 inches.  This valve could not be shut        |
| manually (remotely) either and still indicates open.  A drywell entry is     |
| planned to ascertain the exact status of this valve.                         |
|                                                                              |
| Reactor Core Isolation Cooling (RCIC) has been manually started and is being |
| used in conjunction with Safety Relief Valves (SRVs) to maintain reactor     |
| pressure, temperature and water level.  Suppression pool cooling is          |
| operating, although pool temperature has risen to 112 F.  Tech specs        |
| require the plant to be placed in cold shutdown within 36 hours when pool    |
| temperature exceeds 110 F.  Operators are currently preparing to place High |
| Pressure Coolant Injection (HPCI) online which is expected to reduce the     |
| heat load on the suppression pool and allow its temperature to lower.        |
| Efforts are also in progress to restore the secondary plant to aid in plant  |
| cooldown if necessary.                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
|                                                                              |
| * * * UPDATE AT 0041 ON 6/16/99 BY COLEMAN TAKEN BY WEAVER * * *             |
|                                                                              |
| Just prior to this event a hard ground was coming and going on the 600 Volt  |
| bus 1D.  The licensee believes that the ground was caused by the cycling of  |
| the "B" recirculation pump discharge MOV on Unit 2.   The 600 Volt bus 1D is |
| the normal power supply to 2R24-SO18B which feeds the "B" recirculation pump |
| discharge valve 2B31-FO31B.                                                  |
|                                                                              |
| The "B" RPS MG set tripped causing a half scram, a half group II isolation   |
| (the outboard valves closed), a half group V isolation  (F004 closed & RWCU  |
| pump tripped), reactor building & refueling floor ventilation isolated       |
| (outboard dampers closed), all four Standby Gas Treatment fans auto started, |
| the main control room ventilation went into pressurization mode, and the     |
| fission product monitors isolated (outboard valves).                         |
|                                                                              |
| The licensee notified the NRC resident inspector and the Operations Officer  |
| informed the R2DO (Julian).                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35827       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 02:58[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        02:10[EDT]|
| NRC NOTIFIED BY:  PHIL SANTINI                 |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       99       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF ROD POSITION INDICATION RESULTS IN A RUNBACK                         |
|                                                                              |
| "At 0210, Motor Control Center (MCC) 24 deenergized.  This resulted in a     |
| loss of power to rod position indication.  This in turn caused a dropped rod |
| automatic runback to 95% power.  Axial power tilt remained within the band.  |
| Loss of rod position indication placed the plant in a condition which was    |
| outside the limitations of Technical Specification 3.10.6.  Rod position     |
| indication was subsequently recovered at 0225 when this load was             |
| reenergized.   All automatic functions associated with the loss of MCC 24    |
| and the runback occurred as expected."                                       |
|                                                                              |
| The licensee is investigating whether or not the runback should have reduced |
| power to 85% vs 95% as well as the initial cause for the loss of power to    |
| MCC 24.                                                                      |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35828       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/16/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 03:53[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/15/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/16/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN MADERA          R3      |
|  DOCKET:  0707002                              |JOSEPHINE PICCONE    NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT                                                |
|                                                                              |
| On 6/15/99, at 0930 the Plant Shift Superintendent's office was notified by  |
| operations personnel that a Nuclear Criticality Safety Approval (NCSA) was   |
| not being maintained In the X-705 decontamination building.  While           |
| performing operator rounds, Operations personnel discovered that a general   |
| purpose small diameter container in a transport cart, was incorrectly spaced |
| from a 1-inch line containing fissile solution.                              |
|                                                                              |
| The NCSA for this operation. NCSA-0705.004. has a requirement which states   |
| in part, "when moving uranium bearing containers, a minimum 2 feet           |
| edge-to--edge spacing shall be maintained between other uranium bearing      |
| materials and the container being moved."                                    |
|                                                                              |
| The Nuclear Criticality Safety staff determined that this incident caused a  |
| loss of control such that only one double contingency control remained in    |
| place.                                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35829       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 15:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        13:12[EDT]|
| NRC NOTIFIED BY:  WILLIAM SUSLICK              |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TURBINE DRIVEN AUXILIARY FEEDWATER (TDAFW) PUMP  START AND INJECTION.        |
|                                                                              |
| The Unit 2 TDAFW pump automatically started and injected into the steam      |
| generator secondary side.  The pump started when power was lost to an        |
| instrument panel board in the safe shutdown facility.  The panel board was   |
| aligned to an alternate power source for maintenance activities.  The panel  |
| board was not realigned to its normal power supply before power was removed  |
| from the alternate source.  The TDAFW pump was secured when the instrument   |
| panel was re-energized.                                                      |
|                                                                              |
| The Unit 1 TDAFW pump was tagged out and inoperable at the time of the       |
| event.  The Unit 1 TDAFW pump would  have automatically started if not       |
| tagged out.                                                                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35830       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 15:34[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        14:40[EDT]|
| NRC NOTIFIED BY:  SCOT TODIS                   |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSTULATED FIRE MAY PREVENT MULTIPLE STARTS OF HIGH PRESSURE COOLANT         |
| INJECTION (HPCI).                                                            |
|                                                                              |
| During a review of the Fire Safe Shutdown methodology, it was determined     |
| that potential damage from a postulated fire in Fire Area 6S (Unit 2), could |
| result in fire induced damage to the HPCI vacuum breaker motor operated      |
| valves (MOV) motive and control power source.  Closure of the vacuum breaker |
| MOV, due to fire damage, would prevent multiple starts of  HPCI as required  |
| for this Appendix R scenario.   HPCI remains operable for all other required |
| fire scenarios and plant transients.                                         |
|                                                                              |
| The licensee is establishing compensatory measures.                          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35831       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 06/16/1999|
|LICENSEE:  TECHNICAL WELDING                    |NOTIFICATION TIME: 16:20[EDT]|
|    CITY:  PASDENA                  REGION:  4  |EVENT DATE:        06/16/1999|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CDT]|
|LICENSE#:  TX L02187             AGREEMENT:  Y  |LAST UPDATE DATE:  06/16/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:                               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT RECEIVED VIA FACSIMILE                                |
|                                                                              |
| The following text is a portion of a facsimile received from the Texas       |
| Department of Health:                                                        |
|                                                                              |
| "10 CFR Part 20.2202(b)(1)(I) - Report of exposure (real or threatened) of   |
| greater than or equal to TEDE of 5 rem, eye/lens 75 rem, skin/extremities    |
| 250 reds.                                                                    |
|                                                                              |
| "Incident report 7472:  Technical Welding of Pasadena, TX notified the       |
| TDH-BRC of a 10.082 rem exposure to a radiographer during 4/99.  The         |
| radiographer has been removed from radiation work pending an                 |
| investigation."                                                              |
|                                                                              |
| There was no additional information available on the facsimile.              |
|                                                                              |
| (Call the NRC Operations Center for a contact telephone number and address.) |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35832       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 18:57[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        18:15[EDT]|
| NRC NOTIFIED BY:  CHARLIE KOCSIS               |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH HEAD SAFETY INJECTION EXTERNAL LEAKAGE.                                 |
|                                                                              |
| On June 16, 1999, operators identified packing leakage from a drain valve in |
| the high head safety injection system (Valve SI-105).  When the leakage was  |
| added to the existing system leakage, the control room ventilation system    |
| exceeded its system design basis calculation assumption for external         |
| recirculation system leakage (0.68 GPH).  The control room ventilation       |
| system continues to remain operable as per an existing operability           |
| determination (OD 98-16).  Leakage was subsequently reduced, such that total |
| system leakage was within design base limits.                                |
|                                                                              |
| The licensee plans to notified the NRC resident inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35833       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 19:01[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        15:40[PDT]|
| NRC NOTIFIED BY:  BARBARA HANSEN-HARRIS        |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT                                                     |
|                                                                              |
| Unescorted access granted inappropriately, immediate compensatory measures   |
| taken upon discovery.  The licensee notified the NRC Resident Inspector.     |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35834       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 20:57[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        20:00[EDT]|
| NRC NOTIFIED BY:  BARRY COLEMAN                |LAST UPDATE DATE:  06/16/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT                                                     |
|                                                                              |
| Access granted inappropriately, immediate compensatory measures taken upon   |
| discovery.  The licensee notified the NRC resident inspector.                |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
+------------------------------------------------------------------------------+