Event Notification Report for June 16, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/15/1999 - 06/16/1999
** EVENT NUMBERS **
35752 35823 35824 35825 35826 35827 35828
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35752 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/21/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 15:02[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 10:14[EDT]|
| NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 06/15/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 15 Power Operation |15 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 hour License Condition 2.C.(9) report concerning non-compliance with the |
| approved fire protection program. |
| |
| During a design calculation review, plant engineering department personnel |
| discovered that cable routing for safety/relief valve (SRV) 'G' is not in |
| compliance with Appendix R design assumptions for cable separation. The SRV |
| is used in the dedicated shutdown procedure to control reactor pressure and |
| to depressurize the plant so that a cold shutdown condition can be achieved |
| within 10 hours after plant shutdown (UFSAR commitment). An hourly fire |
| watch has been established in the affected zone, pending an evaluation by |
| engineering department personnel. |
| |
| The NRC Resident Inspector has been notified of this event notification by |
| the licensee. |
| |
| * * * RETRACTED AT 1454 EDT ON 6/15/99 BY PATRICK FALLON TO WILLIAM POERTNER |
| * * * |
| |
| "Further review determined that the previously reported cable routing of |
| associated circuits for SRV 'G' being different than the Appendix R design |
| assumptions, would not have affected the ability of SRV 'G' to function as |
| assumed in the Dedicated Shutdown Procedure. Although the associated |
| circuits were routed through fire zones where use of the Dedicated Shutdown |
| Procedure was required, the fuses for the associated circuits were |
| appropriately coordinated such that fire induced multiple high impedance |
| faults would not have prevented operation of SRV 'G' as assumed in the |
| procedure. Therefore, the existing configuration is in compliance with the |
| approved Fermi 2 fire protection program as required by License Condition |
| 2.C.(9). Accordingly, the previous notification made in accordance with |
| License Condition 2.F is withdrawn." |
| |
| The licensee notified the NRC resident inspector. HOO notified R3DO (JOHN |
| MADERA). |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35823 |
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+------------------------------------------------------------------------------+
| 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
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| 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: 35824 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/15/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 07:45[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 06/15/1999|
+------------------------------------------------+EVENT TIME: 03:56[EDT]|
| NRC NOTIFIED BY: ANTHONY ROGENSKI |LAST UPDATE DATE: 06/15/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID RADIATION ALARM IN AUXILIARY BUILDING CAUSED BY MAINTENANCE ACTIVITY. |
| |
| |
| "WHILE DRAINING CHEMICAL AND VOLUME CONTROL SYSTEM (CVCS) HOLDUP TANK (HUT) |
| 'A' WHICH WAS ISOLATED, THE LICENSEE NOTICED THE AUXILIARY BUILDING |
| PARTICULATE AND GAS MONITORS INCREASING. OPERATORS CLOSED THE DRAIN VALVE |
| AND THE RADIATION MONITORS CONTINUED TO INCREASE. THE GAS MONITOR TRIPPED |
| AND GAVE AN AUXILIARY BUILDING VENTILATION ISOLATION." |
| |
| THE CVCS HUT IS NORMALLY MAINTAINED CLOSED WITH A NITROGEN OVERPRESSURE. |
| RADIATION MONITORS R13 AND R14 INSTALLED ON THE AUXILIARY BUILDING |
| VENTILATION EXHAUST BOTH SHOWED INCREASING COUNTS. THE R14 MONITOR |
| INCREASED TO 2755 CORRECTED COUNTS PER MIN (CCPM) EXCEEDING THE ALARM |
| SETPOINT OF 2250 RESULTING IN THE AUXILIARY BUILDING VENTILATION ISOLATION. |
| THE R13 INCREASED TO 1283 CCPM WELL BELOW THE ALARM SETPOINT OF 3000. THE |
| LICENSEE SUBSEQUENTLY RESTORED VENTILATION AND RESET THE ISOLATION SIGNAL. |
| THERE WAS NO RADIATION RELEASE OFFSITE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35825 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/15/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 20:13[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/15/1999|
+------------------------------------------------+EVENT TIME: 17:00[EDT]|
| NRC NOTIFIED BY: ROBERT MAGLAJANG |LAST UPDATE DATE: 06/15/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA 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 N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH FLUX AT SHUTDOWN ALARM NOT TESTED DURING CHANNEL FUNCTIONAL TEST. |
| |
| The following is a portion of a facsimile received from the licensee: |
| |
| "The function of the Source Range Channels is to provide detection and |
| indication of source range neutron flux during shutdown, refueling and |
| startup modes. The source range channels N31/N32 provide a 'High Flux at |
| Shutdown' alarm in the control room and containment in case of unexpected |
| reactivity excursions during shutdown and refueling operations. This alarm |
| is credited in the Cook licensing basis for detection and mitigation of a |
| boron dilution event as analyzed in UFSAR. This function is required to be |
| available during modes 3, 4, 5 and 6. |
| |
| "Technical Specifications defines a Channel Functional Test as an injection |
| of a simulated signal into the channel as close to the primary sensor as |
| practicable to verify OPERABILITY including alarm and/or trip functions. |
| Contrary to this the 'High Flux at Shutdown' alarm is not tested or verified |
| during the Source Range Channel Functional Test. The function of the Source |
| Range Channels cannot be credited as operable under the Technical |
| Specifications unless it has been tested in conjunction with these Tech Spec |
| requirements. |
| |
| "Technical Specification compensatory actions have begun which include |
| verifying the Shutdown Margin requirements are met within one hour and at |
| least once per 12 hours thereafter. |
| |
| "It should be noted that there is a great degree of confidence in the |
| physical functionality of this alarm based on drawing review and the fact |
| that the alarm came in on a channel spike on 2/4/99. The inoperability is |
| based entirely on missed surveillance requirements." |
| |
| The licensee is revising procedures to test the high flux at shutdown |
| alarm. |
| |
| The licensee plans to contact the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
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