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. |
+------------------------------------------------------------------------------+
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