Event Notification Report for August 17, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/16/2000 - 08/17/2000
** EVENT NUMBERS **
37173 37214 37223 37229 37230 37231 37232
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|Fuel Cycle Facility |Event Number: 37173 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/17/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:18[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/17/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:35[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/16/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MICHAEL PARKER R3 |
| DOCKET: 0707002 |M. WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NRC BULLETIN 91-01, 24 HOUR REPORT - |
| |
| At 1335 on 07/17/00, it was discovered that an NCSA mass control was lost in |
| a compressor seal can storage area in the X-330 building. Two seal cans were |
| identified to contain more items than specifically permitted by |
| NCSA-0330_003.A02 requirement #4 which states: "Only one seal set shall be |
| in each seal can." One seal can was discovered to contain two seal sets and |
| a second seal can was discovered to contain one seal with several (3 or 4) |
| additional seal parts. This deficiency was discovered during recovery |
| activities for NCS event report PTS-00-065 (NRC Event Number #37172) |
| involving a spacing violation of NCSA-0330_003.A02, requirement #8. |
| |
| This event resulted in the loss of one control (mass) of the double |
| criticality control principle. NCS interaction and enrichment control was |
| maintained throughout this event. |
| |
| NCSA-0330_003.A02 requirement #4 compliance was restored at 1415 when the |
| extra seal and seal parts were stored individually in seal cans under NCS |
| Engineering guidance. Complete compliance with NCSA-0330_003.A02 (refer to |
| NCS event #PTS-00-065) was established at 1705. |
| |
| SAFETY SIGNIFICANCE OF EVENT: |
| |
| The safety significance of this event is low. NCSE-0330_003.101 analyzes |
| greater than safe mass in a group of seal cans. In this analysis it states |
| that with an enrichment limit of 15% U-235, the amount of uranium in a seal |
| can would have to be exceeded by 4.6 times the normal amount to reach the |
| minimum critical mass. In this event two seal cans were found to be double |
| loaded. Assuming that both overloaded seal cans were next to each other, |
| the mass in the cans is less than the minimum critical mass. Note: these |
| cans were found because the group they were in was being moved to correct a |
| spacing violation between two other seal can groups. The overloaded seal |
| cans were not directly involved in the spacing violation. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR]: |
| |
| For a criticality to occur, the seal cans would have to have more than a |
| double batch and the enrichment exceed 15% U-235. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, (GEOMETRY, CONCENTRATION, ETC): |
| |
| The controlled parameters in this case are mass, enrichment and |
| interaction. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| The total amount of uranium in the 47 seal cans involved (including the two |
| overloaded cans) is estimated to be 1715 grams uranium or 257.3 grams of |
| U-235. The maximum enrichment for this NCSA is limited to 15% U-235 and the |
| form of the material is dry UO2F2. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| |
| The NCS mass control was lost in this case. Only one seal is allowed to be |
| placed In a seal can. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| At 1415, NCSA-0330_ 003.A02 compliance was restored. The extra seal parts |
| were removed and stored individually in separate seal storage cans. |
| |
| The NRC Resident Inspector and the DOE Site Representative were notified of |
| this event. |
| |
| PTS-2000-03534 PR-PTS-00-066 |
| |
| * * * UPDATE AT 1252 ON 8/2/00, BY SISLER RECEIVED BY WEAVER * * * |
| |
| On 8/2/00 at 0035 hours maintenance personnel performing walkdown |
| verifications for NRC Event PTS-00-066 discovered a seal can containing |
| several pieces of seals that were more than volume of one seal. Compliance |
| was re-established at 0250hrs under NCS Engineering guidance. The various |
| seal parts were separated into three seal cans and properly stored per the |
| NCSA. At the time of this Update, a 100% Walkdown of all Seal Cans in |
| storage is in progress. |
| |
| The licensee notified the NRC resident inspector. The operations center |
| notified the RDO(Creed); EO (Hickey) |
| |
| * * * UPDATE ON 8/16/00 @ 0756 BY VANDERPOOL TO GOULD * * * |
| |
| On 8/15/00 @ 2150 hours maintenance personnel performing walkdown |
| verification for NRC Event PTS.00-066 discovered a seal can containing |
| several pieces of seals that involved more volume than that of one seal. |
| Compliance was re-established at 0032 hours on 08/16/00 under NCS |
| Engineering guidance. The various seal parts were separated into the |
| appropriate seal cans and properly stored per the NCSA. At the time of this |
| update, a 100% walkdown of all seal cans In storage Is in progress. |
| |
| The NRC Resident Inspector was notified along with the DOE Representative. |
| |
| The Reg 3 RDO(Jacobson) and NMSS EO(Piccone) were notified. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37214 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/08/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 21:35[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/08/2000|
+------------------------------------------------+EVENT TIME: 18:44[EDT]|
| NRC NOTIFIED BY: FREDERICK SMITH |LAST UPDATE DATE: 08/16/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 99 Power Operation |99 Power Operation |
| | |
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EVENT TEXT
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| AUTOSTART OF ANNULUS EXHAUST GAS TREATMENT SYSTEM FAN DURING TESTING |
| |
| "During performance of surveillance testing, the lifting of an incorrect |
| lead caused a low flow condition on the in service AEGTS fan. This caused |
| the auto start of the standby AEGTS fan. No low flow alarm was received on |
| the in service fan, but the system functioned properly." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * RETRACTION ON 08/16/00 AT 1435 ET BY KEN RUSSELL TAKEN BY MACKINNON * |
| * * |
| |
| The low flow signal which started the Annulus Exhaust Gas Treatment System |
| fan is not an ESF signal. Therefore, this event is being retracted since |
| the autostart did not occur based on a valid ESF signal. R3DO (John |
| Jacobson) notified. |
| |
| The NRC Resident Inspector was notified of the retraction by the licensee. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37223 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 08/14/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 07:42[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/14/2000|
+------------------------------------------------+EVENT TIME: 06:58[EDT]|
| NRC NOTIFIED BY: WESLEY HILL |LAST UPDATE DATE: 08/16/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| BOTH TRAINS OF HIGH PRESSURE INJECTION DECLARED INOPERABLE |
| |
| The licensee, in the process of a routine train swap between the 1B nuclear |
| volume control (NV) pump and the 1A NV pump, the 1B discharge check valve |
| did not fully seat. Flow from the 1A NV pump was being returned through the |
| 1B NV pump to the suction header. This could have affected the capability |
| of both of the NV pumps to perform their required actions in the event that |
| high head injection to the reactor coolant system was needed. Both pumps |
| were declared inoperable at 0658 EDT which made the high head injection |
| system inoperable. The discharge valve on the 1B NV pump was shut at 0710 |
| EDT to restore the 1A NV pump to operable. |
| |
| The method to be used to restore the 1B NV pump to operable is being |
| considered. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * RETRACTION ON 08/16/00 AT 1711 ET BY T. HEAFNER TAKEN BY MACKINNON * |
| * * |
| |
| "Subsequent to the report, further evaluation determined that the calculated |
| back flow through the 1B NV pump would not have prevented proper starting |
| and operation of that pump. Consequently, that pump was capable of |
| performing it's safety function. With one NV pump operable, there is |
| sufficient injection flow capacity to the reactor coolant system during the |
| event. In addition, for the short time that the 1A NV pump was inoperable, |
| it was not required to assume a single failure of the 1B NV pump during an |
| event. Consequently, McGuire Nuclear Station was not outside it's design |
| basis and Event Report 37223 is retracted." NRC R2DO (Paul Fredrickson) |
| notified. |
| |
| The NRC Resident Inspector was notified of this event retraction by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37229 |
+------------------------------------------------------------------------------+
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 08/16/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 02:15[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/16/2000|
+------------------------------------------------+EVENT TIME: 00:30[EDT]|
| NRC NOTIFIED BY: PAUL UNDERWOOD |LAST UPDATE DATE: 08/16/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 DECLARED HIGH PRESSURE COOLANT INJECTION (HPCI) INOPERABLE DUE TO A |
| FAILURE DURING SURVEILLANCE TESTING |
| |
| "While performing weekly exercise per Operating Order 00-01-0200S, High |
| Pressure Coolant Injection turbine stop valve failed to close when trip |
| solenoid pushbutton was depressed. |
| |
| "High Pressure Coolant Injection was declared inoperable. |
| |
| "Cause of turbine stop valve failure to close is under investigation." |
| |
| With HPCI inoperable, Unit 1 entered a 14 day LCO Action Statement. Both |
| Maintenance and Engineering are evaluating corrective actions. The licensee |
| will inform the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37230 |
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| REP ORG: NORTH CAROLINA DIV OF RAD PROTECTIO |NOTIFICATION DATE: 08/16/2000|
|LICENSEE: QUALITY NDE/JANX |NOTIFICATION TIME: 11:26[EDT]|
| CITY: ROARING RIVER REGION: 2 |EVENT DATE: 08/16/2000|
| COUNTY: STATE: NC |EVENT TIME: 10:00[EDT]|
|LICENSE#: 0851117-1 AGREEMENT: Y |LAST UPDATE DATE: 08/16/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PAUL FREDRICKSON R2 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ALBRIGHT | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
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+------------------------------------------------------------------------------+
EVENT TEXT
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| The North Carolina Division of Radiation Protection reported a radiography |
| camera with a disconnected source.. |
| |
| The state discovered, while reviewing records, they had mis-filed an |
| incident report from a licensee reporting a source had disconnected on a |
| Source Production and Equipment Co. (SPEC) model #150 serial #316 |
| radiography camera. This occurred when Quality NDE(currently Janx) was |
| performing work in Roaring River, N.C. and while they were retrieving the |
| source to its shielded position, the drive cable broke at the gearbox. The |
| licensee followed emergency procedures and brought two more radiographers |
| to the site and retrieved the source to the shielded position manually. |
| Readings of 2mr/hr @ 6" were measured when the source was retracted to the |
| shielded position. The source(#EH1804) at the time of the |
| incident(01/18/99) measured 25 curies @ Iridium-192 and it was disposed |
| 3/99. The individuals involved in the recovery of the source received an |
| actual dose of <8 millirem. The licensee had filed this incident report on |
| 02/09/99 with the State, which was within the required time. |
| |
| N.C. incident report #00-33 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37231 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 08/16/2000|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 16:22[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/16/2000|
+------------------------------------------------+EVENT TIME: 09:10[CDT]|
| NRC NOTIFIED BY: CHARLES BOTTEMILLER |LAST UPDATE DATE: 08/16/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHUCK PAULK R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| A contract supervisor tested positive for alcohol during random testing. |
| His access was immediately suspended. Review of his work determined that |
| their was no impact on plant safety. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37232 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 08/16/2000|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 17:59[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/16/2000|
+------------------------------------------------+EVENT TIME: 16:25[CDT]|
| NRC NOTIFIED BY: G RHODES |LAST UPDATE DATE: 08/16/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |PAUL FREDRICKSON R2 |
|10 CFR SECTION: |WILLIAM BECKNER NRR |
| |FRANK CONGEL IRO |
| |BARDEN FEMA |
| |YATES DOE |
| |LORI THOMAS USDA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| SMOKE SEEN COMING FROM "2C" SERVICE WATER PUMP MOTOR |
| |
| "2C" Service Water Pump (swing) motor was seen having smoke coming from it. |
| On site fire brigade was sent out to the Service Water building and |
| extinguished the fire at 1609 CT. The licensee declared an Alert at 1625 CT |
| due to the potential of the fire affecting ECCS equipment. No offsite |
| assistance was needed and no other equipment onsite was damaged by the fire. |
| Service Water Pumps "2A", "2B", "2D", & "2E" remain in service. All |
| Emergency Core Cooling Systems are fully operable if needed. |
| |
| Fire Alarm for Service Water pump was received in control room at 1548 CT. |
| A person was immediately dispatched to investigate the alarm. Person |
| reported back to control room at 1552 CT that smoke was coming from "2C" |
| Service Water motor. Licensee entered AOP 29 (Plant Fire) at 1552 CT. At |
| 1555 CT "2C" Service Water Pump tripped for unknown reason. Service Water |
| pump flow was degraded for approximately 15 seconds at which time another |
| Service Water pump was placed in service. Lowest service water pressure |
| reached was 70 psi (min pressure is 60 psi). At 1609 CT report received |
| that fire had been extinguished using carbon dioxide. 1616 CT AOP 29 was |
| exited. The licensee notified state and local officials of entering Alert |
| classification. |
| |
| The NRC Resident Inspector was in the control room during the event. |
| |
| NRC Operation Center was notified by Brad Grinstead of the Alabama |
| Department of Public Health and by Kerri Seber of the Florida State Warning |
| Point of the Farley Unit 2 Alert. |
| |
| * * * UPDATE ON 08/16/00 AT 1845 ET BY G RHODES TAKEN BY MACKINNON * * * |
| |
| Alert was terminated at 1736 CT due to fire being out and all systems |
| operating properly. |
| |
| NRC R2DO (Paul Fredrickson), Acting DEDR (Ellis Merschoff), IRO (Frank |
| Congel), NRR EO (Bill Beckner), NRC PAO (Bill Beecher), NRR (Roy |
| Zimmerman), EDO STAFF (Mark Satorius), NRC RCT (John Jolicoeur), FEMA |
| (Belcher), DOE (Yates), USDA (Lori Thomas), EPA Reg IV (Runge), and HHS |
| (Burger), notified. |
| |
| The NRC Resident Inspector was onsite in control room during this event. |
| |
| * * * UPDATE ON 08/16/00 AT 2031 ET BY G. RHODES TAKEN BY MACKINNON * * * |
| |
| "At 1625 [CT] FNP staff declared an Alert Emergency classification based on |
| criteria found in site procedures. The 2C Service Water Pump motor had |
| faulted resulting in a small fire in the Service Water Intake Structure. |
| The Site Fire Brigade responded and the fire was extinguished promptly. No |
| other equipment was damaged. The FNP Unit 2 Service Water system has 5 |
| pumps and requires 2 pumps per train (4 pumps total) to ensure that system |
| design functions are met. The 2C Service Water Pump is a swing pump that |
| can be aligned to either train. The remaining four Unit 2 Service Water |
| pumps are currently operable and in service. |
| |
| "The FNP staff has assessed this event. No plant personnel were injured and |
| only limited damage to plant equipment as described above occurred. There |
| was no affect on the health and safety of the general public and no release |
| of radiation. The Alert was terminated at 1736 [CT]. Both Units are |
| continuing to operate at 100% power." |
| |
| R2DO (Paul Fredrickson) & IRO (Congel) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021