Event Notification Report for August 2, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/01/2001 - 08/02/2001
** EVENT NUMBERS **
38149 38179
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Fuel Cycle Facility |Event Number: 38149 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/18/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/17/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/01/2001|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
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| NRC NOTIFIED BY: SALYERS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
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|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2) SAFETY EQUIPMENT FAILUR| |
| | |
| | |
| | |
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EVENT TEXT
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| HIGH PRESSURE FIRE WATER SPRINKLER SYSTEM DECLARED INOPERABLE |
| |
| On 7/17/01 at approximately 1530 hrs, the Plant Shift Superintendent (PSS) |
| was notified that during a Fire Protection Engineering assessment/inspection |
| that High Pressure Fire Water (HPFW) sprinkler system #165 in the X-333 |
| Building contained five adjacent sprinkler heads with visible corrosion |
| deposits. Previous engineering reviews have concluded that the system under |
| this condition would not be capable of meeting the Technical Safety |
| Requirements (TSR) to maintain operability. |
| |
| The PSS declared the affected sprinkler system inoperable and TSR required |
| actions were implemented. |
| |
| The NRC Resident Inspector was notified along with the DOE Representative. |
| |
| * * * RETRACTION ON 08/01/01 AT 1600 ET BY KURT SISLER TAKEN BY MACKINNON * |
| * * |
| |
| This event is being retracted based upon engineering evaluation |
| (EVAL-SE-2001-0321) approved on July 31, 2001. Functional testing of these |
| sprinkler heads was conducted. The results showed that all these sprinkler |
| heads would have operated when needed and performed their intended safety |
| function. R3DO (John Madera) & NMSS EO (Brian Smith) notified. |
| |
| The NRC resident inspector was notified of this retraction by the |
| certificate holder. |
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|Power Reactor |Event Number: 38179 |
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/01/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 09:05[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/01/2001|
+------------------------------------------------+EVENT TIME: 07:01[CDT]|
| NRC NOTIFIED BY: BRUCE ANDERSON |LAST UPDATE DATE: 08/02/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO NEGATIVE FLUX RATE |
| |
| The unit automatically tripped from 100%; the first out annunciator was Flux |
| Rate Reactor Trip. Immediately following the trip, the rod position |
| indicator showed that five control rods did not insert completely. The stuck |
| control rods indicated 15-20 steps out from bottom. Operators entered their |
| reactor trip/safety injection emergency procedure (1E0), but were able to |
| transition to the trip recovery procedure (1ES0.1). One of the stuck control |
| rods subsequently indicated full insertion. The unit is currently stable in |
| Mode 3. Operators are emergency borating the reactor per 1ES0.1 a total of |
| 1000 gallons (250 gallons per stuck rod). The licensee is continuing their |
| trip recovery. Preliminary investigation indicates a problem with the rod |
| control system may have led to one or more dropped control rods. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE 1025 EDT 8/1/01 FROM DAMMANN TAKEN BY JONES * * * |
| |
| The licensee reported that the auxiliary feedwater (AFW) system (pumps 11 |
| and 12) automatically actuated on steam generator low-low level following |
| the trip, as expected. In addition, two of the stuck rods are now |
| indicating full insertion. The NRC resident inspector has been informed of |
| this update. |
| |
| * * * UPDATE 1624 EDT 08/01/01 FROM GOSMAN TAKEN BY MACKINNON * * * |
| |
| After interviewing the Reactor Operators it was determined that 6 rod bottom |
| lights did not immediately come on after the reactor trip. Also a media |
| press release will be made concerning this event. R3DO (John Madera) |
| notified. |
| |
| The NRC resident inspector was notified of this update by the licensee. |
| |
| * * * UPDATE 0431 EDT 8/2/01 FROM IRVIN TAKEN BY STRANSKY * * * |
| |
| "Investigation into the cause of the reactor trip has determined that |
| control rods associated with Rod Control Power Cabinet 2AC began to insert |
| into the core. As designed, the reactor protection system actuated to insert |
| the remaining control rods. |
| |
| "In accordance with procedures, operators verified the reactor had safely |
| shutdown. However, indicator lights for six of twenty-nine individual |
| control rods did not indicate that the rods had fully inserted. This |
| situation is addressed in the reactor trip procedure and the operators |
| responded appropriately by borating to compensate. |
| |
| "Control rod drop testing has been performed and has verified that all |
| control rods fully inserted. Individual rod position indication calibration |
| check is in progress." |
| |
| The NRC resident inspector will be informed of this update by the licensee. |
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