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Event Notification Report for December 18, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/17/2001 - 12/18/2001

                              ** EVENT NUMBERS **

38575  38577  38578  38579  
.
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|Power Reactor                                    |Event Number:   38575       |
+------------------------------------------------------------------------------+
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 12/16/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 00:30[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/15/2001|
+------------------------------------------------+EVENT TIME:        22:28[EST]|
| NRC NOTIFIED BY:  ALAN RABENOLD                |LAST UPDATE DATE:  12/17/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     R3      |
|10 CFR SECTION:                                 |                             |
|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |
|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 Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| THE REACTOR RECIRCULATION PUMPS DOWN SHIFTED TO SLOW SPEED FOR
UNKNOWN       |
| REASONS RESULTING IN AN AUTOMATIC REACTOR SCRAM, BALANCE-OF-PLANT          
 |
| ISOLATIONS, AND EMERGENCY CORE COOLING SYSTEM ACTUATIONS.                    |
|                                                                              |
| At 2228 EST on 12/15/01, the reactor recirculation pumps down shifted to     |
| slow speed for unknown reasons.  This caused reactor pressure vessel (RPV)   |
| water level to swell, and an automatic reactor scram from 100% power         |
| occurred when Level 8 was reached.  All control rods fully inserted.         |
| Following the scram, RPV water level started to decrease because the         |
| feedwater pumps also tripped (as designed) when Level 8 was reached.  When   |
| RPV water level dropped to Level 2 (130 inches), balance-of-plant isolations |
| occurred, and all of the applicable valves properly isolated.  In addition,  |
| the high pressure core spray (HPCS) and reactor core isolation cooling       |
| (RCIC) systems automatically actuated when Level 2 was reached.  The HPCS    |
| and RCIC systems were utilized to restore RPV water level to the normal      |
| range.                                                                       |
|                                                                              |
| The unit is currently stable in Mode 3 with RPV pressure at 900 psi and RPV  |
| water level at 210 inches.  Normal feedwater is being utilized to maintain   |
| RPV water level within the proper band, and the HPCS and RCIC systems have   |
| been secured.  The main steam isolation valves remained open, and the        |
| condenser is being utilized as the heat sink.  Containment parameters are    |
| currently normal, the electrical grid is stable, and the emergency diesel    |
| generators are available.                                                    |
|                                                                              |
| The licensee stated that all systems functioned as required and that there   |
| was nothing unusual or misunderstood other than the cause of the initiating  |
| event (the recirculation pumps down shifting to slow speed).  The licensee's |
| investigation is underway.                                                   |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1844 EST ON 12/17/01 FROM DAVID GUDGER TO S. SANDIN * * *    |
|                                                                              |
| "This notification is a follow-up to the notification provided on            |
| 12/16/01."                                                                   |
|                                                                              |
| "The following is a description of the sequence of plant events that         |
| occurred as determined by the failure analysis."                             |
|                                                                              |
| "Initial conditions:  Feedwater level control was on Master Level controller |
| selected to the 'B' narrow range channel and the plant was operating at 100% |
| power.  Due to the level summer card 1C34K657 failure, the level signal from |
| the selected channel rapidly decreased to less than 178 inches, Level 3 (L3) |
| signal, which caused the reactor recirculation pumps to receive a            |
| fast-to-slow speed downshift.  Simultaneously, feedwater flow rapidly        |
| increased in response to the low level on the 'B' channel.  The feedwater    |
| pumps tripped at 219 inches, Level 8 (L8), which occurred due to swell from  |
| the recirculation pumps downshift and increased feedwater flow.  The [motor  |
| feed pump (MFP)] did not automatically start due to the L8 signal (as        |
| designed) and level decreased to 130 inches, Level 2 (L2).  The              |
| recirculation pumps tripped, and [the] HPCS and RCIC systems [automatically] |
| started and restored level.  The MFP L8 signals were reset, and level was    |
| controlled on the startup controller."                                       |
|                                                                              |
| "The Reactor Water Cleanup Inboard Containment Isolation Valve failed to     |
| close as designed upon [the] L2 isolation signal.  The valve was manually    |
| closed during containment valve isolation verification following the scram.  |
| The cause of the failure to close was determined to be relay failure.  Two   |
| relays were subsequently replaced and retested satisfactorily."              |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Phillips).                                        |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38577       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 12/17/2001|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 09:58[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        11/20/2001|
+------------------------------------------------+EVENT TIME:        03:25[EST]|
| NRC NOTIFIED BY:  JIM TURKETT                  |LAST UPDATE DATE:  12/17/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHARLES R. OGLE      R2      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INADVERTENT START OF A MOTOR-DRIVEN EMERGENCY FEEDWATER PUMP  (60-Day 
      |
| Report)                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During the performance of a surveillance test, the 'B' Motor-Driven         |
| Emergency Feedwater (EFW) pump was inadvertently started from the Main       |
| Control Board when the intended action was to place the control switch in    |
| the pull-to-lock position.  The plant was preparing to test the function of  |
| the solid state output relay K633 as it pertains to sending an open signal   |
| to the EFW flow control valves IFV03531, IFV03541, and IFV03551.  To prevent |
| actually injecting EFW into the [steam generators (S/G)], the pump for the   |
| train whose relay is being tested (in this case 'B') must be placed in       |
| pull-to-lock since the same relay which opens the IFVs also starts the       |
| pump."                                                                       |
|                                                                              |
| "When the BOP operator attempted to place the pump in P-T-L the pump         |
| started.  This was immediately recognized as an unexpected response, and the |
| pump was shut off within a second.  Due to the start of the EFW pump, S/G    |
| blowdown isolated as per design and had to be subsequently realigned.  [Data |
| from the] plant computer and alarm printers [was] reviewed by the Shift      |
| Supervisor and [Shift Engineer] to determine if any cold EFW actually        |
| entered the S/Gs.  The alarm printer showed 1 second between pump start and  |
| pump stop, which is consistent with the prompt error recognition observed by |
| the crew.  The plant computer data showed no increase in EFW flow during the |
| time period in question.  It is believed from this investigation that the    |
| pump never came up to speed to the point where sufficient pressure was       |
| developed to swing open the discharge check valves, thus no EFW injection    |
| occurred.  The cause of this event is attributed to human performance        |
| error."                                                                      |
|                                                                              |
| "This event does not require a telephone notification under                  |
| 10CFR50.72(b)(3)(iv)(A) because this is being reported as an invalid ECCS    |
| actuation of an Emergency Feedwater Pump.  However, the plant is making this |
| call under the criteria of 10CFR50.73(a)(1) in lieu of submitting an LER     |
| under 10CFR50.73(a)(2)(iv)."                                                 |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38578       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 12/17/2001|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 10:39[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/17/2001|
+------------------------------------------------+EVENT TIME:        08:00[CST]|
| NRC NOTIFIED BY:  GREG BAKER                   |LAST UPDATE DATE:  12/17/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |
|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  |
|2     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SIGNIFICANT FITNESS-FOR-DUTY EVENT UNDER BRAIDWOOD PROGRAM SEC-1.10       
  |
|                                                                              |
| A non-licensed supervisor tested positive based on a for-cause test due to   |
| the odor of alcohol.  The individual was immediately escorted out of the     |
| Protected Area, and the individual's access has been suspended.  (Call the   |
| NRC operations officer for additional details and for the Security Manager's |
| telephone number.)                                                           |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38579       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 12/17/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 16:17[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        12/17/2001|
+------------------------------------------------+EVENT TIME:        15:30[EST]|
| NRC NOTIFIED BY:  DARON ZAKARIAN               |LAST UPDATE DATE:  12/17/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |10       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT DUE TO POTENTIAL OPERATION IN EXCESS OF OPERATING
LICENSE     |
| CONDITION 2.C(1)                                                             |
|                                                                              |
| "After restart of Hope Creek from RF10, analysis of plant parameters         |
| indicated that changes occurred in the final feedwater temperature since the |
| previous operating cycle.  The temperatures as indicated by temperature      |
| loops 1AETE-N041A/B/C/D, were approximately 3 degrees lower than when        |
| operating at 100 percent power prior to the outage.  This indicates that     |
| actual power may have been below 100 percent of last cycle operation.  Other |
| parameters, such as First Stage pressure, main turbine control valve         |
| position, #6 Feedwater Heater shell pressure, feed pump discharge flow,      |
| condensate pump flow, were also lower, substantiating that power was lower   |
| than previous cycle.  Performance Engineering notified Design Engineering of |
| this condition.  Design Engineering then initiated a complete review of      |
| related documentation.                                                       |
|                                                                              |
| "During Hope Creek RF9 (May 2000), the main feedwater temperature loops      |
| required recalibration to support power up-rate.  The traditional method to  |
| determine the RTD curve introduced a +1 degree F bias.  This was             |
| non-conservative, in that power level was higher than calculated by the      |
| plant computer.  In January of 2001, crossflow was implemented to correct    |
| for fouling of the venturis.  In October 2001, a non-conservative moisture   |
| carryover fraction was used in the core thermal power calculation as         |
| reported in Hope Creek Special Report 354/2001-003-00.  As a result of these |
| conditions, Hope Creek Generating Station has potentially operated at power  |
| levels in excess of Operating License Condition 2.C(1), which requires that  |
| the facility be operated at reactor core power levels not in excess of 3339  |
| MWt.  The upper limit may have been exceeded by significantly less than      |
| 0.1%.  This potential overpower condition existed between the time of        |
| crossflow implementation and RF10.                                           |
|                                                                              |
| "This notification is being made in accordance with Hope Creek Operating     |
| License Condition 2.F, as a potential violation of Hope Creek Operating      |
| License Condition 2.C(1).                                                    |
|                                                                              |
| "The moisture carryover fraction was corrected during RF10.  During the      |
| recent forced outage, the 4 RTDs were checked and all four loops were        |
| calibrated, therefore, eliminating the potential for operating above 100%    |
| power."                                                                      |
|                                                                              |
| The period of time during which the unit may have operated in this condition |
| occurred between August 1, 2001, and October 10, 2001.  The corrective       |
| action involving calibration of the 4 RTDs was completed last week.          |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
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