Event Notification Report for August 13, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/10/2001 - 08/13/2001

                              ** EVENT NUMBERS **

38196  38197  38198  38199  38200  38201  38202  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38196       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 08/10/2001|
|LICENSEE:  TERRACON ENGINEERING                 |NOTIFICATION TIME: 09:25[EDT]|
|    CITY:  Dallas                   REGION:  4  |EVENT DATE:        08/09/2001|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CDT]|
|LICENSE#:  L05268                AGREEMENT:  Y  |LAST UPDATE DATE:  08/10/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAMES H. OGDEN               |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN HUMBOLDT 5001C NUCLEAR GAUGE                                          |
|                                                                              |
|                                                                              |
| The gauge was lost during the hours of darkness July 15-16, 2001, from the   |
| back of a truck that was parked overnight at the home of the driver.  The    |
| gauge and it's transport case were removed from a parked pickup truck by     |
| cutting the chain securing the gauge to the bed of the truck.  Also stolen   |
| during this incident was the operator's toolbox and assorted hand tools.     |
| The gauge is a Humboldt Model 5001C, Serial  # 2606, containing two          |
| radioactive sources: 10 millicuries of cesium-137, Serial #6171GQ; and 40    |
| millicuries of americium-241;Be, Serial # NJ02767.  A police report was      |
| filed on July 16, 2001, with the Dallas Police Department (Report #          |
| 0551265-K).  A press release offering a $250 reward for the return of the    |
| gauge was run in the Dallas Morning News for two days.  The gauge has not    |
| been recovered as of this date.  The licensee has been cited for failure to  |
| maintain the gauge under constant surveillance.  The state of Texas has      |
| informed the Radiation Control authorities in Mexico, Arizona, New Mexico,   |
| Arkansas, and Louisiana, as well as the Humboldt Radiation Safety Officer.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38197       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 08/10/2001|
|    UNIT:  [] [2] []                 STATE:  MI |NOTIFICATION TIME: 11:21[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        08/10/2001|
+------------------------------------------------+EVENT TIME:        11:15[EDT]|
| NRC NOTIFIED BY:  LEWIS                        |LAST UPDATE DATE:  08/10/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANN MARIE STONE      R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |98       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION SHUTDOWN DUE TO TWO AUXILIARY FEEDWATER PUMPS BEING  |
| INOPERABLE.                                                                  |
|                                                                              |
|                                                                              |
| Commenced Unit 2 plant shutdown to comply with Technical Specification       |
| 3.7.1.2.b: Two Auxiliary Feedwater pumps inoperable.  Unit 2 Turbine Driven  |
| Auxiliary Feedwater pump was inoperable due to scheduled maintenance.  Unit  |
| 2 "2 East" Motor Driven Auxiliary Feedwater pump was declared inoperable due |
| to a failure of associated room cooling (room cooler inoperable) required by |
| administrative procedure PMP 4030.001.001, Impact of Safety Related          |
| Ventilation on the Operability of Technical Specification Equipment.  All    |
| other systems fully are operable.                                            |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38198       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HONEYWELL INTERNATIONAL, INC.        |NOTIFICATION DATE: 08/10/2001|
|   RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION      |NOTIFICATION TIME: 11:24[EDT]|
| COMMENTS: UF6 CONVERSION (DRY PROCESS)         |EVENT DATE:        08/10/2001|
|                                                |EVENT TIME:        09:45[CDT]|
|                                                |LAST UPDATE DATE:  08/10/2001|
|    CITY:  METROPOLIS               REGION:  3  +-----------------------------+
|  COUNTY:  MASSAC                    STATE:  IL |PERSON          ORGANIZATION |
|LICENSE#:  SUB-526               AGREEMENT:  Y  |ANNE MARIE STONE     R3      |
|  DOCKET:  04003392                             |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W. LESSIG                    |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SMALL URANIUM HEXAFLUORIDE RELEASE ONSITE                                    |
|                                                                              |
| The licensee reported that from 0945 to 0950 CDT, a small UF6 release        |
| occurred in the feeds material building. No material left the site, nor did  |
| the licensee declare an Alert. Two individuals were exposed to fumes from    |
| the leak. Those individuals were treated with oxygen at the facility and     |
| transported to a local hospital. The UF6 leak has been stopped.              |
|                                                                              |
| The exact quantity of material released has yet to be determined. The        |
| licensee is currently conducting an investigation of this event.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38199       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 08/10/2001|
|    UNIT:  [1] [2] [3]               STATE:  CT |NOTIFICATION TIME: 13:18[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        08/10/2001|
+------------------------------------------------+EVENT TIME:        10:15[EDT]|
| NRC NOTIFIED BY:  GENE OLSON                   |LAST UPDATE DATE:  08/10/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|2     N          Y       92       Power Operation  |92       Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANNED OFFSITE NOTIFICATION REGARDING A FISH KILL IN THE DISCHARGE QUARRY   |
| DUE TO A RECENT SUSTAINED HEAT WAVE IN THE NORTHEAST                         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "A visual inspection by Millstone [station biologists] on August 10, 2001,   |
| revealed approximately 50 dead [Tautog] (blackfish) in the discharge quarry  |
| by the fish barrier.  A subsequent dive into the quarry by station           |
| biologists [revealed] 2 additional dead Tautog along the fish barrier.  No   |
| additional moralities or other species were found on the bottom of the       |
| quarry."                                                                     |
|                                                                              |
| "The fish most likely died as a result of the sustained elevated             |
| temperatures during the week of August 6, 2001, experienced throughout New   |
| England and Connecticut.  Intake water temperatures have risen above 70      |
| degrees F with discharge temperatures about 98 degree F.  Water temperatures |
| in the quarry have climbed to above 90 degrees F at times during the week.   |
| Tautog are known to have decreased resistant when water temperatures are     |
| above 90 degrees F."                                                         |
|                                                                              |
| "Station [biologists] continue to monitor fish in the quarry."               |
|                                                                              |
| The licensee stated that there was nothing unusual about the temperature     |
| deltas across the condensers and that discharge temperatures are normal.     |
| The licensee also stated that load has been reduced on Unit 2 in order to    |
| keep condenser pressure below the condenser low pressure alarm setpoint and  |
| to maintain discharge temperatures within acceptable limits.  The discharge  |
| temperatures for Unit 3 were reported to be normal with the unit at full     |
| power.                                                                       |
|                                                                              |
| The licensee plans to notify the NRC resident inspector and the State        |
| Department of Environmental Protection.                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38200       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 08/10/2001|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 19:52[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        08/10/2001|
+------------------------------------------------+EVENT TIME:        18:10[EDT]|
| NRC NOTIFIED BY:  ROSS MOONITZ                 |LAST UPDATE DATE:  08/10/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       84       Power Operation  |84       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF GREATER THAN 25% OF THE EMERGENCY PREPAREDNESS SIRENS DUE TO POWER   |
| OUTAGES FROM ELECTRICAL STORMS                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[A total of 26 out of] 97 emergency preparedness sirens (>25%) are out of   |
| service due to power outages from electrical storms.  [This includes 20 out  |
| of] 27 in York County, 2 in Herford County, 2 in Lancaster County, 1 in      |
| Cecil County, and 1 in Chester County.  Plans are in progress to restore     |
| power."                                                                      |
|                                                                              |
| The licensee reported that all systems functioned as required and that there |
| was nothing unusual or misunderstood.  The licensee also reported that there |
| was no loss of offsite power.                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| ***** UPDATE FROM JACK POPIELARSKI TO LEIGH TROCINE RECEIVED AT 2101 ON      |
| 08/10/01 *****                                                               |
|                                                                              |
| The licensee also notified York County.  The NRC operations officer notified |
| the R1DO (Holody).                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38201       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 08/10/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 23:02[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        08/10/2001|
+------------------------------------------------+EVENT TIME:        21:15[EDT]|
| NRC NOTIFIED BY:  ERIC DEMONCH                 |LAST UPDATE DATE:  08/10/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       84       Power Operation  |84       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNPLANNED REACTOR PROTECTION SYSTEM (RPS) SYSTEM/SAFETY SYSTEM ACTUATIONS    |
| WHILE CRITICAL                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The unit] received [an] isolation of the [transverse incore probe (TIP)]   |
| purge system and the offgas system during [an] electrical transient on the   |
| 230kV distribution system.  [The licensee believes] the isolations were      |
| caused by the voltage fluctuations felt in the plant from the grid.  Since   |
| the TIP purge isolation is processed through [the reactor protection system  |
| (RPS)] and offgas from the offgas [radiation] monitors, this falls under     |
| actuation of a safety system while critical."                                |
|                                                                              |
| "[The licensee] reset isolations and restored systems to normal."            |
|                                                                              |
| The licensee stated that the isolation signals that were processed did not   |
| show up on any alarms.  Alarms were received but nothing specific to         |
| indicate the isolations.  This may have been due to voltage                  |
| fluctuations/losses as a result of power/instrument panels that transferred  |
| to their alternate power supplies.  The voltage fluctuations on the in-house |
| 4160V buses were attributed to the electrical transient on the 230kV         |
| distribution system.                                                         |
|                                                                              |
| There was severe weather in the area at the time of this event.  As a        |
| result, one of two 230kV outgoing power lines and both 34.5kV feed lines     |
| were lost.  All of these lines have since been returned to service.  The     |
| licensee stated that offsite power was never lost because one 230kV line     |
| remained available to backfeed/supply the 34.5kV buses.                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38202       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 08/12/2001|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 12:16[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        08/12/2001|
+------------------------------------------------+EVENT TIME:        07:46[CDT]|
| NRC NOTIFIED BY:  DEAN CURTLAND                |LAST UPDATE DATE:  08/12/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     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     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DUE TO DECREASING REACTOR WATER LEVEL AND GROUP 1       |
| ISOLATION DUE TO LOW REACTOR PRESSURE WHILE IN RUN                           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 07:46:00 [CDT], a reactor water low-level alarm was received.  The       |
| reactor operator verified the low-level condition and took manual control of |
| feedwater level control.  The operator matched feedwater and steam flow.  At |
| 07:46:28 [CDT], the 'B' feedwater pump tripped on low suction pressure.  A   |
| manual scram was inserted at 07:46:42 [CDT] due to lowering reactor water    |
| level.  Level dropped below 170 [inches] on the reactor scram [as expected], |
| and [Group 2, 3, and 4 isolations] were received.  All isolations went to    |
| completion.  At 07:47:48 [CDT], a Group 1 isolation was received on the 850  |
| psig low reactor pressure in Run isolation signal.  The operator was in the  |
| process of [taking] the mode switch [out of] Run, but the isolation occurred |
| before this action could be completed.  All [main steam isolation valves]    |
| closed on the Group 1 isolation signal.  Reactor level increased to the high |
| level trip following the reactor scram, as expected, and the 'A' feedwater   |
| pump tripped.  Due to the Group 1 isolation, the operating crew elected to   |
| manually initiate Low Low Set pressure control using the safety relief       |
| valves.  A relief valve was opened, arming Low Low Set, and the two valves   |
| lowered reactor pressure to 900 psig.  The Group 1 was reset, and main steam |
| line drains to the condenser are being used to control pressure.  The 'A'    |
| feedwater pump high level trip has been reset and is maintaining level."     |
|                                                                              |
| "All systems responded as expected.  The plant is currently in Hot Shutdown  |
| at 800 psig.  Plans are being reviewed to determine the length of the forced |
| outage.  Preliminary investigations indicate that the 'B' feedwater pump     |
| minimum flow valve may have failed open to initiate the event."              |
|                                                                              |
| The licensee stated that there were no maintenance or surveillance           |
| activities ongoing at the time of the event.  All control rods fully         |
| inserted following the manual reactor scram.  All containment parameters are |
| currently normal, and offsite power is available.                            |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+


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