The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for February 16, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/12/1999 - 02/16/1999

                              ** EVENT NUMBERS **

35366  35367  35368  35369  35370  35371  

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35366       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U. S. ARMY (ACALA)                   |NOTIFICATION DATE: 02/12/1999|
|LICENSEE:  U. S. ARMY (ACALA)                   |NOTIFICATION TIME: 16:38[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        02/10/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  02/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TIM MOHS                     |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST MUZZLE REFERENCE SENSOR                                                 |
|                                                                              |
| A unit stationed in Kuwait removed a foggy muzzle reference sensor (MRS)     |
| containing 10 curies of tritium.  The MRS was triple bagged and transported  |
| to headquarters for maintenance in a truck, which was used for transporting  |
| garbage to the dump before its removal at headquarters.  The MRS was         |
| apparently dumped with the garbage in a Kuwait dump.  A safety investigation |
| is underway.  Their reference number is 99-11.  The device is not considered |
| a hazard to personnel.                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35367       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 02/12/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:11[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        02/12/1999|
+------------------------------------------------+EVENT TIME:        14:50[EST]|
| NRC NOTIFIED BY:  JOHN S. SCHORK               |LAST UPDATE DATE:  02/12/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAURIE PELUSO        R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| CONTAINMENT AIR SAMPLING SYSTEM PLACED OUT OF SERVICE FOR EXCESSIVE LEAKAGE  |
|                                                                              |
| The licensee discovered that two automatic closure containment isolation     |
| valves (CM-V-1 and 3) on the containment air sampling system process lines   |
| have excessive leakage.  This was discovered as a result of maintenance      |
| troubleshooting of leakage found in the containment air sampling system      |
| during the annual containment atmosphere post-accident sampling system       |
| surveillance.  The redundant isolation valves have been closed, and the      |
| monitor can remain out of service for 72 hours with 8-hour grab samples      |
| being taken of containment atmosphere per Technical Specification 3.1.8.     |
| Work is underway to install a passive barrier (pipe cap) on the inside       |
| containment end of each process line, after which the associated valves will |
| be repaired.                                                                 |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35368       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 02/12/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 18:30[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        02/12/1999|
+------------------------------------------------+EVENT TIME:        08:54[EST]|
| NRC NOTIFIED BY:  WILLIAM KISNER               |LAST UPDATE DATE:  02/12/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTIFIED THE STATE OF FLORIDA, DEPARTMENT OF HEALTH, OFFICE OF RADIATION     |
| CONTROL                                                                      |
|                                                                              |
| The State of Florida, Department of Health, Office of Radiation Control was  |
| notified of the following event.                                             |
|                                                                              |
| An individual departing alarmed the portal monitor.  Upon investigation it   |
| was discovered that the individual's jacket contained a "hot particle."  The |
| individual is a French national working on site on the Appendix R (Mecatiss) |
| project.  The individual was aware of the contamination and had exited       |
| French nuclear plant(s) with out any questions.  The particle was removed    |
| and the jacket returned.  The particle was determined to be Co-60 and reads  |
| 450,000 dpm by direct frisk with an RM-25 meter with standard pancake probe. |
| The Beta reading was 8 millirem per hour, open window, with an RO-20 survey  |
| instrument.  This has been determined to be reportable under                 |
| 10CFR20.2203(a)(3)(ii), and a 30 day written report will be issued.          |
|                                                                              |
| The licensee notified the NRC Resident Inspector and Region 2 Division of    |
| Reactor Safety (Bruce Mallett).                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35369       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COLTEC INDUSTRIES                    |NOTIFICATION DATE: 02/15/1999|
|LICENSEE:  SYNCHRO-START CORPORATION            |NOTIFICATION TIME: 15:26[EST]|
|    CITY:  BELOIT                   REGION:  3  |EVENT DATE:        01/20/1999|
|  COUNTY:                            STATE:  WI |EVENT TIME:             [CST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  02/15/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |LAURIE PELUSO        R1      |
+------------------------------------------------+THOMAS DECKER        R2      |
| NRC NOTIFIED BY:  JAMES C. GOLDING             |JOHN PELLET          R4      |
|  HQ OPS OFFICER:  LEIGH TROCINE                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10-CFR-PART-21 NOTIFICATION FROM COLTEC INDUSTRIES, FAIRBANKS MORSE ENGINE   |
| DIVISION, REGARDING SYNCHRO-START -- ESSB-4AT SPEED SWITCHES, MODEL SA2110   |
|                                                                              |
| The following text is a portion of a facsimile received from the Coltec      |
| Industries:                                                                  |
|                                                                              |
| "On January 20, 1999, Coltec Industries, Fairbanks Engine Division (FMED),   |
| became aware of a potential safety hazard associated with the Synchro-Start  |
| -- ESSB-4AT speed switches supplied to PSE&G -- Hope Creek Nuclear Power     |
| Station.  FMED had supplied four Synchro-Start ESSB-4AT Model-SA2110 speed   |
| switches to Hope Creek in late 1997 and early 1998, which malfunctioned      |
| after approximately 70 hours of energization.  Hope Creek had previously     |
| evaluated the failures as not being a substantial safety hazard.             |
|                                                                              |
| "In the ... root cause investigation, FMED evaluated the starting circuitry  |
| and confirms that this is not a substantial safety hazard at Hope Creek due  |
| to redundant circuitry.  However, the investigation revealed that it is      |
| likely that one more ESSB-4AT Model-SA2 110 speed switch manufactured by     |
| Synchro-Start may have been supplied to the nuclear industry or non-nuclear  |
| application by a supplier other than Coltec Industries. The list of possible |
| recipients of the suspect speed switch are:  Wolf Creek Nuclear, Engine      |
| Systems Inc, Florida Keys Electric, Interstate Power Company, Rolls Royce,   |
| and Traycanna.  Therefore, notification is being made of the potential       |
| substantial safety hazard that might exist at other nuclear facilities that  |
| have purchased an ESSB-4AT speed switch in late 1997 and early 1998.         |
|                                                                              |
| "The Engineering Report also determined the root cause of the speed switch   |
| failures to be personnel error at Synchro-Start.  A personnel error was made |
| by picking the wrong current limiting resistor from stock for installation   |
| into the speed switch power supply circuit card.  Corrective actions have    |
| been taken by Synchro-Start to prevent recurrence including moving the stock |
| location of the resistors, retraining personnel, and changing procedures to  |
| verify proper resistor during bench testing.                                 |
|                                                                              |
| The Engineering Report from Coltec Industries also stated, "While the        |
| degradation described in the Part 21... pertains only to PSE&G at Hope Creek |
| and the ESSB-4AT speed switch, Coltec Engineering has also evaluated the     |
| applicability to other power stations that use a similar speed switch, such  |
| as models ESSB-2AT and --3AT, in a similar circuit arrangement.  These other |
| models of speed switch would also use the same internal power supply.        |
| Coltec identifies the power stations listed below.  It should be noted that  |
| Hope Creek is the only installation that employs the ESSB-4AT for speed      |
| switch requirements.  Coltec has not been notified of any other speed switch |
| degradations at any of the other nuclear power stations; Hope Creek is the   |
| only instance.                                                               |
|                                                                              |
| "Alabama Power--Farley                                                       |
| Entergy--Arkansas Nuclear One                                                |
| Georgia Power--Hatch I                                                       |
| Detroit Edison--Fermi 2                                                      |
| Northeast Utilities--Millstone 3                                             |
| Public Service New Hampshire--Seabrook                                       |
| Angra Brazil                                                                 |
| Duquesne Light--Beaver Valley                                                |
| SCE&G--V C Summer                                                            |
| PECO--Limerick                                                               |
| Union Electric--Callaway                                                     |
| Kansas Gas and Electric--Wolf Creek                                          |
| PSE&G--Hope Creek                                                            |
|                                                                              |
| "Coltec Engineering has also reviewed the starting circuitry for the above   |
| mentioned power stations.  All of the above stations have the similar        |
| redundant starting circuitry found at Hope Creek with four exceptions.  The  |
| four exceptions are Alabama Power, Detroit Edison, Northeast Utilities, and  |
| Angra Brazil.  At these four plants, if the installed speed switch should    |
| fail, the diesel would then fail to start, because of the failed speed       |
| switch, and not perform its intended design function.  At this time, there   |
| is no substantive safety hazard because none of these plants have received   |
| any suspect speed switches.                                                  |
|                                                                              |
| "Therefore, this investigation and finding at Hope Creek is not considered a |
| substantial safety hazard as defined by [10 CFR] Part 21.  This is due to    |
| the redundancy in the starting circuitry.  However, since there may be one   |
| remaining speed switch with an improper internal power supply, there may be  |
| a safety hazard depending on the configuration of the starting circuitry and |
| the incorporation of redundancy at that site."                               |
|                                                                              |
| (Call the NRC operations officer for a contact address and telephone         |
| number.)                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35370       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/15/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 16:58[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/15/1999|
+------------------------------------------------+EVENT TIME:        15:19[CST]|
| NRC NOTIFIED BY:  JIM McKAY                    |LAST UPDATE DATE:  02/15/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) GROUP IV ISOLATION DURING TESTING     |
|                                                                              |
| During a quarterly HPCI test run, a Group IV high steam flow isolation was   |
| received.  The cause of the high steam flow isolation is under               |
| investigation.                                                               |
|                                                                              |
| The licensee stated that the isolation had not yet been reset and that all   |
| other emergency core cooling systems are operable and available if needed.   |
| The unit is currently in a 14-day limiting condition for operation because   |
| HPCI is out of service.                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35371       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 02/15/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 22:33[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/15/1999|
+------------------------------------------------+EVENT TIME:        21:45[EST]|
| NRC NOTIFIED BY:  GARY CLEMENTS                |LAST UPDATE DATE:  02/15/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT UNIT 1 FUELING WATER STORAGE TANK (FWST) CHANNEL 3 WAS NOT    |
| PLACED IN BYPASS WITHIN 6 HOURS OF BECOMING INOPERABLE                       |
|                                                                              |
| FWST Channel 3 was tripped shortly after 0800 today to facilitate a          |
| modification to change out a transmitter.  With this channel removed from    |
| service, plant technical specifications require the licensee to place the    |
| channel in bypass within 6 hours.  At 2145, it was discovered that the       |
| channel had not been placed in bypass within 6 hours of becoming inoperable, |
| and the unit entered Technical Specification 3.0.3.  The channel was         |
| successfully placed in bypass within 2 minutes, and Technical Specification  |
| 3.0.3 was exited at 2147.                                                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector                      |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 25, 2021