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Event Notification Report for September 22, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/21/1999 - 09/22/1999

                              ** EVENT NUMBERS **

36091  36203  36204  36205  36206  36207  36208  36209  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36091       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 08/31/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 02:21[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        08/30/1999|
+------------------------------------------------+EVENT TIME:        22:22[CDT]|
| NRC NOTIFIED BY:  GREEN                        |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|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                                   
+------------------------------------------------------------------------------+
| FAILURE OF A SINGLE TRAIN SYSTEM THAT IS REQUIRED TO MITIGATE THE            |
| CONSEQUENCES OF AN ACCIDENT                                                  |
|                                                                              |
| On 8/30/99 at 2222 while performing maintenance on SW-MOV-650MV, Reactor     |
| Equipment Cooling (REC) heat exchanger "A" Service Water (SW) Outlet Valve,  |
| SW-MOV-650MV was manually opened while disconnecting Limit Switches. The     |
| valve was opened to a point that allowed 2475 Gallons Per Minute (GPM) of    |
| service water flow thru the "A" REC heat exchanger.  Service water flow      |
| greater than 1200 GPM thru the "A" REC heat exchanger results in the "A"     |
| Service Water subsystem being inoperable (LCO 3.7.2) which requires          |
| restoration of the "A" Service Water subsystem within 30 days.  LCO 3.8.1    |
| was entered for Diesel Generator 1 (DG1) because it was declared inoperable  |
| due to the Service Water being inoperable. The Control Room Emergency        |
| Filtration System (CREFS), which is a single train system, was aligned to a  |
| bus that would be powered from DG1 in the event of an accident.  This        |
| condition resulted in CREFS also being declared inoperable (LCO 3.7.4)       |
|                                                                              |
| When the increased flow though the "A" REC heat exchanger was discovered by  |
| a Control Room Operator, the Valve Technicians performing the maintenance    |
| were instructed to manually close SW-MOV-650MV until Service Water flow      |
| through the "A" REC Heat Exchanger was reduced below 1200 GPM, which was     |
| completed at 2238. All of the previously mentioned LCO's were also exited at |
| this time.  At the time this event occurred both sources of offsite power    |
| were available and DG2 was determined to not be affected by this condition.  |
|                                                                              |
| The Resident Inspector was notified.                                         |
|                                                                              |
| *** UPDATE ON 9/21/99 @ 0259 BY GREEN TO GOULD ***    EVENT RETRACTION       |
|                                                                              |
| SUBSEQUENT INVESTIGATION HAS DETERMINED THAT D/G#1 WAS ALWAYS CAPABLE OF     |
| PERFORMING ITS SAFETY FUNCTION DURING THE EVENT.  THEREFORE, CREFS REMAINED  |
| OPERABLE AND THIS EVENT IS BEING RETRACTED.                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.   REG 4 RDO(TAPIA) WAS INFORMED         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36203       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 00:56[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        09/21/1999|
+------------------------------------------------+EVENT TIME:        00:50[EDT]|
| NRC NOTIFIED BY:  BOYER                        |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT SUMMERS       R1      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIALLY CONTAMINATED INJURED PERSON TRANSPORTED OFFSITE.                 |
|                                                                              |
| THE LICENSEE TRANSPORTED AN INDIVIDUAL , WHO INJURED HIS LOWER BACK WHILE    |
| WORKING INSIDE CONTAINMENT ON THE UPPER MANWAY, TO THE HERSHEY MEDICAL       |
| CENTER.  HE MAY HAVE BEEN CONTAMINATED, SO HE WAS ACCOMPANIED BY HEALTH      |
| PHYSICS PERSONNEL TO THE HOSPITAL.                                           |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED                                      |
|                                                                              |
| *** UPDATE ON 9/21/99 @ 0209 BY BOYER TO GOULD ***                           |
|                                                                              |
| THE INDIVIDUAL WAS NOT CONTAMINATED, HOWEVER, HIS CLOTHING WAS AND IT IS     |
| BEING RETURNED TO THE SITE.                                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36204       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 08:04[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        09/21/1999|
+------------------------------------------------+EVENT TIME:        04:38[EDT]|
| NRC NOTIFIED BY:  ARAB                         |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE                                                     |
|                                                                              |
| During performance of the calibration/functional surveillance test of the    |
| HPCI equipment room temperature instrumentation, the trip unit being tested  |
| failed upscale.  A step in the surveillance procedure places a keylock       |
| switch in the TEST position, preventing a HPCI system Channel B isolation    |
| and HPCI Turbine Trip. The trip unit was declared inoperable.                |
|                                                                              |
| Fermi 2 Technical Specifications require that the inoperable instrument      |
| channel be restored to OPERABLE status in 6 hours or that the ACTION be      |
| performed to close the affected system isolation valves within 1 hour and    |
| declare the system inoperable.                                               |
|                                                                              |
| On September 21, 1999 at 0438 hours, the affected HPCI isolation valves were |
| isolated and the HPCI system was declared inoperable, putting the plant in a |
| 14 day LCO action statement.                                                 |
|                                                                              |
| Efforts to replace the failed trip unit are in progress.                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36205       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/21/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:28[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/21/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:08[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/21/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  WILLIAM POERTNER             |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO SANITARY WATER SUPPLY LINE RUPTURE.              |
|                                                                              |
| At approximately 1008 hours on 9/21/99, the Ohio EPA and the National        |
| Response Center were notified of a sanitary water supply line rupture from   |
| one of the plant's 24 inch sanitary water supply lines.  This rupture may    |
| have an effect on the environment as sanitary water (Drinking Water) enters  |
| local water sheds.  Follow-up notifications were made to the above agencies  |
| to inform them that the leak was isolated at 1040 hours.                     |
|                                                                              |
| There was no loss of hazardous/radioactive material or                       |
| radioactive/radiological contamination exposure as a result of this event.   |
|                                                                              |
| The NRC Resident has been notified.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36206       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 15:30[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        09/21/1999|
+------------------------------------------------+EVENT TIME:        14:00[EDT]|
| NRC NOTIFIED BY:  JOHN BALLETTA                |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT SUMMERS       R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
|  SECTION OF FIRE PROTECTION PIPING NOT SEISMICALLY SUPPORTED PER NRC INFO    |
| NOTICE 98-31                                                                 |
|                                                                              |
| A CONTRACTOR ASSISTING THE LICENSEE WITH A REVIEW OF FIRE PROTECTION SYSTEM  |
| PIPING                                                                       |
| WITH RESPECT TO INFORMATION OUTLINED IN NRC INFORMATION NOTICE 98-31         |
| IDENTIFIED POTENTIALLY HIGH IMPACT LOADS ON A FOUR INCH DIAMETER SECTION OF  |
| FIRE PROTECTION SYSTEM PIPING IN THE PRIMARY AUXILIARY BUILDING.  HIGH       |
| IMPACT LOADS COULD BE IMPOSED ON THE VICTAULIC COUPLINGS ON THE PIPING       |
| DURING A SEISMIC EVENT.                                                      |
|                                                                              |
| FAILURE OF THIS PIPING COULD CAUSE FLOODING IN THE LOWER LEVEL OF THE        |
| PRIMARY AUXILIARY BUILDING WHICH INCLUDES THE RHR PUMPS.  WITHIN THE NEXT 24 |
| HOURS, THE LICENSEE PLANS TO INSTALL TWO ADDITIONAL PIPE SUPPORTS ON THIS    |
| SECTION OF PIPING TO LIMIT PIPE DISPLACEMENT AND TO LIMIT THE POTENTIAL FOR  |
| IMPACT LOADING ON THIS SECTION OF PIPING.                                    |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36207       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/21/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:10[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/20/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        20:18[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/21/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |JOHN SURMEIER        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF CASTLE                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Site DOE Rep notified of the loss of one NCSA control at a DOE regulated   |
| area of the site -                                                           |
|                                                                              |
| At 2018 on 09/20/99, it was determined that a Nuclear Criticality Safety     |
| Approval (NCSA) requirement was violated in the X-705 West Annex which is a  |
| Department of Energy (DOE) regulated area of the Portsmouth site. This event |
| was reportable to DOE as a loss of one NCSA control.  This notification to   |
| another government agency is reportable to the NRC as a four hour event      |
| notification report.                                                         |
|                                                                              |
| There was no radioactive or radiological contamination exposure as a result  |
| of this event.                                                               |
|                                                                              |
| Portsmouth personnel notified the NRC Resident Inspector.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36208       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 20:37[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        09/07/1999|
+------------------------------------------------+EVENT TIME:        00:14[CDT]|
| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - HPCI SYSTEM INOP DUE TO HPCI STEAM SUPPLY ISOLATION VALVE NOT CLOSING      |
| DURING A TEST -                                                              |
|                                                                              |
| At 0014 CDT on 09/07/99, while performing a High Pressure Coolant Injection  |
| (HPCI) steam line flow analog trip system calibration and functional         |
| surveillance test, the HPCI steam supply isolation valve (#MO 1-2301-5)      |
| failed to close.  The licensee entered Tech Spec 3.7.D, Action 1 for an      |
| inoperable containment isolation valve, and isolated the HPCI steam supply.  |
| This action rendered the HPCI System inoperable and the licensee entered     |
| Tech Spec 3.5.A, Action 3.  This placed Unit 1 in a 14 day LCO.  This event  |
| is being reported to the NRC in accordance with 10CFR50.72(b)(2)(iii)(D), a  |
| condition that prevented the fulfillment of a safety function.               |
|                                                                              |
| The valve was repaired and declared operable at 1730 CDT on 09/07/99.        |
|                                                                              |
| The licensee is continuing to evaluate the reportability of this issue.      |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36209       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 20:41[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        09/10/1999|
+------------------------------------------------+EVENT TIME:        14:40[CDT]|
| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| -CONTROL ROOM EMERGENCY FILTRATION SYSTEM INOP DUE TO FAILING ITS            |
| SURVEILLANCE TEST-                                                           |
|                                                                              |
| At 1440 CDT on 09/10/99, while performing the Control Room Emergency         |
| Filtration (CREF) System monthly surveillance test, the system flow rate was |
| found to be 2317 scfm.  The required tech spec flow rate is 2000 scfm +/-    |
| 10%.  The licensee declared the CREF System inoperable per Tech Spec 3.8.D   |
| and entered a 7 day LCO.  This event is being reported to the NRC in         |
| accordance with 10CFR50.72 (b)(2)(iii)(D), a condition that prevented the    |
| fulfillment of a safety function.                                            |
|                                                                              |
| The licensee declared the CREF System operable 40 minutes later after        |
| adjusting the air flow.                                                      |
|                                                                              |
| The licensee is continuing to evaluate the reportability of this issue.      |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+