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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
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