Event Notification Report for September 20, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/17/1999 - 09/20/1999
** EVENT NUMBERS **
36043 36064 36143 36170 36185 36186 36187 36188 36189 36190 36191 36192
36193 36194 36195 36196 36197 36198 36199 36200 36201
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36043 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/19/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:56[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/19/1999|
+------------------------------------------------+EVENT TIME: 11:58[EDT]|
| NRC NOTIFIED BY: CHARLIE KOCIS |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH MOTOR-DRIVEN AUXILIARY BOILER FEEDWATER PUMPS AUTO STARTED DURING |
| SURVEILLANCE ACTIVITIES. |
| |
| On August 19, 1999, at approximately 1158 EDT, both motor-driven auxiliary |
| boiler feedwater pumps automatically started after exceeding their 28-second |
| time delay during performance of the low-low steam generator water level |
| section of procedure 3PT-M13B, "Reactor Protection Logic Channel Functional |
| Test." The operators secured the pumps before discharge pressure exceeded |
| steam generator pressure preventing them from feeding the steam generators. |
| As a result, there was no positive reactivity addition. The operators |
| anticipated these results because the test states in its precaution and |
| limitations section that the pumps would start if the action required by the |
| test is not completed within the 28-second time delay. |
| |
| The NRC resident inspector has been notified by the licensee. |
| |
| *************** UPDATE AT 1520 EDT ON 09/17/99 FROM BRIAN ROKES TO LEIGH |
| TROCINE *************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The [licensee] is withdrawing the 4-hour non-emergency notification made on |
| August 19, 1999, at 1456 hours (ENS Log No. 36043). The notification |
| reported the automatic starting of both motor-driven auxiliary boiler |
| feedwater (AFW) Pumps after exceeding their start logic 28-second time delay |
| during performance of the Low-Low Steam Generator Water Level section of |
| procedure 3PT-M13B, 'Reactor Protection Logic Channel Functional Test,' as |
| an engineered safety feature actuation." |
| |
| "Upon further assessment, [the licensee] determined that this event is not |
| reportable because the event meets the intent of the exception criteria of |
| 10 CFR 50.72(b)(2)(ii)(A), which states, 'The actuation results from and is |
| part of the preplanned sequence during testing or reactor operation.' Test |
| 3PT-M13B intended to initiate the AFW pump start logic for both motor-driven |
| AFW pumps and the steam-driven AFW pump for reasons other than to mitigate |
| the consequences of an event. The intended result is to start the |
| steam-driven AFW pump but to take action during the 28-second time delay to |
| prevent the motor-driven AFW pumps from actually operating. Action is also |
| taken to prevent the steam-driven AFW pump from delivering flow. Test |
| 3PT-M13B expects the motor-driven pumps to operate if action is not taken |
| within the 28-second delay time delay. The test requires coordination with |
| an operator before proceeding with the test step that initiates the timer |
| for auto start of the motor-driven AFW pumps. The test states that each of |
| the test logic sequence actions must be completed within 28 seconds to |
| prevent auto start of the motor-driven AFW pumps." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Della Greca). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36064 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/24/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:54[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/23/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:18[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/18/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RON CRABTREE | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM SLAVE UNITS MAY NOT MEET REQUIRED |
| STANDARD |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: |
| |
| "At 1718 HOURS ON 08/23/99, THE PLANT SHIFT SUPERINTENDENT WAS NOTIFIED THAT |
| THE CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) SLAVE UNITS MAY NOT MEET [THE] |
| ANSI 8.3, SECTION 5.5, STANDARD. ANSI 8.3 IDENTIFIES THAT THE CAAS SYSTEM |
| SHALL AUTOMATICALLY INITIATE AN EVACUATION ALARM SIGNAL WITHIN � SECOND OF |
| THE ALARM SETPOINT BEING EXCEEDED. ENGINEERING COULD NOT PROVIDE ASSURANCE |
| THAT THE CAAS SLAVE UNITS WOULD MEET THIS REQUIREMENT. FACILITIES WITH CAAS |
| CLUSTERS (DETECTORS) AND THEIR EVACUATION HORNS ARE COMPLIANT WITH [THE] |
| ANSI 8.3, SECTION 55, REQUIREMENT. |
| |
| "THE SAFETY SIGNIFICANCE IS MINIMAL SINCE THE SLAVES WILL STILL PROVIDE |
| ALARM INDICATION |
| BEFORE SIMILAR INDICATIONS WOULD BE PROVIDED UNDER THE [TECHNICAL SAFETY |
| REQUIREMENT LIMITING CONDITION FOR OPERATION] ACTIONS IMPLEMENTED." |
| |
| FOR INFORMATION: THE ALARMS DISCUSSED HERE ARE REMOTE ALARMS IN AREAS |
| WITHIN SO MANY FEET OF THE AREA OF CONCERN, BUT OUTSIDE THE BUILDING OR |
| ROOM. |
| |
| PLANT PERSONNEL HAVE INFORMED THE NRC RESIDENT INSPECTOR AND THE ONSITE |
| DEPARTMENT OF ENERGY (DOE) REPRESENTATIVE. |
| |
| *** UPDATE ON 09/18/99 @ 1007 FROM HALCOMB TO GOULD *** EVENT RETRACTION |
| |
| THIS EVENT IS BEING RETRACTED SINCE TESTING OF ALL SLAVE FACILITY EVACUATION |
| HORNS HAS BEEN COMPLETED, AND IT WAS DETERMINED THAT THEY WILL INITIATE AN |
| ALARM SIGNAL WITHIN � SECOND AS REQUIRED BY ANSI STANDARD 8.3. THEREFORE, |
| THIS EVENT IS NOT REPORTABLE. |
| |
| PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY |
| THE DOE SITE REPRESENTATIVE. THE R3DO (SHEAR) AND NMSS EO (SHERR) WERE |
| NOTIFIED BY THE NRC OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36143 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/10/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:39[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/09/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/18/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS R3 |
| DOCKET: 0707002 |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM HORN INOPERABLE DUE TO IMPROPER |
| CONNECTION |
| |
| At 1500 hours, on 09/09/99, the Criticality Accident Alarm System (CAAS) |
| slave horn in the X-344B building was discovered to be not connected to the |
| X-344A CAAS evacuation alarm as designed. During troubleshooting |
| activities, maintenance personnel found that the horn was connected to the |
| gas release alarm system instead of the CAAS evacuation horn system. |
| |
| This condition is reportable to the NRC per 10 CFR 76.120(c), "Safety |
| Equipment Failure/Actuation." The equipment is required by a technical |
| safety requirement (TSR) to be available and operable, and no redundant |
| equipment is available and operable to perform the required safety |
| function. |
| |
| There was no loss of hazardous material or radioactive/radiological |
| contamination exposure as a result of this event. |
| |
| The NRC resident inspector has been notified by Portsmouth personnel. |
| |
| *** UPDATE ON 09/18/99 @ 1007 FROM HALCOMB TO GOULD *** EVENT RETRACTION |
| |
| THIS EVENT IS BEING RETRACTED AFTER FURTHER INVESTIGATION AND TESTING HAS |
| DETERMINED THAT THE X-344B FACILITY EVACUATION HORN IS NOT NEEDED TO SATISFY |
| TSR AUDIBILITY REQUIREMENTS SINCE THE X-344A EAST CLUSTER HORN PROVIDES THE |
| REQUIRED AUDIBILITY. THEREFORE, REPORTABILITY WAS NOT REQUIRED. |
| |
| PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY |
| THE DEPARTMENT OF ENERGY SITE REPRESENTATIVE. THE R3DO (SHEAR) AND NMSS EO |
| (SHERR) WERE NOTIFIED BY THE NRC OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36170 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 09/16/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 02:32[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 09/16/1999|
+------------------------------------------------+EVENT TIME: 01:55[EDT]|
| NRC NOTIFIED BY: KEVIN ABELL |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|10 CFR SECTION: |ANNE BOLAND, REG 2 IRC |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PARTIAL LOSS OF EMERGENCY SIREN CAPABILITY DURING HURRICANE FLOYD |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The Plant was operating at 100% power when 22 Warning Sirens became |
| inoperable due to loss of power. The counties of Chatham, Harnett, and Wake |
| are each affected. Wind speeds in these areas are higher than normal due to |
| the effects of hurricane Floyd. One additional Warning Siren in Wake County |
| was previously inoperable due to failing its periodic test. Repairs will be |
| made when wind speed subsides." |
| |
| Harris has a total of 81 sirens of which 22 represents slightly greater than |
| 25%. Residents living within 5 miles of the site have tone alert radios as |
| a backup. |
| |
| The licensee informed the NRC resident inspector and plans to inform |
| state/local agencies. |
| |
| ******************** UPDATE AT 1558 ON 09/17/99 FROM GARY WARD TO LEIGH |
| TROCINE ******************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "As of 1400 on [09/17/99], 67 of 81 warning sirens are operable. Operable |
| sirens are available in each of the four surrounding counties. |
| Additionally, alternative compensatory measures, such as tone alert radios |
| and route alerting are in place for public notification in the event of an |
| actual emergency." |
| |
| "Harris nuclear plant is now below the threshold for normal reporting of |
| inoperable sirens. Power restoration [to the remaining sirens] will |
| continue throughout the weekend." |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R2DO (Christensen). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36185 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 06:49[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 06:05[EDT]|
| NRC NOTIFIED BY: MICHAEL MALENO |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF DIRECT COMMUNICATIONS TO BOTH VERMONT AND MASSACHUSETTS STATE |
| POLICE |
| |
| The licensee discovered at 0605 EDT that the Nuclear Alert System was not |
| available. Repairs are in progress. |
| |
| *** UPDATE ON 09/17/99 AT 1111 EDT FROM MALENO TAKEN BY MacKINNON *** |
| |
| At 1000 hours, power was restored to the Nuclear Alert System. |
| |
| The R1DO (Niel Della Greca) was notified by the NRC operations officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36186 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 10:40[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 09:40[EDT]|
| NRC NOTIFIED BY: BRIAN ROKES |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: |FEMA, DOE, USDA, HHS FAX |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |EPA, DOT (via NRC) FAX |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO THE NEW YORK STATE DEPARTMENT OF CONSERVATION |
| OF A SPILL OF LESS THAN ONE GALLON OF LUBE OIL THAT WAS RELEASED INTO THE |
| PLANT'S FLOOR DRAIN SYSTEM WHICH DISCHARGES INTO THE PLANT'S COOLING WATER |
| DISCHARGE CANAL |
| |
| An oil sheen from less than a one-gallon spill of the lube oil was observed |
| on the surface of the discharge canal. The water of the discharge canal is |
| river water that has been used to cool plant equipment during plant |
| operations. The discharge canal has oil containment barriers that are |
| designed to contain a majority of the oil discharge. Cleanup of the oil |
| spill is in progress. |
| |
| The NRC resident inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36187 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 11:16[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 09:30[CDT]|
| NRC NOTIFIED BY: ROGEER CHILDERS |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: |DAVID MATTHEWS NRR |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| EMERGENCY NOTIFICATION SYSTEM AND LOCAL PHONE COMMUNICATION INOPERABLE |
| |
| The licensee reported that all FTS-200 and commercial telephone lines went |
| dead. Communication to the plant still is available via cellular telephone |
| or the load dispatcher. The licensee is investigating why the telephone |
| system is inoperable. The onsite telephone representative is working on the |
| problem. |
| |
| The NRC resident inspector has been notified of this event by the licensee. |
| |
| ********** UPDATE AT 1527 ON 09/17/99 FROM ROGER CHILDERS TO LEIGH TROCINE |
| ********** |
| |
| The cause of the problems was determined to be a line that was cut during |
| the performance of digging at a golf coarse. The line was repaired at |
| approximately 1330 CDT, and subsequent tests revealed that the commercial |
| telephone lines and the Emergency Notification System and Health Physics |
| Network lines are back in service. Based upon these tests, it was assumed |
| that the remaining FTS-2000 lines are also back in service. |
| |
| The licensee notified the NRC resident inspector and plans to make a |
| courtesy notification to the state. The NRC operations officer notified the |
| R3DO (Shear) and NRR EO (Matthews). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36188 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 11:38[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 10:50[EDT]|
| NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| GREATER THAN 10% OF THE EMERGENCY SIRENS ARE INOPERABLE DUE TO TROPICAL |
| STORM FLOYD. (See similar Indian Point Unit 3 event: #36189.) |
| |
| The licensee was notified at 1050 EDT that 14 out of 77 emergency sirens in |
| Westchester County were inoperable, 10 out of 10 emergency sirens in Putman |
| county are inoperable, 14 out of 16 emergency sirens in Orange county are |
| inoperable, and it is expected that a significant number of emergency |
| sirens in Rockland county are inoperable. Counties have initiated route |
| alerting procedures. The licensee is currently in the process of trying to |
| restore the inoperable sirens. |
| |
| The NRC resident inspector will be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36189 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 11:40[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 10:50[EDT]|
| NRC NOTIFIED BY: BRIAN ROKES |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 10% OF THEIR EMERGENCY SIRENS HAVE BECOME INOPERABLE DUE TO |
| TROPICAL STORM FLOYD. (See similar Indian Point Unit 2 event: # 36188.) |
| |
| At 1050 EDT, it was determined that the emergency siren notification system |
| was degraded in each of the four counties (Orange County, Putman County, |
| Rockland County, and Westchester County). A recent storm caused electric |
| power line outages and telephone line outages in all four counties. The |
| loss of electric and telephone lines resulted in greater than 10% of the |
| sirens not being operational in each county. It is estimated that |
| approximately 60 of the 154 sirens are not operational. The emergency plan |
| would utilize route alerting and public radio announcements to notify the |
| public in lieu of the non-operating sirens. Restoration of the sirens will |
| be coordinated with the restoration plans of the electric companies and |
| telephone companies. |
| |
| The NRC resident inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36190 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 12:44[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 11:48[EDT]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 09/18/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INOPERABLE EMERGENCY NOTIFICATION SYSTEM LINE AND PUBLIC NOTIFICATION SYSTEM |
| DUE TO A DOWNED TELEPHONE LINE |
| |
| At 1148, a local subcontractor notified the licensee that the Public |
| Notification System (a weather radio system) was inoperable. Apparently, a |
| line is down between the National Weather Service and the licensee's local |
| office. Therefore, no signal is being received from the National Weather |
| Service. Therefore, state of Vermont will be able to call the National |
| Weather Service, but the National Weather Service will be unable broadcast |
| for public notification because this telephone line is down. The licensee |
| stated that repairs are ongoing and that the line may be returned to service |
| at approximately 1500. |
| |
| A subsequent test of the licensee's Emergency Notification System line |
| revealed that it was also inoperable. |
| |
| The licensee plans to notify the NRC resident inspector; the applicable |
| local agencies; and the states of Massachusetts, Vermont, and New |
| Hampshire. |
| |
| *** UPDATE ON 09/18/99 @ 0400 FROM BROOKS TO GOULD *** |
| |
| THE PUBLIC NOTIFICATION SYSTEM WAS RETURNED TO SERVICE AT 0355 ON 09/18/99. |
| THE EMERGENCY NOTIFICATION SYSTEM WAS VERIFIED OPERABLE AT 0405 ON |
| 09/18/99. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. THE R1DO (DELLA |
| GRECA) WAS NOTIFIED BY THE NRC OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36191 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 14:21[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 13:46[EDT]|
| NRC NOTIFIED BY: STEPHEN BAKER |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 65 Power Operation |62 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A DROPPED CONTROL ELEMENT |
| ASSEMBLY |
| |
| At 1346 EDT, a control rod assembly (CEA) dropped into the core and was |
| subsequently declared inoperable. As a result, the licensee plans to |
| commence a unit shutdown at 1425 EDT in accordance with Technical |
| Specification 3.0.3. The licensee plans to place the unit in Mode 3 (Hot |
| Standby) in order to repair the CEA. |
| |
| The cause of the dropped CEA is under investigation. There were no |
| CEA-related maintenance or surveillance activities ongoing at the time of |
| the event. The unit was at reduced power (65%) to facilitate manual |
| waterbox cleaning due to condenser fouling from Hurricane Floyd. The |
| licensee stated that all systems functioned as required and that there was |
| nothing that was unusual or not understood (other than the cause of the |
| dropped CEA). |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36192 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 15:48[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 13:50[CDT]|
| NRC NOTIFIED BY: |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM ANDREWS R4DO |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABILITY OF BOTH |
| STANDBY GAS TREATMENT TRAINS (Refer to event #36195 for additional |
| information.) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1350 [CDT], it was discovered that both Z-sump pumps were inoperable, |
| which causes both standby gas treatment [(SGT)] trains to be inoperable. |
| [Technical Specification Limiting Condition for Operation (TS LCO)] 3.6.4.3, |
| Condition D, Two SGT Subsystems Inoperable in Modes 1, 2, or 3, required |
| action is to enter [TS] LCO 3.0.3 immediately. [TS] LCO 3.0.3 was entered |
| at 1350 [CDT]." |
| |
| "Surveillance testing of the Z-sump pumps was in progress due to anomalous |
| behavior of the pumps and associated circuitry earlier in the day while |
| placing the augmented offgas system in service." |
| |
| The licensee plans to place the unit in Mode 4 (Cold Shutdown). The current |
| estimated restart date is 09/20/99. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36193 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 15:50[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 15:28[EDT]|
| NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA 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
+------------------------------------------------------------------------------+
| POTENTIAL INOPERABILITY OF THE AUTOMATIC START FUNCTION OF AN AUXILIARY |
| BOILER FEEDWATER PUMP |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "With the unit in Hot Shutdown during a review of the Accident Mitigation |
| System Actuation Circuitry (AMSAC), the licensee determined that a condition |
| existed that could have rendered the automatic start of the 21 auxiliary |
| boiler feedwater pump (21 ABFP) inoperable contrary to the requirements of |
| the Safety Evaluation, 'Indian Point Unit 2 ATWS Rule (10 CFR 50.62) (TAC |
| NO. 59103),' issued May 16, 1989. [The] 21 ABFP would have failed to start |
| if the following conditions had existed: 480-volt bus 3A loss of power, no |
| black out condition or safety injection, and an AMSAC condition existed. |
| Consequently, the requirements specified in the SER, 'Equipment, diverse |
| from the [reactor trip system], is required to initiate the auxiliary |
| feedwater (AFW) system and turbine trip for ATWS events,' would not have |
| been met. Since this condition was discovered [while the unit was] in Hot |
| Shutdown, it is reportable under 10 CFR 50.72(b)(2)(i)." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36194 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 20:54[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 17:02[CDT]|
| NRC NOTIFIED BY: CHRIS VAUGHN |LAST UPDATE DATE: 09/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 30 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM FROM 30% POWER DUE TO A MAIN TURBINE TRIP ON |
| MOISTURE SEPARATOR HIGH LEVEL |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At approximately 1702 [CDT] on 09/17/99 during power ascension activities, |
| Unit 2 automatically scrammed on a main turbine trip. Initial indications |
| are that the turbine trip was initiated as a result of moisture separator |
| high level. An investigation is ongoing into the cause of the moisture |
| separator high level. The scram resulted in a low reactor water level |
| causing an automatic isolation of primary containment isolation system |
| (PCIS) groups 2, 3, 6, and 8 [as expected]. EOI-1 was entered due to low |
| reactor water level. Water level was restored to normal with the reactor |
| feedwater system, and EOI-1 was subsequently exited. No main steam safety |
| relief valves (MSRV) were actuated during this event." |
| |
| "This event is reportable per 10 CFR 50.72(b)(2)(ii) as, 'any event that |
| results in a manual or automatic actuation of any engineered safety feature |
| (ESF).' This event also requires a 30-day written report per 10 CFR |
| 50.73(a)(2)(iv)." |
| |
| The licensee stated that all control rods fully inserted following the |
| automatic reactor scram and that all actuations that did occur were as |
| expected. All systems functioned as required, and there was nothing unusual |
| or not understood. The low water level signal was received when reactor |
| vessel water level decreased to +11". Reactor vessel water level did not go |
| below 0", and the reactor core isolation cooling and high pressure coolant |
| injection systems actuate at -45". There were no emergency core cooling |
| system actuations, and none were required. |
| |
| The recirculation pumps automatically tripped due to the turbine trip with |
| the reactor at approximately 30% |
| power. The licensee was unable to place a recirculation pump back in |
| service prior to exceeding the temperature limitations between the steam |
| dome and bottom head. As a result, the licensee commenced a unit cooldown |
| in order to get back within the required limitation of 145�F. The most |
| recent temperature difference was approximately 200�F. |
| |
| The unit is currently stable in Mode 3 (Hot Shutdown). The control rod |
| drive system is being used to maintain reactor vessel water level. The |
| condensate and feedwater systems are also available. The main steam |
| isolation valves are open, and the main condenser is being used for |
| cooldown. Containment parameters are normal. The containment isolations |
| have since been reset, and the systems have been returned to normal status |
| as appropriate. Offsite power is available, and the emergency diesel |
| generators are operable and available if needed. |
| |
| Prior to this event, power ascension activities were in progress on Unit 2 |
| following a shutdown from the previous day due to problems with the |
| electrohydraulic control system. Unit 1 is currently defueled, and Unit 3 |
| is currently operating at 100% power. Units 1 and 3 were not affected by |
| this event. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36195 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/17/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 22:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/17/1999|
+------------------------------------------------+EVENT TIME: 20:56[CDT]|
| NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 09/18/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |JOHN PELLET R4 |
|10 CFR SECTION: |DAVID MATTHEWS NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |BERNICE CARR FEMA |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 25 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DECLARATION OF AN UNUSUAL EVENT DUE TO A HYDROGEN EXPLOSION WITHIN THE |
| OFFGAS SYSTEM (Refer to event #36192 for additional information.) |
| |
| Earlier today (09/17/99), a loss of the Zulu sump pumps caused both standby |
| gas treatment trains to be inoperable. This in turn resulted in a technical |
| specification required plant shutdown from 100% power due to loss of the |
| standby gas treatment system. (Refer to event #36192 for additional |
| information.) Subsequent inspections and evaluations determined that the |
| plant sustained a hydrogen explosion within the offgas system some time |
| between 0500 CDT and 0700 CDT on 09/17/99. The hydrogen explosion was |
| contained within the system, but the Zulu sump sustained damage at the base |
| of the elevated release point tower. Indications are that the explosion |
| took place mainly in the sump itself, but there may have been a pressure |
| wave that propagated back through the offgas system. The extent of the |
| damage is under investigation. This sump is part of the offgas system and |
| secondary containment. |
| |
| The licensee performed a rapid shutdown and manually scrammed the unit from |
| 25% power at 2040 CDT. The rapid shutdown does not allow the unit to flood |
| up to avoid receipt of a low reactor water level. All rods fully inserted. |
| Low water level was received, and this resulted in actuations of primary |
| containment isolation system groups 2 (emergency core cooling systems and |
| various systems within the reactor building containment), 3 (reactor water |
| cleanup), and 6 (heating and ventilation, primary containment purge and |
| vents, standby gas initiation, etc.). The lowest water level was 0" (narrow |
| range). There were no emergency core cooling system actuations, and none |
| were required. The reactor core isolation cooling and high pressure coolant |
| injection systems are required to actuate at -37". The licensee entered |
| emergency operating procedure charts EOI-1A and EOI-5A for low reactor water |
| level and tripping of the reactor building heating and ventilation (due to a |
| secondary containment pressure spike), respectively. The reactor building |
| (secondary containment) differential pressure went positive and then |
| immediately went negative. This was recovered using the standby gas |
| system. |
| |
| The unit is currently stable in Hot Shutdown, and the licensee plans to |
| place the unit in Cold Shutdown. Normal feedwater and the control rod drive |
| system are being used to supply water to the reactor vessel. The main steam |
| isolation valves are open, and the main condenser is available as a heat |
| sink. Reactor pressure is currently stable, and the bypass valves are |
| closed at this time. Containment parameters are normal. |
| |
| As a result of the explosion within the protected area, the licensee |
| declared an Unusual Event at 2056 CDT on 09/17/99. The Unusual Event |
| termination criteria is to ensure that there is no more hydrogen left in the |
| system via the shutdown of the augmented offgas system and the completion of |
| the required air purge until the length of time (required by procedures) has |
| been doubled. The licensee stated that there is no possibility that another |
| explosion would occur at this time because the system has been purged. The |
| initial problem was the result of a procedural problem that caused a valve |
| to be throttled which backed up hydrogen in the system. That has since been |
| suspended, and the augmented offgas system has been taken off line. |
| |
| The current wind speed of 14.3 mph is coming from 135�. There is no |
| precipitation in the area, and the plume stability class is F. There has |
| been no release of radioactive materials greater than technical |
| specification limits, and there are no protective action recommendations. |
| The licensee stated that the situation is stable. |
| |
| The licensee notified the NRC resident inspector and the state. (Call the |
| NRC operations officer for a site contact telephone number.) |
| |
| *** UPDATE ON 09/18/99 @ 0224 EDT FROM SCHIZAS TO GOULD *** |
| |
| THE PLANT TERMINATED THE UNUSUAL EVENT AT 0107 CDT ON 09/18/99 DUE TO |
| COMPLETION OF ALL VENTING ACTIVITIES IN THE OFFGAS SYSTEM. THERE IS NO |
| POSSIBILITY OF FURTHER EXPLOSIONS DUE TO HYDROGEN GAS CURRENTLY EXISTING. |
| THE PLANT IS STABLE AND COOLING DOWN TO MODE 4. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE R4DO |
| (PELLET), IRO (CONGEL), NRR EO (MATTHEWS), AND FEMA (BELCHER) WERE NOTIFIED |
| BY THE NRC OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36196 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/18/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 10:53[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 09/18/1999|
+------------------------------------------------+EVENT TIME: 08:45[EDT]|
| NRC NOTIFIED BY: HAISLET |LAST UPDATE DATE: 09/18/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 1 Startup |1 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD A PRIMARY CONTAINMENT SYSTEM ISOLATION (PCIS) ACTUATION. |
| |
| WHILE LINING UP THE REACTOR CORE ISOLATION COOLING STEAM SYSTEM FOR STANDBY, |
| THEY RECEIVED A GROUP 5 PCIS ISOLATION. THE ISOLATION WENT TO COMPLETION |
| SUCCESSFULLY. THE CAUSE OF THE ISOLATION IS BEING INVESTIGATED. THE |
| ISOLATION SIGNAL WAS RESET BY 0848 EDT, AND THE STEAM VALVES WERE RESTORED |
| BACK TO NORMAL. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36197 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/18/1999|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 13:29[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/18/1999|
+------------------------------------------------+EVENT TIME: 01:00[CDT]|
| NRC NOTIFIED BY: JOHN SELL |LAST UPDATE DATE: 09/18/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
|NLTR LICENSEE 24 HR REPORT | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RESPONSE TO NRC BULLETIN 80-24 REGARDING LEAKAGE OF SERVICE WATER INTO |
| REACTOR CONTAINMENTS (24-HOUR REPORT) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0100 [CDT] on 09/18/99, a pin hole leak was identified on the 'A' Unit 1 |
| containment fan cooler. The unit had been in a 72-hour [limiting condition |
| for operation (LCO)] for partial blockage of this cooler by zebra mussels. |
| The leak was discovered during treatment for the zebra mussels. The LCO |
| expires at 1035 [CDT] on 09/19/99. The plan is presently to isolate the |
| leaking tube section and restore the cooler as operable but degraded." |
| |
| There was nothing unusual or not understood and all systems functioned as |
| required. The licensee stated that there are four containment fan coolers |
| per unit. The licensee also stated the NRC Bulletin 80-24 has been |
| superceded but that they are still committed to the provisions of this |
| bulletin. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36198 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/19/1999|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 08:15[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/19/1999|
+------------------------------------------------+EVENT TIME: 07:30[EDT]|
| NRC NOTIFIED BY: MYERS |LAST UPDATE DATE: 09/19/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD AN RPS ACTUATION ON A LOW LEVEL STEAM GENERATOR SIGNAL. |
| |
| THE PLANT HAD A REACTOR PROTECTION SIGNAL ACTUATION DUE TO AN ACTUAL LOW |
| LEVEL STEAM GENERATOR TRIP SIGNAL. THE REACTOR WAS ALREADY SHUT DOWN WITH |
| ALL RODS FULLY INSERTED, SO THERE WAS NO AFFECT ON THE REACTOR FROM THIS |
| ACTUATION. THE STEAM GENERATOR LEVEL WAS RESTORED TO ABOVE THE LOW LEVEL |
| TRIP SETPOINT. THE CAUSE OF THE LOW STEAM GENERATOR LEVEL APPEARS TO BE DUE |
| TO INADEQUATE PROCEDURES, BUT THEY ARE STILL INVESTIGATING. |
| |
| THE NRC RESIDENT INSPECTOR ALONG WITH STATE AND LOCAL AGENCIES WERE NOTIFIED |
| BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36199 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 09/19/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 13:24[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/19/1999|
+------------------------------------------------+EVENT TIME: 11:00[EDT]|
| NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 09/19/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO DISCOVERY OF A DEAD SEA TURTLE IN THE INTAKE |
| CANAL |
| |
| At 1100 EDT, the licensee discovered a dead green sea turtle in the plant's |
| intake canal. In accordance with the licensee's marine turtle permit (which |
| is part of the licensee's Environmental Protection Plan), the licensee |
| notified the Department of Environmental Protection's Bureau of Protected |
| Species at 1145 EDT. |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36200 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/19/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 17:13[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/19/1999|
+------------------------------------------------+EVENT TIME: 16:30[EDT]|
| NRC NOTIFIED BY: JOHN MILLER |LAST UPDATE DATE: 09/19/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|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 SAFETY SYSTEM (HIGH PRESSURE COOLANT INJECTION) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1630 on 09/19/99 after the I&C Department was unable to successfully |
| complete a scheduled surveillance activity, the high pressure coolant |
| injection system was declared inoperable. Initial troubleshooting indicates |
| that a card failure has resulted in a sealed-in trip signal. Hope Creek is |
| currently at 100% power with no other systems inoperable. Actions to |
| restore the high pressure coolant injection system to an operable status are |
| underway." |
| |
| The licensee stated that surveillance was being performed on one of the trip |
| signals and that one of the cards that regulates voltage for this trip |
| signal appears to have failed in a semi-energized state. This signal |
| provides just enough of a voltage to keep the trip signal in. As a result, |
| the licensee is in the process of obtaining a replacement card. This event |
| places the unit in a 14-day technical specification limiting condition for |
| operation. |
| |
| The licensee plans to notify the NRC resident inspector and the Lower |
| Alloways Creek Township. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36201 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/20/1999|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 03:59[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/20/1999|
+------------------------------------------------+EVENT TIME: 00:09[EDT]|
| NRC NOTIFIED BY: CHISM |LAST UPDATE DATE: 09/20/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 4 Startup |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED AT 4% POWER. |
| |
| While in mode 2 at approximately 450 psig during unit 2 startup, an |
| automatic group 1 (MSIV's, steam line drain and reactor sample valves) |
| isolation occurred. The main steam line isolation caused reactor pressure to |
| rise. The licensee inserted control rods and stabilized reactor pressure at |
| approximately 950 psig. After verifying that the automatic isolation signal |
| had cleared, the licensee equalized around and reopened the MSIV's in order |
| to restart a reactor feed pump and restore RPV level control. When feed flow |
| was restored, a rapid power rise was observed prompting the licensee to |
| insert a manual reactor scram. All control rods fully inserted as expected, |
| and no ECCS actuation occurred or safety relief valves lifted. The licensee |
| took conservative action to insert a manual scram. |
| |
| The systems affected by the automatic isolations were returned to service. |
| Unit 2 is currently in hot shutdown. The licensee has formed an event |
| investigation team for this event. The cause of the automatic isolation has |
| not been positively determined, but it appears the isolation occurred when |
| the licensee was draining the condenser pressure sensing lines for the |
| pressure transmitters resulting in a Group 1 isolation on low condenser |
| vacuum in accordance with OGP-02, APPROACH TO CRITICALITY AND PRESSURIZATION |
| OF THE REACTOR. |
| |
| The Resident Inspector was notified. |
+------------------------------------------------------------------------------+
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