Event Notification Report for June 29, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/28/1999 - 06/29/1999
** EVENT NUMBERS **
35873 35874 35875 35876 35877 35878
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35873 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/27/1999|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:21[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/27/1999|
+------------------------------------------------+EVENT TIME: 16:55[CDT]|
| NRC NOTIFIED BY: VAUDY HOLLEY |LAST UPDATE DATE: 06/28/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|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 Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| LOSS OF OFFSITE COMMUNICATION SYSTEM - TONE ALERT RADIO |
| |
| After thunderstorms moved through the area of the plant, the licensee |
| discovered that communications with the meteorological tower had been lost |
| and the tone alert radio system was unavailable for greater than 15 minutes, |
| part of the public communication (warning) system. |
| |
| Workers have been called in to investigate and repair the systems that have |
| been lost. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * RETRACTION 1759 6/28/1999 FROM HAWKINS TAKEN BY STRANSKY * * * |
| |
| The licensee has determined that, although the primary power supply was |
| lost, the backup power supply remained available; therefore, the tone alert |
| radio system remained operable. The NRC resident inspector has been informed |
| of this retraction by the licensee. Notified R2DO (Belisle). |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35874 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/28/1999|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 03:55[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/28/1999|
+------------------------------------------------+EVENT TIME: 03:00[EDT]|
| NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 06/28/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|ACCS 50.72(b)(1)(iv) ECCS INJECTION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL |
| |
| The reactor automatically scrammed on low reactor vessel water level because |
| of maintenance activities on the 'B' level keep fill system. Operators |
| venting the keep fill system unintentionally vented the 'B' reference leg |
| because the isolation valve between the two systems is apparently leaking. |
| This venting caused level instruments using the 'B' reference leg to |
| indicate high. The mismatch on level indicators caused the feed system to |
| switch to the 'B' leg (which happened to be the failed system). This |
| resulted in a decrease in feed flow and an actual decrease in reactor vessel |
| water level. |
| |
| The decrease in reactor water level caused a reactor scram and High Pressure |
| Coolant Injection (HPCI) initiation. Reactor Core Isolation Cooling (RCIC) |
| did not initiate because it uses the 'B' reference leg as an input. |
| All control rods fully inserted. The plant is stable in mode 3. Water |
| level has been restored to the normal band and is being maintained by the |
| feed system. The recirculating pumps are operating and no safety relief |
| valves lifted. The lowest indicated level was -45". |
| |
| The licensee notified the NRC resident inspector. |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35875 |
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+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/28/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/28/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:05[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/28/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LICENSEE 24 HOUR REPORT - CRANE STOPPED WHILE MOVING UF6 CYLINDER |
| |
| "On June 28, 1999 at approximately 0105, the X-343 south crane movement |
| stopped completely and would not operate in any direction. The crane failed |
| while a full liquid UF6 cylinder was being removed from autoclave #6. The |
| crane brakes functioned as designed to prevent further movement of the UF6 |
| cylinder. Following failure of the crane, the UF6 cylinder was suspended |
| approximately two feet above the autoclave rollers. The exact cause of the |
| crane movement failure is currently under investigation. The actuation of |
| the crane brake is believed to have been necessary as a result of the |
| opening of the thermal overloads. Pending further investigation of the cause |
| for the brake actuation, the brake actuation is being considered a valid |
| safety system actuation, and reportable in accordance with SAR Table 6.9, |
| Criterion J2. As a precautionary measure, all liquid UF6 handling cranes |
| have been tagged out of service pending the noted investigation. Support |
| cradles have been positioned to support the suspended liquid UF6 cylinder." |
| |
| The NRC resident inspector has been informed of this event. |
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|Other Nuclear Material |Event Number: 35876 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WEST VIRGINIA UNIVERSITY |NOTIFICATION DATE: 06/28/1999|
|LICENSEE: WEST VIRGINIA UNIVERSITY |NOTIFICATION TIME: 16:07[EDT]|
| CITY: MORGANTOWN REGION: 2 |EVENT DATE: 06/25/1999|
| COUNTY: STATE: WV |EVENT TIME: [EDT]|
|LICENSE#: 47-23035-01 AGREEMENT: N |LAST UPDATE DATE: 06/28/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |AL BELISLE R2 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEN DOUGLAS | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MISSING SHIPMENT OF SULFUR-35 |
| |
| The licensee reported that 7 millicuries (mCi) of S-35 was missing from a |
| shipment that arrived from ICN radiochemicals of California on the morning |
| of 6/25/1999. Upon receipt, an individual inspected the package and reported |
| that the shipment was present; however, during the investigation, he |
| admitted that he may not have properly checked it. The loss was discovered |
| when the package was opened in the laboratory, and the researcher discovered |
| that the package contained only dry ice. |
| |
| The licensee has contacted the vendor, who indicated that the package went |
| through a quality assurance inspection before shipment. The licensee's |
| investigation is continuing. |
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|Power Reactor |Event Number: 35877 |
+------------------------------------------------------------------------------+
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| FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/28/1999|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 19:29[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 06/28/1999|
+------------------------------------------------+EVENT TIME: 12:44[PDT]|
| NRC NOTIFIED BY: BRIAN GARDES |LAST UPDATE DATE: 06/28/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC CLOSURE OF MSIVs |
| |
| The licensee reported that the main steam isolation valves (MSIVs) |
| automatically closed due to unknown reasons.; however, surveillance |
| procedure ESP-RPS-X301 (Turbine Throttle Valves Channel Check) was being |
| performed at the time. The unit is currently in Cold Shutdown for a fuel |
| savings dispatch. |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35878 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/28/1999|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 21:43[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/28/1999|
+------------------------------------------------+EVENT TIME: 18:42[EDT]|
| NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 06/28/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE 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 70 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR SCRAM DUE TO LOSS OF CONDENSER VACUUM |
| |
| At 1842 EDT, an automatic turbine trip/reactor scram occurred due to low |
| condenser vacuum after all four circulating water pumps tripped. All control |
| rods inserted following the scram, and the main steam isolation valves |
| (MSIVs) remained open. No safety/relief valves lifted during the event. All |
| systems functioned as expected with primary containment isolation system |
| (PCIS) Group 2 (drywell floor and equipment drains), Group 6 (containment |
| atmosphere cooling) and Group 8 (RHR shutdown cooling) isolations occurring |
| due to low reactor vessel water level following the scram. The scram signal |
| was reset at 1850 EDT. |
| |
| The unit is currently stable in Hot Shutdown. Reactor vessel pressure is |
| being controlled using the main turbine bypass valves. The licensee has |
| restored circulating water system flow to the main condenser. |
| |
| The licensee reported that the circulating water pumps tripped as a result |
| of excessive differential pressure across the intake screens caused by a |
| fish run in the intake canal. Operators had manually reduced power from |
| 100% prior to the event in an attempt to stabilize condenser vacuum. Unit 1 |
| experienced similar increased differential pressure in the circulating water |
| system, but were able to stabilize condenser vacuum after reducing power to |
| 70%. The fish run has subsided, and the licensee is currently returning Unit |
| 1 to 100% or rated power. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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