U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/21/1998 - 12/22/1998 ** EVENT NUMBERS ** 35027 35087 35092 35154 35181 35182 35183 35184 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35027 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/13/1998| | UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 09:50[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 11/13/1998| +------------------------------------------------+EVENT TIME: 09:15[EST]| | NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 | |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Hot Standby |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Plant shutdown required by Technical Specifications. | | | | At 0915 on 11/12/98, the unit entered Technical Specification (TS) 3.8.1.1, | | due to overheating of an offsite electrical supply bus (the main | | transformer). TS 3.8.1.1 requires that two offsite electrical supplies be | | available. The unit reduced power and subsequently entered Hot Standby at | | 2007 on 11/12/98. The licensee determined that repairs to the main | | transformer could not be completed within the time of the TS Action | | Statement. Due to the inability to restore a second source of offsite | | power, TS 3.8.1.1 requires the unit to be in Cold Shutdown within 30 hours | | (from 0915 on 11/13/98). The licensee stated that the reportability of this | | event was determined after a review of examples contained in NUREG-1022, | | Revision 1, since the unit had been voluntarily placed into Hot Standby. | | The NRC resident inspector has been informed of this event by the licensee. | | | | * * * Retraction on 12/09/98 at 1228 EST by Kilby taken by MacKinnon * * * | | | | North Atlantic has determined that this event was not reportable pursuant to | | 10 CFR 50.72(b)(1)(i)(A). The shutdown was initiated based upon | | conservative action prior to the expiration of the Technical Specification | | allowed outage time (AOT). The plant was already shutdown (Mode 3, Hot | | Standby) when AOT expired. In accordance with the guidance of NUREG-1022, | | "The initiation of any nuclear plant shutdown does not include mode changes | | required by Technical Specification if initiated after the plant is already | | in a shutdown condition." (NUREG-1022, Rev. 1, pg. 24). Accordingly, this | | event did not involve the initiation of a shutdown required by the Technical | | Specification and the prompt report is hereby retracted. The licensee will | | be submitting an LER on this event. The NRC Resident Inspector was notified | | of this event retraction by the licensee. The NRC Operations Officer | | notified R1DO (Rogge). | | | | * * * Update at 1227 on 12/21/98 by Ron Strickland to Jolliffe * * * | | | | The original event time and date of this event should have been 1900 on | | 11/12/98. The licensee notified the NRC Resident Inspector. The NRC | | Operations Officer notified R1DO John White. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35087 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/30/1998| | UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 09:59[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 11/30/1998| +------------------------------------------------+EVENT TIME: 06:25[EST]| | NRC NOTIFIED BY: GAMBRELL |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 | |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 | |2 N Y 100 Power Operation |100 Power Operation | |3 N N 0 Cold Shutdown |0 Cold Shutdown | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | KEOWEE HYDROELECTRIC UNITS DECLARED INOPERABLE PLACING THE PLANT IN TECH | | SPEC 3.7.7 LCO ACTION STATEMENT. | | | | SHORTLY AFTER START-UP OF BOTH KEOWEE HYDRO UNITS (ONSITE EMERGENCY POWER | | SOURCE FOR THE PLANT) THE UNITS WERE DECLARED INOPERABLE BECAUSE IT WAS | | DETERMINED THAT THE EXISTING CONDITIONS DID NOT MEET ACCEPTABLE LIMITS FOR | | POWER GENERATION. BOTH UNITS WERE SHUT DOWN AT 0629, RETURNING THEM TO | | OPERABLE STATUS, THEREBY EXITING THE LCO. THIS RESULTED IN BOTH TRAINS OF | | ONSITE EMERGENCY POWER BEING INOPERABLE FOR A PERIOD OF 19 MINS, HOWEVER, | | NONE OF THE OCONEE UNITS WERE RECEIVING POWER FROM KEOWEE AND THERE WAS NO | | EFFECT ON THE OCONEE UNITS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | ***************Update at 1315 on 12/21/98, by Douglas taken by | | Weaver********************************************** | | The licensee has retracted this event. | | | | "In this event, it had been determined that shortly after start-up of both | | Keowee Hydro units for commercial power generation, that existing conditions | | did not meet pre-established limits and the Keowee units were shutdown. | | Shutdown restoring the Keowee units to operability. The pre-established | | limits of concern ensure that on a loss of offsite power to Oconee, the | | Keowee units are capable of rejecting commercial loads and connecting to | | required Oconee electrical loads within 23 seconds. | | | | "When Keowee Hydro rejects commercial load, the turbine generators will | | overspeed and cannot be connected to the Oconee loads until they coast down | | to 110% of synchronous speed. To limit the overspeed following rejection of | | commercial loads, limits are placed on the differential head across the | | Keowee turbines. The turbine differential head limits vary with the Lake | | Keowee level and the levels at the turbine tailrace (Keowee River or Lake | | Hartwell at normal elevations) and, to a lesser extent, generator load. | | When the tailrace water level is low, the turbine backpressure (based on | | tailrace elevation) component of differential head cannot be determined | | until the turbines are in operation and loaded. | | | | "The differential head limits for the Keowee units were developed based on | | analyses which were extremely conservative with respect to consideration of | | the infrequent low tailrace levels. This conservatism results from the | | absence of thorough analysis of the impacts of low tailrace water elevation | | and any testing at or near these elevations to validate the analytical | | models. Tailrace water elevations have been essentially those of Lake | | Hartwell since turbine overspeed has been a consideration for Keowee | | operability for commercial power generation. The current levels of Lake | | Hartwell are such that the Keowee tailrace elevation is that of the Keowee | | River. | | | | "Following the November 30, 1998 event, additional analyses were performed | | of the operating condition which existed during the 19 minutes the Keowee | | Hydro units were in commercial operation. These analyses show that Keowee | | Hydro could have rejected commercial loads and automatically connected to | | the Oconee emergency loads within the maximum allowed 23 seconds. | | | | "As a consequence, Duke Energy has concluded that this event does not meet | | the report requirements of 10 CFR 50.72." | | | | The licensee will inform the NRC Resident Inspector of this retraction. The | | HOO notified the R2DO (Frederickson) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35092 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/30/1998| | UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 12:33[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 11/30/1998| +------------------------------------------------+EVENT TIME: 10:55[EST]| | NRC NOTIFIED BY: M. McCLUSKIE |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GLENN MEYER 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 +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE | | | | The licensee determined that the high pressure coolant injection (HPCI) | | inboard isolation valve failed to indicate closed during surveillance | | testing. Due to the indeterminate position of the isolation valve, it was | | declared inoperable and the outboard isolation valve was closed. Technical | | Specification 3.5.e.2 was entered due to HPCI being inoperable, a seven day | | shutdown requirement. | | | | Investigation revealed an open torque switch as the problem. Repairs and | | testing are in progress. | | | | The licensee notified the NRC Resident Inspector and the State of Vermont. | | | | * * * Update at 1345 on 12/21/98 by Mark Magnuson to Jolliffe * * * | | | | Based on Licensee investigation, Operations and System Engineering personnel | | determined that the HPCI System would have performed its full design | | function during this event. Thus, the Licensee desires to retract this | | event. | | | | The Licensee notified the NRC Resident Inspector. | | | | The NRC Operations Officer notified the R1DO John White. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35154 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/16/1998| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 01:38[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 12/15/1998| +------------------------------------------------+EVENT TIME: 22:35[CST]| | NRC NOTIFIED BY: CRAIG JORGENSEN |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 1 Startup |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN FROM <1% POWER DUE TO LACK OF SRM/IRM | | OVERLAP - | | | | THE PLANT WAS IN CONDITION 2 (STARTUP) AT LESS THAN 1% POWER FOLLOWING A | | REFUELING OUTAGE. | | | | STEP 8.2.9.1 OF PROCEDURE 2.1.1 REQUIRES THAT ALL OPERABLE INTERMEDIATE | | RANGE MONITOR (IRM) CHANNELS INDICATE AT LEAST MID SCALE ON RANGE 1 PRIOR TO | | SOURCE RANGE MONITOR (SRM) ROD BLOCK (1E5 CPS) WITH THE SRM DETECTORS FULLY | | INSERTED. THIS RESPONSE COULD NOT BE ACHIEVED, SO PLANT OPERATORS | | TERMINATED THE STARTUP AND ENTERED PROCEDURE 2.1.4, NORMAL SHUTDOWN FROM | | POWER, AT 2235 CST ON 12/15/98. PLANT OPERATORS FULLY INSERTED ALL CONTROL | | RODS AND PLACED THE MODE SWITCH IN THE SHUTDOWN POSITION. | | | | AT 2357 CST ON 12/15/98, THE LICENSEE DETERMINED THIS EVENT TO BE A ONE HOUR | | TECH SPEC REQUIRED PLANT SHUTDOWN REPORTABLE EVENT BASED ON A DISCUSSION | | AMONG LICENSEE OPERATIONS, LICENSING, AND MANAGEMENT PERSONNEL. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). THE LICENSEE IS | | INVESTIGATING THIS SITUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1727 ON 12/21/98 BY JOHN OSWALD TO JOLLIFFE * * * | | | | ON 12/16/98, THE LICENSEE REVISED THE TECH SPEC BASIS AND PROCEDURE 2.1.1 BY | | MEANS OF A 10CFR50.59 EVALUATION TO STATE THAT THE IRM/SRM OVERLAP COULD BE | | VERIFIED BY OBSERVING THAT THE IRMs ARE ON SCALE PRIOR TO WITHDRAWING THE | | SRMs FROM THE FULLY INSERTED POSITION. THE LICENSEE SUCCESSFULLY PERFORMED | | THE REVISED PROCEDURE AND CONTINUED THE PLANT STARTUP. | | | | THE APPLICABLE TECH SPEC REQUIREMENT, SR 3.3.1.1.5, WHICH STATES, "VERIFY | | THE SRM AND IRM CHANNELS OVERLAP" AND THE FREQUENCY, "PRIOR TO WITHDRAWING | | THE SRMs FROM THE FULLY INSERTED POSITION" WERE FULFILLED DURING THIS EVENT. | | A PLANT SHUTDOWN WAS NOT REQUIRED BY TECH SPECS SINCE THE IRMs AND THE SRMs | | WERE OPERABLE. THE SWITCH FROM OPERATING CONDITION 2 TO OPERATING CONDITION | | 4 WAS A VOLUNTARY SHUTDOWN AND AS SUCH IS NOT REPORTABLE TO THE NRC IN | | ACCORDANCE WITH 10CFR50.72(b)(1)(i)(A). THUS, THE LICENSEE DESIRES TO | | RETRACT THIS EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED R4DO BLAIR SPITZBERG. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35181 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TENNESSEE DEPT OF ENVIR & CONSER |NOTIFICATION DATE: 12/21/1998| |LICENSEE: BAPTIST MEMORIAL HOSPITAL |NOTIFICATION TIME: 10:22[EST]| | CITY: MEMPHIS REGION: 2 |EVENT DATE: 12/16/1998| | COUNTY: STATE: TN |EVENT TIME: 12:00[EST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 12/21/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |FRED COMBS EO NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SHULTS (FAX) | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TENNESSEE DEPARTMENT OF ENVIRONMENT AND CONSERVATION INCIDENT REPORT # | | TN-98-203 | | | | ON 12/18/98, THE RADIATION SAFETY OFFICER AT BAPTIST MEMORIAL HOSPITAL, | | MEMPHIS, TN REPORTED A THERAPEUTIC MISADMINISTRATION TO THE STATE. THE | | EVENT OCCURRED ON 12/16/98, WHEN A MAN DUE TO RECEIVE HIS LAST LUNG | | TREATMENT WAS GIVEN A BRAIN TREATMENT INSTEAD. THE TREATMENT WAS 2 | | FRACTIONS OF 150 CENTIGRAYS EACH. THE MAN WAS ASKED IF HE WAS A CERTAIN | | PATIENT, HE SAID YES EVEN THOUGH THE TECHNICIAN HAD STATED A DIFFERENT NAME. | | THE MACHINE USED WAS A VARIAN LINEAR ACCELERATOR, MODEL 1990 CLINAC 2100c. | | | | THIS EVENT DOES NOT POSE A THREAT TO PUBLIC HEALTH AND SAFETY. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35182 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/21/1998| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 18:15[EST]| | RXTYPE: [1] GE-3 |EVENT DATE: 12/21/1998| +------------------------------------------------+EVENT TIME: 17:50[EST]| | NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN WHITE R1 | |10 CFR SECTION: | | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HINGES ON TURBINE BUILDING TORNADO DOOR FOUND BROKEN AND BEING REPAIRED - | | | | WHILE PERFORMING MAINTENANCE ACTIVITIES ON THE TURBINE BUILDING 'B' | | SWITCHGEAR ROOM PERSONNEL DOOR #95, MAINTENANCE TECHNICIANS DISCOVERED THAT | | THE DOOR HINGES WERE BROKEN. THE PLANT TORNADO ANALYSIS REQUIRES THAT THIS | | DOOR BE OPERABLE. | | | | TECH SPEC LCO A/S 3.9.B REQUIRES THE LICENSEE TO RESTORE THE DOOR TO | | OPERABLE STATUS WITHIN 24 HOURS OR TO PLACE THE PLANT IN AT LEAST COLD | | SHUTDOWN CONDITION. THE LICENSEE IS REPAIRING THE DOOR AND EXPECTS TO | | COMPLETE REPAIRS WITHIN 24 HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2225 ON 12/21/98 BY GREG ANDERSON TO JOLLIFFE * * * | | | | AT 2224 ON 12/21/98, THE LICENSEE REPAIRED THE DOOR AND EXITED THE TECH SPEC | | LCO A/S. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R1DO JOHN WHITE. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35183 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 12/21/1998| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 19:16[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 12/21/1998| +------------------------------------------------+EVENT TIME: 16:20[EST]| | NRC NOTIFIED BY: PETE ABBOTT |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN WHITE R1 | |10 CFR SECTION: | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 25 Power Operation |25 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE DUE TO SYSTEM FLOW | | OSCILLATIONS- | | | | WHILE TESTING THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM AT 25% | | POWER, THE LICENSEE OBSERVED SYSTEM FLOW OSCILLATIONS. THE LICENSEE REMOVED | | THE HPCI TURBINE FROM SERVICE TO DETERMINE THE CAUSE AND TAKE CORRECTIVE | | ACTIONS AND DECLARED THE HPCI SYSTEM INOPERABLE. TECH SPEC LCO A/S | | 3.5.C.1.a REQUIRES THE LICENSEE TO RESTORE THE HPCI SYSTEM TO OPERABLE | | STATUS WITHIN 7 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35184 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/21/1998| | UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 22:26[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/21/1998| +------------------------------------------------+EVENT TIME: 08:04[CST]| | NRC NOTIFIED BY: ANDREWS/BANGASSER |LAST UPDATE DATE: 12/21/1998| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN MADERA R3 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 N 0 Cold Shutdown |0 Cold Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | INADEQUATE COMPENSATORY MEASURES TAKEN IN RESPONSE TO SECURITY EVENT. | | IMMEDIATE CORRECT COMPENSATORY MEASURES TAKEN UPON DISCOVERY, REFER TO THE | | HOO LOG FOR ADDITIONAL DETAILS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+