Event Notification Report for March 4, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/03/1999 - 03/04/1999
** EVENT NUMBERS **
35327 35365 35418 35426 35435 35436 35437 35438
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35327 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 13:57[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 12:03[EST]|
| NRC NOTIFIED BY: FIELDER |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
|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
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 14 DAY LCO DUE TO HPCI BEING DECLARED INOPERABLE. |
| |
| THE HPCI SYSTEM WAS ISOLATED AND DECLARED INOPERABLE DUE TO A SUSPECTED |
| PROBLEM WITH STEAMLINE FLOW SWITCH TRIP SETPOINT. IT WAS DETERMINED THERE |
| WAS A POSSIBILITY THAT THE SETSCREW INTERNAL TO THE BARTON DIFFERENTIAL |
| PRESSURE SWITCH HAD NOT BEEN TIGHTEN AFTER PERFORMANCE OF THE LAST |
| CALIBRATION. THIS CONDITION COULD CAUSE EXCESSIVE DRIFT. |
| |
| A SECOND CONCERN IS THE SWITCH'S RESPONSE DURING A SEISMIC EVENT MAY BE |
| AFFECTED WITH A LOOSE SCREW. HPCI WAS ISOLATED TO MAINTAIN PRIMARY |
| CONTAINMENT INTEGRITY AND A MAINTENANCE REQUEST HAS BEEN SUBMITTED. THIS |
| CONCERN MAY ALSO BE APPLICABLE TO OTHER SAFETY RELATED SYSTEMS AND THEY WILL |
| BE CHECKED TO ENSURE THE SETSCREW IS APPROPRIATELY TIGHTENED. RCIC IS |
| OPERABLE. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| * * * RETRACTED AT 1021 EST ON 3/3/99 BY KEN GRACIA TO FANGIE JONES * * * |
| |
| The licensee has determined that the as-found trip setting for the steamline |
| flow switch was satisfactory. Also, the as-found setting of the steamline |
| flow switch was greater than the indication that occurs when the HPCI |
| turbine is initiated and was greater than the indication that occurs during |
| HPCI turbine operation. The HPCI system was operable before the |
| surveillance and was returned to service within the Technical Specification |
| timeframe for HPCI. The steamline flow switch was replaced because its |
| performance, based on previous calibrations, was degrading. The steamline |
| flow switch was, in fact, operable and therefore, there was no violation of |
| Technical Specifications. |
| |
| The instrument plate screw(s) protrude through the instrument scale because |
| that feature is a calibration convenience only. The seismic qualification |
| of the steamline flow switch was not affected by the screws that did |
| protrude through the scale plate. |
| |
| Therefore, this event notification is retracted as not reportable. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO (Michael Modes). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35365 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/11/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 23:56[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/11/1999|
+------------------------------------------------+EVENT TIME: 22:49[EST]|
| NRC NOTIFIED BY: DAVID JENKINS |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO |
| INABILITY TO ESTABLISH REFERENCE FLOW CONDITIONS. |
| |
| HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO INABILITY TO ESTABLISH REFERENCE |
| FLOW CONDITIONS DURING PERFORMANCE OF THE QUARTERLY OPERABILITY TEST. THESE |
| CONDITIONS ARE NORMALLY ESTABLISHED AT 2,500 REVOLUTIONS/MINUTE AND 4,550 |
| GALLONS/MINUTE. DURING THIS PERFORMANCE OF THE TEST, A FLOW OF 4,450 |
| GALLONS/MINUTE WAS OBTAINED WITH REFERENCE TURBINE SPEED. |
| |
| THE HPCI SYSTEM IS A SINGLE TRAIN EMERGENCY CORE COOLING SYSTEM. |
| ACCORDINGLY, EMERGENCY HIGH PRESSURE INJECTION IS NOT AVAILABLE AT THIS |
| TIME. THE HIGH PRESSURE REACTOR CORE ISOLATION COOLING (RCIC) REMAINS |
| OPERABLE, AND THE AUTOMATIC DEPRESSURIZATION SYSTEM (BACKUP SYSTEM FOR |
| HPCI) ALSO REMAINS OPERABLE. PLANT TECHNICAL SPECIFICATIONS SECTION 3.5 |
| ALLOWS CONTINUED OPERATION FOR 14 DAYS WITH HPCI SYSTEM INOPERABLE. |
| |
| ENGINEERING AND MAINTENANCE PERSONNEL ARE WORKING TO DETERMINE THE CAUSE OF |
| THIS EVENT. ONCE THE CAUSE IS UNDERSTOOD, A CORRECTIVE ACTION PLAN WILL BE |
| DEVELOPED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| * * * RETRACTED AT 1123 EST ON 3/3/99 BY STEVE TABOR TO FANGIE JONES * * * |
| |
| The licensee has determined that the HPCI system was capable of performing |
| its design basis function. The declaration on inoperability was |
| conservative based on initial indications. However, after a calibration |
| check of the flow instrumentation, which indicated the need for calibration, |
| the flow instrument was calibrated. The HPCI flow test was performed again |
| with satisfactory results, showing that no flow degradation had occurred. |
| Thus, this event notification is retracted. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R2DO (Claude Julian). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35418 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 02/27/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 13:37[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 02/27/1999|
+------------------------------------------------+EVENT TIME: 11:39[EST]|
| NRC NOTIFIED BY: DOUGLAS GOMEZ |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY 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 70 Power Operation |70 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTAINMENT VENTILATION ISOLATION DURING I&C WORK ON RADIATION MONITOR |
| |
| "During Instrument and Control (I/C) activities on radiation channel R-12, |
| an unexpected Containment Ventilation Isolation (CVI) occurred. The planning |
| activities for this maintenance recognized the potential of generating a CVI |
| signal and directed the technicians to install a jumper to prevent the |
| actuation. Even with the jumper installed an unexpected CVI occurred when |
| the R-12 drawer was deenergized. The CVI was therefore due to maintenance |
| activities and was not the result of an actual high radiation condition. |
| |
| "No plant system other than the containment ventilation monitoring system |
| was affected by this event. The plant is stable at approximately 70% power |
| with a plant coastdown in progress. |
| |
| "This event is reportable under lOCFR50.72(b)(2)(ii), 'Any condition that |
| results in a manual or automatic actuation an Engineered Safety Feature.'" |
| |
| The NRC resident inspector has been informed of this notification. |
| |
| * * * RETRACTED AT 0905 EST ON 3/3/99 BY KEVIN McLAUGHLIN TO FANGIE JONES * |
| * * |
| |
| The licensee, RG&E, is retracting this event notification. RG&E has |
| confirmed that the Containment Ventilation Isolation (CVI) signal that was |
| generated on 02/27/99 was an invalid actuation and involved only the system |
| equivalent to the reactor building ventilation system. Further evaluation |
| confirmed that the CVI signal was due to a temporary electrical jumper that |
| was connected, but did not make adequate electrical contact with the |
| terminal board. The CVI was not in response to any radiation condition. |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
| |
| The NRC Headquarters Operations Officer notified the R1DO (Michael Modes). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35426 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/01/1999|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 20:18[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/01/1999|
+------------------------------------------------+EVENT TIME: 19:29[EST]|
| NRC NOTIFIED BY: BUTLER |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG 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 N 0 Hot Shutdown |0 Hot Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH MAIN AND BACKUP PROMPT NOTIFICATION SYSTEMS WERE OUT OF SERVICE. |
| |
| THE NOAA WEATHER RADIO SIGNALS WERE NOT BEING RECEIVED AT HATCH FOR |
| APPROXIMATELY 6 MINUTES. IT APPEARS THAT DUE TO A LOOSE WIRE ON THE |
| MICROPHONE, NOAA HAD NOT RECORDED ANYTHING ON THE TAPE THAT IS TRANSMITTED |
| TO THE LICENSEE. THE PROBLEM WAS CORRECTED AT 1935. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| * * * UPDATE 1200 EST 3/3/99 FROM BARRY COLEMAN TO S.SANDIN * * * |
| |
| THE LICENSEE IN RESPONSE TO PUBLIC INQUIRIES REGARDING INADVERTENT RADIO |
| TEST SIGNALS NOTIFIED BOTH STATE AND LOCAL AGENCIES. ALSO, A LOCAL TV |
| STATION CONTACTED THE LICENSEE BASED ON PUBLIC INTEREST. NOTIFIED |
| R2DO(CAUDLE JULIAN). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35435 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/03/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 17:01[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 03/03/1999|
+------------------------------------------------+EVENT TIME: 16:13[EST]|
| NRC NOTIFIED BY: MACKENZIE |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 20% OF THE SIRENS ARE OUT OF SERVICE |
| |
| DUE TO SEVERE WEATHER IN THE AREA OF THE SITE MORE THAN 20% OF THE |
| LICENSEE'S SIRENS ARE INOPERABLE. THE PLANT HAD RECEIVED A SEVERE STORM |
| WARNING WITH HIGH WINDS FROM THE WEATHER SERVICE AT 1400. REPAIR EFFORTS |
| WILL BE INITIATED IMMEDIATELY. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED ALONG WITH STATE AND LOCAL |
| AGENCIES. |
| |
| ***UPDATE ON 3/3/99 @ 2006 BY HOLBROOK TO GOULD *** |
| |
| THE NUMBER OF INOPERABLE SIRENS IS 5 OUT OF 62 WHICH IS WITHIN THE 20% LIMIT |
| AS OF 1813. |
| THE RESIDENT INSPECTOR WILL BE INFORMED. |
| |
| REG 2 RDO(JULIAN) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35436 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: AUTOMATIC SWITCH CO. |NOTIFICATION DATE: 03/03/1999|
|LICENSEE: AUTOMATIC SWITCH CO. |NOTIFICATION TIME: 15:51[EST]|
| CITY: FLORHAM PARK REGION: 1 |EVENT DATE: 03/03/1999|
| COUNTY: STATE: NJ |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 03/03/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL MODES R1 |
| |VERN HODGES NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: YAOUANC(FAX) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC SWITCH CO (ASCO) REPORTED A MANUFACTURING DEFICIENCY . |
| |
| CERTAIN PUMP AND AMPLIFIER ASSEMBLIES USED IN ASCO GENERAL CONTROLS |
| HYDRAMOTOR ACTUATORS COULD HAVE A MANUFACTURING DEFICIENCY WHICH MAY AFFECT |
| THE OPERATION OF THE ACTUATORS. ASCO WAS ALERTED TO THIS PROBLEM UPON |
| EXAMINATION OF A HYDRAMOTOR ACTUATOR, THAT WAS RECENTLY RETURNED TO ASCO |
| FROM NINE MILE POINT 2 AFTER IT HAD FAILED DURING THE POST INSTALLATION |
| TESTING. THIS CONDITION MAY RESULT IN THE FAILURE OF THE ACTUATOR PISTON TO |
| RETRACT WHEN THE HYDRAMOTOR IS POWERED, OR THE ACTUATOR PISTON RETURNING TO |
| THE SPRING EXTENDED POSITION WHILE THE HYDRAMOTOR IS POWERED. THEY ARE |
| CONTINUING THE INVESTIGATION AND WILL PROVIDE A COMPLETE LIST OF POTENTIALLY |
| AFFECTED ACTUATORS, ALONG WITH THEIR PURCHASERS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35437 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 03/03/1999|
| UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 20:31[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/1999|
+------------------------------------------------+EVENT TIME: 15:01[PST]|
| NRC NOTIFIED BY: MAGRUDER |LAST UPDATE DATE: 03/03/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PHIL HARRELL R4 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|AESF 50.72(b)(2)(ii) ESF ACTUATION |JOSEPH GIITTER IRO |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUXILIARY OFFSITE POWER TRIPPED DURING MAINTENANCE WORK DUE TO A PROCEDURAL |
| DISCREPANCY. |
| |
| THE AUXILIARY OFFSITE POWER TRIP RESULTED IN THE AUTO START AND LOADING OF |
| THE 1-2 DIESEL GENERATOR ON A BUS UNDERVOLTAGE SIGNAL. THE OPERATING RHR |
| PUMP TRIPPED, BUT WAS MANUALLY RESTARTED WITHIN 39 SEC, WITHOUT ANY |
| NOTICEABLE TEMPERATURE INCREASE OCCURRING IN THE PRIMARY SYSTEM. THE TRIP |
| OF THE OFFSITE POWER OCCURRED DURING MAIN TURBINE WORK WHICH CAUSED A THRUST |
| BEARING TRIP SIGNAL. THE THRUST BEARING TRIP WAS NOT CUT OUT AT THE TIME, |
| THUS THE INITIATION OF A UNIT TRIP SIGNAL OCCURRED, TRIPPING OFFSITE |
| AUXILIARY POWER. |
| |
| ONE OF THE THREE VITAL BUSES WAS ALIGNED WITH ITS STARTUP FEEDER BREAKER IN |
| THE TEST POSITION FOR PLANNED TESTING. WHEN AUXILIARY POWER TRIPPED, THE |
| BUS COULD THEREFORE NOT TRANSFER TO OFFSITE STARTUP POWER AND THE DIESEL |
| GENERATOR STARTED ON BUS UNDERVOLTAGE. THE RUNNING RHR PUMP WAS SHED FROM |
| THE BUS DURING THE TRANSFER. THE OTHER TWO BUSES SUCCESSFULLY TRANSFERRED |
| TO THE STARTUP POWER SOURCE. |
| |
| THE VITAL BUS ON THE DIESEL WAS TRANSFERRED AT 1549 PST TO THE STARTUP POWER |
| SOURCE AND THE DIESEL WAS SECURED AT 1551 PST. ALL OFFSITE POWER SOURCES |
| WERE RESTORED AT 1800 PST. |
| |
| THE PROCEDURE DISCREPANCY WILL BE CORRECTED. |
| |
| THE RESIDENT INSPECTOR WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35438 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 03/04/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 01:15[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/04/1999|
+------------------------------------------------+EVENT TIME: 00:28[EST]|
| NRC NOTIFIED BY: BILL RUDD |LAST UPDATE DATE: 03/04/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|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
+------------------------------------------------------------------------------+
| IMPROVED TECHNICAL SPECIFICATION REVIEW FOUND SUSPECT SURVEILLANCE |
| |
| The licensee identified a suspect surveillance during a programatic review |
| of Improved Technical Specifications Surveillances. The surveillance |
| involved the timers for the hydrogen skimmer suction isolation valves. The |
| acceptance criteria in the surveillance procedure was higher than allowed by |
| the acceptance criteria of the Updated Final Safety Analysis Report Table |
| 7-15. The licensee entered LCO 3.0.3 due to both trains being out of |
| tolerance. The licensee exited LCO 3.0.3 at 0059 EST after one of the |
| timers was recalibrated and that train was declared operable. |
| |
| The licensee also verified unit 1 hydrogen skimmer suction valve timers were |
| in specification. One of unit 1's valves was out of specification and will |
| be reported as a 30 day written report. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021