U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/16/98 - 10/19/98 ** EVENT NUMBERS ** 34628 34731 34736 34776 34916 34922 34923 34924 34925 34926 34927 34928 34929 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34628 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:24 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/10/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:35[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/17/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MIKE UNDERWOOD | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 24 HOUR NRC BULLETIN 91-01, SUPPLEMENT 1 EVENT - | | | | A U-233 SOLUTION HAD BEEN SPILLED IN A SINK IN THE RADIOCHEMISTRY | | LABORATORY (ROOM 57) IN BUILDING C-710. ROOM 57 HAD BEEN DESIGNATED | | AS A FISSILE CONTROL AREA (FCA) IN ACCORDANCE WITH NCSA 1493-19. | | IN ORDER TO CLEAN UP THE RADIOLOGICAL CONTAMINATION PRODUCED BY THE | | SPILL, PLANT PERSONNEL ESTABLISHED A CONTAMINATION AREA AROUND THE SINK. | | THEY SET UP AN 8 GALLON PLASTIC BAG TO COLLECT THE RADIOLOGICAL WASTE | | (URANIUM CONTAMINATED RAGS) GENERATED DURING THE CLEANUP OF THIS SPILL. | | | | HOWEVER, AT 1335 CDT ON 08/10/98, PLANT PERSONNEL DISCOVERED THAT NCSA | | GEN-15 LIMITED THE MAXIMUM VOLUME OF A PLASTIC BAG USED FOR THE COLLECTION | | OF RADIOLOGICAL WASTE IN AN FCA TO BE 5.5 GALLONS. COLLECTING RADIOLOGICAL | | WASTE IN A BAG LARGER THAN 5.5 GALLONS COULD ALLOW THE ACCUMULATION OF AN | | UNSAFE VOLUME OF FISSILE MATERIAL. | | | | THIS CONDITION VIOLATED ONE OF THE DOUBLE CONTINGENCY CONTROLLED PARAMETERS | | (VOLUME CONTROL); THE OTHER PARAMETER (MASS CONTROL) WAS NEVER VIOLATED | | DURING THIS EVENT. PLANT PERSONNEL ESTIMATED THAT LESS THAN 20 MICROGRAMS | | OF U-233 HAD BEEN ACCUMULATED IN THIS BAG. | | | | PLANT PERSONNEL REMOVED THE BAG FROM ROOM 57 AND PROCESSED THE BAG AND | | ITS CONTENTS AS RADIOLOGICAL WASTE. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND ARE REPORTING THIS | | EVENT TO THE NRC IN ACCORDANCE WITH THEIR SAFETY ANALYSIS REPORT, TABLE | | 6.9-1, CRITERIA A.4.a, AS AN NRC BULLETIN 91-01, SUPPLEMENT 1, 24 HOUR | | EVENT. | | | | *** UPDATE ON 10/17/98 @ 0002 BY CAGE TO GOULD *** RETRACTION | | | | FURTHER EVALUATION BY NCS HAS CONCLUDED THAT THE VOLUME CONTROL WAS | | VIOLATED, HOWEVER, NO MATERIAL SUBJECT TO NCS CONTROL UNDER THE APPLICABLE | | WASTE MANAGEMENT NCSE WAS COLLECTED IN THE BAG. THE QUANTITY OF URANIUM | | 233 MAINTAINED IN THE LAB WAS BELOW THE MASS LIMIT ESTABLISHED FOR NCS | | CONTROL OF THE MATERIAL. MATERIAL BELOW THIS LIMIT HAS NO NCS SIGNIFICANCE | | AND IS EXEMPT FROM NCS CONTROL FOR WASTE GENERATION. IN ORDER FOR A | | CRITICALITY EVENT TO BE POSSIBLE, A MASS OF URANIUM 233 ABOVE THE SPECIFIED | | LIMIT WOULD HAVE TO BE AVAILABLE IN THE LAB AND WOULD HAVE TO BE IMPROPERLY | | COLLECTED IN THE BAG. THEREFORE, THE DOUBLE CONTINGENCY PRINCIPLE WAS | | MAINTAINED, MAKING THIS EVENT NOT REPORTABLE. THE LICENSEE IS THEREBY | | RETRACTING THIS EVENT. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | OPERATIONS OFFICER NOTIFIED REG 3 RDO(JORGENSEN) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34731 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/03/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/02/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/16/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |SCOTT MOORE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: K. SISLER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-Hour NRC Bulletin 91-01 Report | | | | Facility personnel discovered that a nuclear criticality safety approval | | (NCSA) requirement was not being maintained in a laboratory storage area | | (Room 232) of the X-710 Laboratory. One poly bottle containing 8 grams of | | U-235 was found in this storage area in an array stored less than 12 inches | | from an inside room corner, thus violating Requirement #6 of | | NCSA_PLANT006.A04. This constitutes a loss of control "A" (reflection) in | | the double contingency matrix for contingency event A.8.2 (reflection). | | Control "B" (spacing) was maintained throughout this event. Control "A" was | | established at 2030 under the direction of a nuclear criticality safety | | (NCS) personnel. | | | | The NRC resident inspector has been informed of this event. | | | | * * * RETRACTION 1629 10/15/98 FROM LARSON TAKEN BY STRANSKY * * * | | | | "ON 10/14/98, NUCLEAR CRITICALITY ENGINEERING HAD DETERMINED THAT THE | | CONTROLLING NCSA FOR THIS EVENT WAS NCSA_PLANT006. THE PREVIOUSLY | | REFERENCED NCSA (NCSA_710.007) DISCUSSED STORAGE ARRAY REQUIREMENTS, NOT | | SINGLE STORAGE RACK REQUIREMENTS. AFTER REVIEWING NCSA_PLANT006 | | REQUIREMENTS AND WHAT WAS REPORTED AND INVESTIGATED IT WAS DETERMINED THAT | | THERE WAS NO VIOLATION OF A DOUBLE CONTINGENCY PRINCIPLE UNDER THIS NCSA. | | THIS EVENT REPORT IS BEING RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | NOTIFIED R3DO (JORGENSEN). | | | | * * * UPDATE AT 0945 ON 10/16/98 BY SISLER TO JOLLIFFE * * * | | | | THIS EVENT IS UNRETRACTED. THE ABOVE RETRACTION RATIONALE IS FOR EVENT | | #34736. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R3DO BRUCE JORGENSEN. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34736 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:56 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/03/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/16/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH WILLIAMSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-Hour NRC Bulletin 91-01 report | | | | Facility personnel discovered that a nuclear criticality safety approval | | (NCSA) requirement was not being maintained in laboratory storage area room | | 120 of the X-710 Laboratory. A container (poly bottle) was found in this | | storage area in a non-secured holder, violating requirement #2 of | | NCSA_0710_077_A00. Requirement #2 states, in part: "storage areas shall | | have securely anchored holders designed to physically maintain the required | | spacing." This condition constitutes a loss of one control ("A" - spacing) | | in the double contingency matrix for contingency event A/B.7.1. Control "B" | | (mass/moderation) was maintained throughout this event. Control "A" was | | immediately established. | | | | The improper anchoring of a single poly bottle holder has a low safety | | significance. The failure of a single poly bottle holder is bounded by | | placing two containers in contact, which was examined in the NCSE. | | | | The NRC resident inspector has been informed of this event. | | | | * * * UPDATE AT 0945 ON 10/16/98 FROM LARSON TO JOLLIFFE * * * | | | | ON 10/14/98, NUCLEAR CRITICALITY ENGINEERING HAD DETERMINED THAT THE | | CONTROLLING NCSA FOR THIS EVENT WAS NCSA-PLANT006. THE PREVIOUSLY | | REFERENCED NCSA (NCSA-710.007) DISCUSSED STORAGE ARRAY REQUIREMENTS, | | NOT SINGLE STORAGE RACK REQUIREMENTS. AFTER REVIEWING NCSA-PLANT006 | | REQUIREMENTS AND WHAT WAS REPORTED AND INVESTIGATED, IT WAS DETERMINED THAT | | THERE WAS NO VIOLATION OF A DOUBLE CONTINGENCY PRINCIPLE UNDER THIS NCSA. | | THEREFORE, THIS EVENT REPORT IS BEING RETRACTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO BRUCE JORGENSEN. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34776 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/15/98 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 14:19 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 09:55[PDT]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 10/16/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THE PROCESS MONITORING SYSTEM DOES NOT MEET THE | | UFSAR DESIGN BASIS. | | | | UFSAR SECTION 11.5, "PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND | | SAMPLING SYSTEMS," SUB SECTION 11.5.1.1, "DESIGN BASES - PROCESS MONITORING | | SYSTEMS," STATES THE SYSTEM WILL: "PROVIDE CONTINUOUS REMOTE INDICATION AND | | RECORDING OF AIRBORNE RADIOACTIVE CONTAMINATION IN THE FORM OF PARTICULATES | | AND IODINES IN AREAS WHERE PERSONNEL NORMALLY HAVE ACCESS." THE EXISTING | | PROCESS MONITORING SYSTEM, HOWEVER, DOES NOT CURRENTLY INCLUDE CONTINUOUS | | PARTICULATE AND IODINE MONITORING TO DETERMINE RADIOACTIVE CONTAMINATION IN | | AREAS WHERE PERSONNEL NORMALLY HAVE ACCESS. | | | | THIS UFSAR REFERENCES REG GUIDE 8.8, "INFORMATION RELEVANT TO ENSURING THAT | | OCCUPATIONAL RADIATION EXPOSURES AT NUCLEAR POWER STATIONS WILL BE AS LOW | | AS IS REASONABLY ACHIEVABLE," AND ONE OF THE "ALARA" PROGRAM OBJECTIVES IN | | THIS REGULATORY GUIDE IS ON RADIATION MONITORING SYSTEMS. | | | | COMPLIANCE WITH THE OCCUPATIONAL EXPOSURE LEVELS IN 10 CFR PART 20 IS | | PERFORMED USING ROUTINE AIRBORNE RADIOACTIVITY SURVEYS AND JOB-SPECIFIC | | AIRBORNE RADIOACTIVITY SAMPLING. THE LICENSEE BELIEVES THIS CONDITION HAS | | NO SAFETY SIGNIFICANCE, AND THE EXISTING PERSONNEL LEVELS ARE WELL BELOW | | NRC REGULATORY LIMITS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * RETRACTION 1958 10/16/98 FROM CLAY WILLIAMS TAKEN BY STRANSKY * * * | | | | "ON SEPTEMBER 15, 1998, AT 1419 EDT, SCE NOTIFIED THE NRC IN ACCORDANCE | | WITH 10CFR50.72(b)(1)(ii)(B) THAT SAN ONOFRE UNITS 2 AND 3 WERE OUTSIDE THE | | DESIGN BASIS OF THE PLANT FOR CONTINUOUS PARTICULATE AND IODINE MONITORING | | TO DETERMINE RADIOACTIVE CONTAMINATION IN AREAS WHERE PERSONNEL NORMALLY | | HAVE ACCESS. AT THE TIME OF THE INITIAL REPORTING, IT APPEARED THAT | | MODIFICATIONS HAD BEEN MADE TO THE PROCESS RADIATION MONITORING SYSTEM THAT | | WERE NOT ACCOMPANIED BY THE REQUISITE CHANGE TO THE FINAL SAFETY ANALYSIS | | REPORT (FSAR) AND WERE NOT APPROPRIATELY CONSIDERED UNDER A 50.59 ANALYSIS. | | | | "DURING SUBSEQUENT INVESTIGATION, THE SAFETY EVALUATION AND A PROPOSED | | CHANGE PACKAGE TO REMOVE THIS DESIGN BASIS FROM THE FSAR WERE IDENTIFIED. | | SINCE APPROPRIATE DOCUMENTATION HAD PREVIOUSLY BEEN PREPARED AS PART OF A | | PROJECT TO REPLACE THE RADIATION MONITORING SYSTEMS, SCE HAS CONCLUDED THAT | | THE ISSUE IS NOT REPORTABLE. ACCORDINGLY, SCE IS WITHDRAWING THE | | NOTIFICATION AND WILL NOT BE SUBMITTING A 30-DAY LICENSEE EVENT REPORT." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. NOTIFIED R4DO | | (JONES). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34916 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 10/14/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 20:49 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 10/14/98 | +------------------------------------------------+EVENT TIME: 15:24[EDT]| |NRC NOTIFIED BY: ART LEWIS |LAST UPDATE DATE: 10/17/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LETDOWN COOLER #1 RUPTURE DISC RUPTURED. | | | | UPON STARTUP OF THE COMPONENT COOLING WATER (CCW) PUMP #2, A CCW LEAK | | RESULTED. THIS PUMP STARTUP CAUSED LETDOWN COOLER #1 RUPTURE DISC TO FAIL | | WHICH CAUSED CCW SURGE TANK LEVEL TO DECREASE. THE CCW SURGE TANK LEVEL | | WAS NOT STOPPED AT THE DIVIDER PLATE OF 33", DUE TO NON-ESSENTIAL VALVES | | CYCLING. THE LEAK HAS BEEN ISOLATED AND SURGE TANK LEVEL RESTORED TO | | NORMAL LEVEL. THIS IS A CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF A SAFETY SYSTEM NEEDED TO SHUTDOWN THE REACTOR AND MAINTAIN | | IT IN A SAFE SHUTDOWN CONDITION. CCW IS USED TO COOL THE RESIDUAL HEAT | | REMOVAL COOLERS WHEN THE PLANT IS IN A SHUTDOWN CONDITION, etc. | | | | DUE TO THE VALVES CYCLING, IT APPEARS THAT THERE MAY HAVE BEEN A | | MAINTENANCE CONDITION THAT COULD HAVE LED TO THE VALVE CYCLING. A FLOW | | SWITCH WAS OUT FOR MAINTENANCE AND THE VALVES CONTINUED TO CYCLE WHICH | | CAUSED BOTH OF THE LOOPS TO FEED THE LEAK (THROUGH THE RUPTURE DISC). CCW | | SURGE TANK LEVEL WENT FROM 50" TO LESS THAN 33". THE LOWEST LEVEL THE CCW | | SURGE TANK LEVEL COULD HAVE GONE TO CANNOT BE DETERMINED BECAUSE THE CCW | | SURGE TANK LEVEL IS JUST A DIGITAL POINT (EITHER IN ALARM OR ABNORMAL). CCW | | SURGE TANK LEVEL IS NOT GIVEN OUT IN AN ANALOG VALUE. | | | | UPDATE: OTSG #1 MSSV #17B7 IS THE ONE THAT STUCK OPEN AND RECLOSED AT A | | PRESSURE OF 920 psig. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | | | | SEE EVENT #34915 FOR BACKGROUND INFORMATION. | | | | * * * RETRACTION 1930 10/17/98 FROM JOHN BALDWIN TAKEN BY STRANSKY * * * | | | | "THE INITIAL NOTIFICATION IDENTIFIED A CONDITION THAT COULD HAVE PREVENTED | | THE COMPONENT COOLING WATER (CCW) SYSTEM FROM PERFORMING ITS SAFETY | | FUNCTION, DUE TO A CYCLING OF NONESSENTIAL VALVES COINCIDENT WITH A CCW | | LEAK. THE LEAK WAS THE RESULT OF A RUPTURE DISC FAILURE IN THE NUMBER 1 | | LETDOWN COOLER WHEN THE NUMBER 2 CCW PUMP WAS STARTED MANUALLY. DURING THE | | EVENT IT WAS IDENTIFIED THAT CCW SURGE TANK LEVEL WAS DECREASING. | | | | "AT THE TIME OF THE INITIAL NOTIFICATION IT WAS UNDERSTOOD THAT THE | | EXISTING PLANT CONDITIONS REPRESENTED A COMMON MODE FAILURE OF THE CCW | | SYSTEM. | | | | "EVALUATION OF THIS EVENT HAS SHOWN THAT LETDOWN COOLER ISOLATION VALVES | | CC1411A AND CC1411B FUNCTIONED AS DESIGNED TO ISOLATE THE NUMBER 1 LETDOWN | | COOLER WITHIN 10 SECONDS ON LOW SURGE TANK LEVEL SWITCH INITIATION TO | | TERMINATE THE LEAK AND MAINTAIN SURGE TANK INVENTORY AND NPSH TO THE CCW | | PUMPS. FURTHER, THE EVALUATION HAS ALSO SHOWN THAT VALVE CYCLING WAS NOT A | | FACTOR. THEREFORE, A LOSS OF SAFETY FUNCTION DID NOT OCCUR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS RETRACTION BY THE | | LICENSEE. NOTIFIED R3DO (JORGENSEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34922 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 10/16/98 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 09:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/15/98 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: GARY HAMILTON |LAST UPDATE DATE: 10/16/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -FIRE WATCH DISCONTINUED BEFORE FIRE DOOR WAS PROPERLY RESTORED TO SERVICE- | | | | AT 1100 ON 10/15/98, THE LICENSEE DISCOVERED THAT TAPE HAD BEEN PLACED OVER | | THE LATCHING MECHANISM OF UNIT 2 LOWER CONTAINMENT AIRLOCK ENCLOSURE FIRE | | DOOR #AX393D. THE LICENSEE IMMEDIATELY DECLARED THE DOOR INOPERABLE AS A | | CONSERVATIVE MEASURE SINCE IT WAS IN AN UNTESTED CONFIGURATION. THE | | LICENSEE REMOVED THE TAPE AND RESTORED THE DOOR TO OPERABLE STATUS. | | | | THE LICENSEE DOES NOT KNOW WHEN THE TAPE WAS PLACED ON THE DOOR LATCH. THEY | | DETERMINED THAT, ON 10/06/98, THE DOOR HAD BEEN PROPPED OPEN FOR REFUELING | | OUTAGE WORK AND AN HOURLY FIRE WATCH HAD BEEN ESTABLISHED IN ACCORDANCE | | WITH THE CATAWBA FIRE PROTECTION PROGRAM. | | | | ON 10/11/98, THE DOOR WAS CLOSED AND THE FIRE WATCH WAS DISCONTINUED. | | HOWEVER, THE TAPE ON THE LATCHING MECHANISM HAD NOT BEEN REMOVED AND THE | | FIRE PROTECTION REQUIREMENT TO PROVIDE A FIRE WATCH ON THIS DOOR HAD NOT | | BEEN MET DURING THE TIME THAT THE DOOR WAS INOPERABLE. | | | | THE CATAWBA FACILITY OPERATING LICENSE REQUIRES THAT ALL PROVISIONS OF THE | | APPROVED FIRE PROTECTION PROGRAM BE IMPLEMENTED AND MAINTAINED IN EFFECT. | | FAILURE TO MAINTAIN A FIRE WATCH ON AN INOPERABLE FIRE DOOR IS A VIOLATION | | OF THE CATAWBA FIRE PROTECTION PROGRAM AND IS REPORTABLE TO THE NRC WITHIN | | 24 HOURS AS REQUIRED BY FACILITY OPERATING LICENSE, CONDITION 2.F. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34923 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ROSEMOUNT NUCLEAR INSTRUMENTS, INC |NOTIFICATION DATE: 10/16/98 | | CITY: EDEN PRAIRIE REGION: 3 |NOTIFICATION TIME: 14:40 [ET]| | COUNTY: STATE: MN |EVENT DATE: 10/16/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 10/16/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE (VIA FAX) NRR | |NRC NOTIFIED BY: JEFFREY W. SCHMITT | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING INCORRECTLY TABULATED INFORMATION REGARDING | | RADIATION PERFORMANCE. | | | | "PURSUANT TO 10CFR PART 21 PARAGRAPH 21.21(b), ROSEMOUNT NUCLEAR | | INSTRUMENTS, INC. (RNII) IS WRITING TO INFORM YOU THAT CERTAIN DATA | | CONTAINED IN THE QUALIFICATION AND TYPE TEST REPORTS FOR ROSEMOUNT MODEL | | 1154 SERIES H ALPHALINE NUCLEAR PRESSURE TRANSMITTER, WHICH WERE USED TO | | SPECIFY THE RADIATION PERFORMANCE IDENTIFIED IN RELEVANT PRODUCT DATA | | SHEETS AND MANUALS, WERE INCORRECTLY TABULATED AND REPORTED. THIS RESULTS | | IN A SMALL CHANGE TO THE 1154 SERIES H NUCLEAR PRESSURE TRANSMITTER | | 30-MINUTE RADIATION ACCURACY SPECIFICATION. ALL OTHER RADIATION AND OTHER | | ACCIDENT LEVEL SPECIFICATIONS ARE UNAFFECTED." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 10/17/98 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 04:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/16/98 | +------------------------------------------------+EVENT TIME: 19:00[CDT]| |NRC NOTIFIED BY: MILLIFF |LAST UPDATE DATE: 10/17/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED A VIOLATION OF TECH SPEC SURVEILLANCE REQUIREMENTS. | | | | DURING 2RE06 (UNIT 2 REFUELING OUTAGE 6), THE LICENSEE DISCOVERED THAT THE | | HOT LEG STRAIGHT LENGTH OF TUBE R02C59 IN STEAM GENERATOR 2B WAS | | INADVERTENTLY NOT INSPECTED BY THE BOBBIN COIL METHOD DURING 2RE05. THE | | RECORDED 2RE05 BOBBIN DATA FOR TUBE R02C59 DOES NOT MATCH EITHER THE | | BASELINE DATA FROM THE PRE-SERVICE INSPECTION, NOR DOES IT MATCH THE DATA | | TAKEN IN 2RE06. THIS INDICATES THAT THE BOBBIN PROBE WAS IN A TUBE OTHER | | THAN R02C59 WHEN THE DATA THOUGHT TO BE FOR TUBE R02C59 WAS TAKEN DURING | | 2RE05. IN 2RE06 THE INSPECTION OF TUBE R02C59 FOUND NO DEFECTS, INDICATING | | THAT HAD THE CORRECT TUBE BEEN INSPECTED AS PLANNED IN 2RE05, NO DEFECTS | | WOULD HAVE BEEN FOUND THEN EITHER. IN 2RE05, THE STEAM GENERATOR | | INSPECTION RESULTED IN A C-3 CONDITION IN ALL GENERATORS, FOR WHICH | | TECHNICAL SPECIFICATIONS REQUIRE A 100% INSPECTION OF THE TUBES IN SERVICE. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34925 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 10/17/98 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 04:31 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 10/17/98 | +------------------------------------------------+EVENT TIME: 02:10[EDT]| |NRC NOTIFIED BY: COATES |LAST UPDATE DATE: 10/17/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 75% POWER DUE TO A TURBINE TRIP. | | | | WHILE CONDUCTING A POWER RANGE NUCLEAR INSTRUMENTATION SURVEILLANCE | | (OST-005), THE CONTROL FUSES BLEW ON NI-44 (THE CAUSE OF THE BLOWN FUSES IS | | UNKNOWN AND BEING INVESTIGATED). AT THIS POINT A TURBINE RUNBACK OCCURRED | | FROM 100% POWER TO APPROXIMATELY 75% POWER. PRESSURIZER PORVS CYCLED OPEN | | AND CLOSED SEVERAL TIMES DURING THE RUNBACK WHEN THE STEAM DUMPS FAILED TO | | OPEN. WHEN OPERATORS MANUALLY OPENED THE STEAM DUMPS, THE STEAM GENERATOR | | LEVELS SWELLED TO THE TURBINE TRIP SETPOINT, CAUSING A TURBINE TRIP/REACTOR | | TRIP TO OCCUR. ALL RODS FULLY INSERTED, NO ECCS INITIATED AND ALL PORVS | | APPEAR TO HAVE FULLY RESEATED. ALL AUXILIARY FEEDWATER PUMPS AUTO STARTED | | FOLLOWING THE TRIP OF BOTH MAIN FEED PUMPS. THE PLANT IS CURRENTLY IN MODE | | 3. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34926 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/18/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:15 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/17/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/18/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE JORGENSEN RDO | | DOCKET: 0707001 |MICHAEL WEBER EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE #1 NORMETEX PUMP IN C-315 TRIPPED WHILE RUNNING ON-STREAM AND EXCEEDED | | SAFETY LIMITS. | | | | ON 10/17/98 AT 1730 CDT, THE C-315 #1 NORMETEX PUMP TRIPPED WHILE RUNNING | | ON-STREAM. A DISCHARGE PRESSURE OF APPROXIMATELY 50 PSIA WAS RECORDED ON | | THE MICROMAX COMPUTER MONITORING/CONTROL SYSTEM. THIS IS GREATER THAN THE | | TSR SAFETY LIMIT, SL2.3.2.1 WHICH IS 45 PSIA. | | | | ON 8/26/98, A TRIP OCCURRED ON THE C-315 #2 NORMETEX PUMP WHICH ALSO | | RESULTED IN A SL EXCEEDANCE AND WAS REPORTED AS EVENT # 34693. COMPENSATORY | | ACTIONS WERE INITIATED WHICH INCLUDED STATIONING AN OPERATOR TO | | CONTINUOUSLY MONITOR THE PLANT'S OPERATING NORMETEX PUMPS SUCTION AND | | DISCHARGE PRESSURES. LIMITS SET FORTH FOR THE C-315 #1 NORMETEX WERE 3.7 | | PSIA MAXIMUM INLET PRESSURE AND 29.5 PSIA MAXIMUM DISCHARGE PRESSURE. THE | | OPERATOR MONITORING THE C-315 #1 NORMETEX PRESSURES ON 10/17/98 REPORTED A | | SUCTION PRESSURE OF 3.5 PSIA AND A DISCHARGE PRESSURE OF 27.5 PSIA. | | | | PRELIMINARY INVESTIGATIONS BY THE SYSTEMS ENGINEER INDICATES THAT A | | SOLENOID THAT PROVIDES AIR TO OPERATE THE PUMP DISCHARGE VALVE HAS FAILED. | | | | THE C-315 #1 NORMETEX PUMP WAS SHUT DOWN AND ISOLATED BY AUTOMATIC ACTIONS | | AND WAS DECLARED INOPERABLE PENDING INVESTIGATION AND A TECHNICAL | | EVALUATION IN COMPLIANCE WITH TSR 1.6.1.2C. THE AUTOMATIC CLOSURE OF THE | | PUMP SUCTION AND DISCHARGE BLOCK VALVES LIMITS THE AMOUNT OF UF6 THAT CAN | | BE RELEASED. THE PUMP, WHEN ISOLATED, DOES NOT CONTAIN SIGNIFICANT AMOUNTS | | OF UF6 AND THERE WAS NO RELEASE. THERE IS NO EVIDENCE OF DAMAGE TO THE | | PUMP OR TO THE DISCHARGE EXPANSION JOINT. | | | | AS A PRECAUTIONARY MEASURE, ALL OPERATING NORMETEX PUMPS WERE PLACED IN | | STANDBY AND THE PLANT ON RECYCLE PENDING FURTHER INVESTIGATION. AT THIS | | TIME, NO SAFETY SYSTEM ACTUATION HAS BEEN IDENTIFIED. HOWEVER, DUE TO THE | | EXCEEDANCE OF THE SAFETY LIMIT, THIS VOLUNTARY NOTIFICATION IS BEING MADE | | TO PROVIDE INFORMATION. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34927 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/18/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 15:34 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/18/98 | +------------------------------------------------+EVENT TIME: 13:42[EDT]| |NRC NOTIFIED BY: BARRY COLEMAN |LAST UPDATE DATE: 10/18/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |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 +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A MANUAL ESF ACTUATION OF A PRIMARY CONTAINMENT | | ISOLATION VALVE (PCIV) WHILE PERFORMING A SURVEILLANCE OF THE REMOTE | | SHUTDOWN PANEL (RSDP). | | | | "WHILE PERFORMING RSDP CHECKS PER THE RCIC VALVE OPERABILITY SURVEILLANCE | | PROCEDURE, THE 'A' RHR PUMP TRIPPED. THIS WAS A LOSS OF SDC THAT OCCURRED | | AT 1342EDT AND IT WAS RETURNED TO SERVICE AT 1349EDT. | | | | "THE PUMP TRIPPED FROM THE SDC SUCTION ISOLATION VALVE NOT BEING FULL OPEN | | (2E11-F009). THE 2E11-F009 [VALVE] WAS PARTIALLY CLOSED (APPROXIMATELY 3 | | SECONDS) WHEN THE EMERGENCY TRANSFER SWITCH AT THE RSDP FOR 2E51-F007, RCIC | | ISOLATION VALVE, WAS PLACED IN [THE] EMERGENCY POSITION. THIS ONE | | EMERGENCY TRANSFER SWITCH SHIFTS CONTROL TO THE RSDP FROM THE CONTROL ROOM | | FOR BOTH 2E51-F007 AND 2E11-F009. | | | | "THIS WAS CONSIDERED A MANUAL ESF ACTUATION OF [A] PCIV." | | | | THE LICENSEE ATTRIBUTES THIS INADVERTENT MANUAL ESF ACTUATION TO AN | | INADEQUATE PRECAUTIONARY STEP IN THE SURVEILLANCE PROCEDURE. DURING THE | | SEVEN MINUTES THAT SHUTDOWN COOLING (SDC) WAS LOST, THERE WAS NO NOTICEABLE | | INCREASE IN REACTOR COOLANT SYSTEM (RCS) TEMPERATURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34928 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/18/98 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 15:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/98 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: M. D. GWIRTZ |LAST UPDATE DATE: 10/18/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A MAJOR LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO | | AN UNRECOVERABLE FAULT ON A MICROPROCESSOR BASED ANNUNCIATOR SYSTEM. | | | | "THE UNIT 2 AUXILIARY ANNUNCIATOR SYSTEM HAS BEEN LOST FOR 24 HOURS. THIS | | SYSTEM MONITORS VARIOUS PLANT ALARMS SUCH AS VALVE POSITIONS AND BUS | | VOLTAGES. ONE DIRECT TECH SPEC PARAMETER IS MONITORED VIA THIS SYSTEM; | | AXIAL FLUX DIFFERENCE. HOURLY ADDITIONAL READINGS ARE IN PLACE TO | | COMPENSATE PER THE TECH SPEC SURVEILLANCE REQUIREMENT. WORK IS IN PROGRESS | | TO RESTORE THE SYSTEM TO A FUNCTIONAL STATUS. ADDITIONAL COMPENSATORY | | ACTIONS ARE BEING PUT INTO PLACE TO MONITOR KEY ALARMS LOST." | | | | THE LICENSEE NOTED THAT WHAT APPEARS TO BE A GROUNDING LINE FAULT HAS | | CAUSED CHASSIS VOLTAGE TO FLUCTUATE. A TROUBLESHOOTING TEAM WILL WORK ON | | THIS PROBLEM THROUGH THE WEEKEND. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34929 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 10/19/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 00:01 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 10/18/98 | +------------------------------------------------+EVENT TIME: 21:52[EDT]| |NRC NOTIFIED BY: BALDWIN |LAST UPDATE DATE: 10/19/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 4 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 4% POWER DUE TO AN ANTICIPATORY REACTOR TRIP SYSTEM | | (ARTS) SIGNAL. | | | | WHILE PERFORMING A STARTUP FOLLOWING A SHORT OUTAGE, A REACTOR TRIP | | OCCURRED WHILE PLACING THE ARTS CHANNEL 1 BYPASS SWITCH TO NORMAL. THIS | | WAS BEING CONDUCTED IN ACCORDANCE WITH THE PLANT STARTUP PROCEDURE. | | HOWEVER, ACCORDING TO THE OPERATOR, THE BYPASS SWITCH WAS INADVERTENTLY | | PLACED IN "SPARE" AT ABOUT THE TIME THE REACTOR TRIP OCCURRED. THE TRIP | | WAS APPARENTLY CAUSED BY TRIPS OF ARTS CHANNELS 2, 3, AND 4. ALL CONTROL | | RODS FULLY INSERTED, NO ECCS ACTUATIONS OCCURRED AND NO SAFETY RELIEF | | VALVES LIFTED. | | | | AN INVESTIGATION IS IN PROGRESS AS TO WHY ARTS ACTIVATED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+