U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/09/97 - 10/10/97 ** EVENT NUMBERS ** 32823 32999 33003 33037 33048 33051 33052 33053 33054 33055 33056 33057 33058 33059 33060 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32823 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF A SAFETY REVIEW TO ADDRESS FINAL SAFETY ANALYSIS ATTRIBUTES ON | | ASSOCIATED COMPONENT COOLING WATER COOLING REQUIREMENTS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING THE ONGOING NRC [ARCHITECT-ENGINEER] DESIGN INSPECTION, A QUESTION | | WAS ASKED RELATIVE TO DUAL TRAIN COMPONENT COOLING WATER (CCW) SYSTEM | | OUTAGES. DURING DUAL TRAIN CCW OUTAGES, CCW COOLING IS SUPPLIED TO THE | | SPENT FUEL POOL (SFP) HEAT EXCHANGER ONLY FROM THE OPPOSITE UNIT. IF THAT | | UNIT HAS A LOSS OF COOLANT ACCIDENT (LOCA), CCW TO THE SFP HEAT EXCHANGER | | WILL ISOLATE. FINAL SAFETY ANALYSIS REPORT (FSAR) TABLE 9.5-2, FOOTNOTE 3, | | INDICATES THAT THE SFP HEAT EXCHANGER IS ASSUMED TO BE ON THE NON-ACCIDENT | | UNIT." | | | | THE LICENSEE REPORTED THE FOLLOWING INSPECTION QUESTIONS: | | | | "1) DOES A DUAL TRAIN CCW OUTAGE REPRESENT A CONDITION OUTSIDE THE PLANT | | DESIGN BASIS?" | | | | "2) WAS THIS REVIEWED AS PART OF THE PROCESS OF ALLOWING A DUAL TRAIN CCW | | OUTAGE?" | | | | "BASED ON A REVIEW OF FSAR TABLE 9.5-2, IT WAS CONCLUDED THAT FOOTNOTE 3 | | WAS ESTABLISHED TO CLARIFY WHY NO VALUES FOR SFP HEAT EXCHANGER FLOW FOR | | THE UNIT UNDERGOING THE LOCA ARE LISTED IN THE TABLE. FOOTNOTE 3 REFLECTS | | NORMAL SFP COOLING SYSTEM DESIGN AND OPERATION." | | | | "A REVIEW WAS PERFORMED OF THE SAFETY EVALUATION PERFORMED FOR THE UNIT 2 | | FULL CORE OFFLOAD WITH ONE TRAIN OF SPENT FUEL COOLING. THIS SAFETY REVIEW | | COVERED THE UNIT 2 REFUELING OUTAGE SCHEDULE WHICH INCLUDED A DUAL TRAIN | | CCW OUTAGE." | | | | "FOOTNOTE 3 OF TABLE 9.5-2 REPRESENTS THE NORMAL DESIGN OF THE SFP COOLING | | SYSTEM, THAT IS, THE SFP COOLING SYSTEM IS DESIGNED TO REMOVE THE HEAT | | GENERATED BY STORED SPENT FUEL ELEMENTS IN THE [SFP]. THE SYSTEM | | INCORPORATES TWO SEPARATE TRAINS." | | | | "THE SAFETY REVIEW FOR THE UNIT 2 FULL CORE OFFLOAD WITH ONE TRAIN OF SPENT | | FUEL COOLING ADDRESSED THE FSAR SECTION 9.4 ATTRIBUTE OF THE SFP COOLING | | DEALING WITH BULK POOL TEMPERATURE REQUIREMENTS; HOWEVER, THE SAFETY REVIEW | | FAILED TO ADDRESS FSAR SECTION 9.5 ATTRIBUTES ASSOCIATED CCW COOLING | | REQUIREMENTS AS GIVEN IN TABLE 9.5-2." | | | | " A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE ACTIONS TO INVESTIGATE | | THIS EVENT AND PROVIDE PREVENTIVE ACTIONS." | | | | THIS ISSUE IMPACTS BOTH UNITS. HOWEVER, THE UNITS ARE NOT CURRENTLY IN A | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS A RESULT OF | | THIS ISSUE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 10/09/97 AT 0800 FROM PTACEK TO GOULD*** | | | | THE LICENSEE HAS DELETED THE WORDS "TIME TO BOIL EVENT AND" FROM THE | | CONCLUSION PARAGRAPH ADDRESSING THE SAFETY REVIEW SINCE ONLY BULK POOL | | TEMPERATURE REQUIREMENTS WERE ADDRESSED IN THE SAFETY REVIEW. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R3DO | | (CLAYTON) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32999 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 09/27/97 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 00:06 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/26/97 | +------------------------------------------------+EVENT TIME: 22:53[CDT]| |NRC NOTIFIED BY: WEIGENENT |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 40 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR WATER LEVEL EXCEEDED MAXIMUM DESIGN LEVEL FOR MAIN STEAM | | LINE BREAK ANALYSIS. | | | | AT 2253 CDT ON 09/26/97, UNIT 2 WAS SHUTTING DOWN DUE TO A PREVIOUS PROBLEM | | WITH CONTAINMENT MAINTENANCE AIRLOCK LEAKAGE. (SEE EVENT #32996.) THE | | STEAM GENERATOR WATER LEVEL EXCEEDED THE MAXIMUM ALLOWED IN THE MAIN STEAM | | LINE BREAK ANALYSIS DUE TO PROBLEMS WITH THE FEEDWATER LEVEL CONTROL | | SYSTEM. THE LICENSEE IS INVESTIGATING THE CAUSE AND DETERMINING CORRECTIVE | | ACTION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE ON 10/09/97 AT 0928 EDT FROM ANDERSON TO GOULD*** | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE FOLLOWING REASON | | WAS TAKEN FROM THE LICENSEE'S FACSIMILE: | | | | "THEY HAVE IMPLEMENTED ADMINISTRATIVE CONTROLS TO PROVIDE MARGIN BETWEEN | | OPERATION AND ASSUMPTIONS IN THE MAIN STEAM LINE BREAK ACCIDENT ANALYSIS. | | SPECIFICALLY, UPPER STEAM GENERATOR NARROW RANGE LEVEL IS CONSERVATIVELY | | LIMITED TO 5% ABOVE [THE] STEAM GENERATOR PROGRAM LEVEL BAND FROM 5% TO 40% | | POWER. THIS LIMIT IS IN PLACE TO PREVENT EXCEEDING CONTAINMENT PRESSURE | | DESIGN LIMITS DURING A MAIN STEAM LINE BREAK. AT OR ABOVE 10% POWER, THE | | HIGH LEVEL STEAM GENERATOR TRIP AT 67% PROVIDES PROTECTION. | | | | THE MAXIMUM NARROW RANGE LEVEL REACHED WAS 57.4% AT A REACTOR POWER OF 39%. | | | | AN OPERATING CURVE FOR STEAM GENERATOR LEVEL HAS BEEN DEVELOPED FOR | | REPORTABILITY BUT HAS NOT YET BEEN IMPLEMENTED INTO OPERATING PROCEDURES. | | REVIEW OF THE SUPPORTING CALCULATIONS FOR THE STEAM GENERATING OPERATING | | CURVE IDENTIFIES THE ACTUAL MAXIMUM ALLOWABLE LEVEL AT 39% POWER AS 67%. | | THEREFORE, OPERATION OF UNIT 2 WITH STEAM GENERATOR LEVEL AT 57.4% NARROW | | RANGE AND 39% POWER WAS NOT OUTSIDE OF THE DESIGN BASIS OF THE PLANT." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R3DO (CLAYTON). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/28/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/28/97 | +------------------------------------------------+EVENT TIME: 08:45[CDT]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION CHILLERS NOT SEISMICALLY MOUNTED. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "WHILE PERFORMING A LEAK CHECK ON THE #0VC13CA DEHYDRATOR, TWO OF THE FOUR | | HOLDDOWN BOLTS WERE FOUND TO BE ERODED. THE DEHYDRATOR WAS ALSO FOUND TO | | BE SITTING ON A PIECE OF WOOD 7 INCHES X 7 INCHES X 1/2 INCH. THE OTHER | | UNIT (#0VC13CB) WAS FOUND TO HAVE A SIMILAR PIECE OF WOOD; HOWEVER, THE | | BOLTS WERE UNABLE TO BE EXAMINED. IDENTICAL PIECES OF WOOD WERE ALSO FOUND | | ON THE DEHYDRATORS FOR THE STATION DRYWELL CHILLERS #1VP04CA AND #1VP04CB. | | | | THIS CONDITION FOR THE CONTROL ROOM VENTILATION CHILLERS IS APPLICABLE TO | | 10CFR50.72(b)(2)(i). THIS IS DUE TO THE PRESENCE OF 'WOOD' SUPPORTING | | COMPONENTS ON THESE CHILLERS NOT BEING SEISMICALLY QUALIFIED. THIS WOULD | | REQUIRE THE UNIT TO BE SHUT DOWN IF IT WERE OPERATING PER CLINTON POWER | | STATION'S IMPROVED TECHNICAL SPECIFICATION 3.7.4, 'CONTROL ROOM AIR | | CONDITIONING SYSTEM.'" | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1530 ON 10/09/97 FROM MIKE HUDSON ENTERED BY JOLLIFFE * * * | | | | LICENSEE ENGINEERING DEPARTMENT PERSONNEL DETERMINED THAT THE WOODEN FRAME | | SUPPORTING THE CHILLER DEHYDRATORS IS PART OF THE ORIGINAL DESIGN AND THAT | | THESE COMPONENTS ARE SEISMOLOGICALLY QUALIFIED IN THIS CONDITION. | | | | IN ADDITION, LICENSEE ENGINEERS ALSO DETERMINED THAT THE ERODED MOUNTING | | BOLTS WERE STILL CAPABLE OF PERFORMING THEIR DESIGN FUNCTION SUCH THAT | | THERE WAS NO IMPACT ON THE SEISMIC QUALIFICATION OF THE CHILLERS. THUS, | | THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED THE R3DO (BRENT CLAYTON). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33037 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/07/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 04:14 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 03:10[CDT]| |NRC NOTIFIED BY: GEORGE TURNER |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | |BLAINE MURRAY, R4 IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST KEYS | | | | COMPENSATORY MEASURES HAVE BEEN FULLY IMPLEMENTED. THE LICENSEE WILL | | NOTIFY THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | | | | * * * UPDATE @ 1225 ON 10/09/97 FROM CARLSON/THOMAS ENTERED BY JOLLIFFE * * | | | | AFTER FURTHER EVALUATION OF THIS EVENT, THE LICENSEE DETERMINED THAT THIS | | EVENT IS A LOGGABLE SECURITY EVENT AND NOT A REPORTABLE SECURITY EVENT AND | | THUS, DESIRES TO RETRACT THIS EVENT. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS OF COMPENSATORY ACTIONS TAKEN.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED THE R4DO (JOHN PELLET) AND R4 IAT (BLAINE MURRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33048 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 16:32[CDT]| |NRC NOTIFIED BY: MARK CARNAHAN |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE DUE TO FAILURE TO TEST LOAD | | SEQUENCE RELAYS. | | | | THE LICENSEE HAS DETERMINED THAT RELAYS IN UNIT 2 THAT BLOCK THE AUTOMATIC | | START OF COMPONENTS WHICH SEQUENCE ONTO THE ESF BUSES DURING UNDERVOLTAGE | | CONDITIONS HAVE NOT BEEN TESTED. AS A RESULT, THE UNIT 2 EMERGENCY DIESEL | | GENERATORS (EDG) HAVE BEEN DECLARED INOPERABLE, INCLUDING THE EDG SHARED | | WITH UNIT 1. THE LICENSEE BELIEVES THAT THIS PROBLEM ALSO EXISTS ON UNIT 1, | | AND HAS ALSO DECLARED THE UNIT 1 EDGs INOPERABLE. DUE TO THE INOPERABILITY | | OF ALL FIVE EDGs; THE SERVICE WATER, COMPONENT COOLING WATER, AND UNIT 2 | | RESIDUAL HEAT REMOVAL SYSTEMS ARE INOPERABLE. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1937 ON 10/09/97 FROM MARK CARNAHAN ENTERED BY JOLLIFFE * * | | | | AT 1741 CDT ON 10/09/97, THE LICENSEE SATISFACTORILY TESTED THE UNIT 2 | | RELAYS AND DECLARED OPERABLE THE UNIT 1 #1B EDG, UNIT 2 #2B EDG, UNIT 1/2 | | #0 SWING EDG, THE ASSOCIATED SERVICE WATER SYSTEM, COMPONENT COOLING WATER | | SYSTEM, AND UNIT 2 #2A RHR SYSTEM TRAIN. THE UNIT 1 #1A EDG AND THE UNIT 2 | | #2A EDG REMAIN INOPERABLE FOR UNRELATED MAINTENANCE ACTIVITIES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R3DO (BRENT CLAYTON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33051 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 05:47 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 04:40[EDT]| |NRC NOTIFIED BY: STETSON |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED A FULL SCRAM SIGNAL WHILE THE UNIT WAS IN CONDITION 5. | | | | DURING THE RESTORATION FROM A SAFETY TAGOUT ON THE CONTROL ROD DRIVE | | HYDRAULIC SYSTEM, A FULL REACTOR SCRAM SIGNAL WAS RECEIVED. THE VALVES FOR | | THE HYDRAULIC SYSTEM WERE RESTORED PRIOR TO THE AIR AND THE CONTROL POWER | | RESULTING IN LEAKAGE PAST THE CONTROL ROD DRIVE SEALS FILLING THE SCRAM | | DISCHARGE VOLUME. THE TIME BETWEEN THE "INSTRUMENT VOLUME NOT DRAINED" | | ALARM TO THE RECEIPT OF THE FULL SCRAM WAS SEVEN MINUTES. NO CONTROL ROD | | MOTION OCCURRED, AND ALL RODS WERE FULLY INSERTED. ALL CONTROL ROD DRIVES | | ARE ISOLATED, AND THE ACCUMULATORS ARE DEPRESSURIZED. THE SCRAM AIR HEADER | | WAS ALSO DEPRESSURIZED PRIOR TO THE EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33052 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 09:15 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 07:50[CDT]| |NRC NOTIFIED BY: ANDREWS |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A PLANT OPERATING CONDITION THAT IS MORE LIMITING THAN THOSE | | SPECIFIED IN THE UPDATED SAFETY ANALYSIS REPORT (USAR) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AS PART OF THE USAR REVIEW AND UPDATE PROJECT, THE PLANT ENGINEERING STAFF | | IDENTIFIED A TRANSIENT SCENARIO WHICH COULD POTENTIALLY PLACE THE PLANT IN | | AN UNANALYZED CONDITION. THE CURRENT [CHEMICAL VOLUME CONTROL SYSTEM] | | MALFUNCTION ANALYSIS IN USAR, SECTION 14, EVALUATES THE EFFECTS FROM AN | | INADVERTENT BORON DILUTION IN REFUELING, START-UP, AND POWER (MANUAL AND | | AUTOMATIC ROD CONTROL) OPERATION. THE USAR REVIEW CONCLUDE[D] THAT THE | | PLANT IS WITHIN THE DESIGN BASIS AS DESCRIBED IN THE ANALYSIS FOR THESE | | PLANT CONDITIONS. HOWEVER, PER PLANT TECHNICAL SPECIFICATIONS, OTHER PLANT | | OPERATING CONDITIONS ARE ALLOWED WHICH COULD BE MORE LIMITING FROM A BORON | | ANALYSIS PERSPECTIVE. FOR EXAMPLE, PRELIMINARY CALCULATIONS HAVE BEEN | | PERFORMED WHICH INDICATE THAT WITH A UNIT IN COLD SHUTDOWN AT THE MINIMUM | | BORON CONCENTRATION SPECIFIED BY PLANT PROCEDURES, THE TIME TO LOSS OF | | SHUTDOWN MARGIN WOULD BE LESS THAN THE 24 MINUTES SPECIFIED IN THE USAR FOR | | THE REFUELING CASE. THE PLANT STAFF WILL BE INVOKING ADMINISTRATIVE | | CONTROLS TO ENSURE THAT THE [SAFETY ANALYSIS REPORT] ANALYSIS IS BOUNDING | | PRIOR TO ENTERING THESE CONDITIONS." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33053 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/09/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:16 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/09/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:20[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/09/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY SYSTEM ACTUATIONS INVOLVING STEAM SHUTDOWN TO AUTOCLAVE #4 AND | | AUTOCLAVE #2 IN THE FEED AND TRANSFER BUILDING | | | | THE FOLLOWING TEXT IS A PORTION OF TWO FACSIMILES RECEIVED FROM PORTSMOUTH: | | | | "ON 10/9/97 AT 0120 HOURS, OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN | | ALARM ON AUTOCLAVE #4 IN THE X-343 FACILITY. THE STEAM SHUTDOWN WAS CAUSED | | BY AN ACTUATION OF THE HIGH CONDENSATE ALARM (BOTH 'A' AND 'B' PROBES). | | INVESTIGATION OF THE ALARMS REVEALED THAT THE AUTOCLAVE #4 HIGH CONDENSATE | | ALARM WAS CAUSED BY AN ACTUAL HIGH CONDENSATE CONDITION. THE AUTOCLAVE | | CONDENSATE ALARM IS A 'Q' SAFETY SYSTEM IN THE X-343 FACILITY. THE | | ACTUATION OF THE AUTOCLAVE HIGH CONDENSATE SYSTEM ALARM OCCURRED WHILE THE | | AUTOCLAVE WAS IN OPERATIONAL MODE II (HEATING). THIS EVENT IS REPORTABLE | | TO THE NRC PER EVENT REPORTING PROCEDURE UE2-RA-RE1030, APPENDIX D, SECTION | | J, PARAGRAPH 2 (24-HOUR REPORT). THE X-343 AUTOCLAVE #4 WAS IMMEDIATELY | | SHUTDOWN AND DECLARED INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT. THERE | | WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURES ASSOCIATED WITH THIS 'Q' SYSTEM ALARM ACTUATION." | | | | "ON 10/9/97 AT 0545 HOURS, OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN | | ALARM ON AUTOCLAVE #2 IN THE X-343 FACILITY. THE STEAM SHUTDOWN WAS CAUSED | | BY AN ACTUATION OF THE HIGH CONDENSATE ALARM (BOTH 'A' AND 'B' PROBES). | | INVESTIGATION OF THE ALARMS REVEALED THAT THE AUTOCLAVE #2 HIGH CONDENSATE | | ALARM WAS CAUSED BY AN ACTUAL HIGH CONDENSATE CONDITION. THE AUTOCLAVE | | CONDENSATE ALARM IS A 'Q' SAFETY SYSTEM IN THE X-343 FACILITY. THE | | ACTUATION OF THE AUTOCLAVE HIGH CONDENSATE SYSTEM ALARM OCCURRED WHILE THE | | AUTOCLAVE WAS IN OPERATIONAL MODE II (HEATING). THIS EVENT IS REPORTABLE | | TO THE NRC PER EVENT REPORTING PROCEDURE UE2-RA-RE1030, APPENDIX D, SECTION | | J, PARAGRAPH 2 (24-HOUR REPORT). THE X-343 AUTOCLAVE #2 WAS IMMEDIATELY | | SHUTDOWN AND DECLARED INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT. THERE | | WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURES ASSOCIATED WITH THIS 'Q' SYSTEM ALARM ACTUATION." | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND A DEPARTMENT OF ENERGY | | SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33054 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 13:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 11:45[CDT]| |NRC NOTIFIED BY: MIKE WINTER |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AIR FOUND IN THE SAFETY INJECTION SYSTEM DURING A SURVEILLANCE TEST - | | | | DURING PERFORMANCE OF THE MONTHLY EMERGENCY CORE COOLING SYSTEMS VENTING | | SURVEILLANCE TEST, AIR WAS FOUND IN THE SAFETY INJECTION SYSTEM DISCHARGE | | PIPING. THE SOURCE OF THE AIR IS UNKNOWN. THE LICENSEE IS INVESTIGATING | | THE SOURCE OF THE AIR AND THE OPERABILITY OF THE SAFETY INJECTION SYSTEM. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33060 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - DEAD SEAL DISCOVERED IN THE PLANT SERVICE WATER FOREBAY - | | | | THE LICENSEE IS MAKING A 24-HOUR NOTIFICATION TO THE NRC IN ACCORDANCE WITH | | SECTION 4.1 OF THE ENVIRONMENTAL PROTECTION PLAN, APPENDIX B, OF THE PLANT | | TECHNICAL SPECIFICATIONS DUE TO A DEAD SEAL BEING OBSERVED IN THE PLANT | | SERVICE WATER FOREBAY. | | | | THE LICENSEE NOTIFIED THE NATIONAL MARINE FISHERIES SERVICE IN GLOUCESTER, | | MASSACHUSETTS, IN ACCORDANCE WITH THE MARINE MAMMAL PROTECTION ACT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | NOTE: REFER TO EVENT #33045 FOR A SIMILAR EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33056 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:05 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 14:35[EDT]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DAIRY MILK PAIL FOUND INSIDE SPENT FUEL POOL - | | | | THE PLANT IS DECOMMISSIONED WITH ALL THE FUEL IN THE SPENT FUEL POOL. | | | | THE LICENSEE DISCOVERED A SMALL STAINLESS STEEL DAIRY MILK PAIL (15 INCHES | | HIGH X 15 INCHES TOP DIAMETER X 10 INCHES BOTTOM DIAMETER) WEDGED BETWEEN | | THE 'B' FUEL RACK AND THE SPENT FUEL POOL EAST WALL ON THE FLOOR OF THE | | INSIDE OF THE SPENT FUEL POOL INSIDE CONTAINMENT UNDER 30 FEET OF WATER. | | | | THE FACILITY OPERATING LICENSE PROHIBITS STORAGE OF MATERIAL IN THIS AREA. | | THE LICENSEE PLANS TO REMOVE THE PAIL AND INVESTIGATE THIS CONDITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33057 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 18:10[EDT]| |NRC NOTIFIED BY: JIM LABIS |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON, R3 RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |JIM CREED, R3 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | A PLANT SAFEGUARDS DEGRADATION RELATED TO AN AREA BOUNDARY WAS DISCOVERED. | | IMMEDIATE COMPENSATORY MEASURES BEGAN UPON DISCOVERY BUT WERE NOT FULLY | | IMPLEMENTED AT THE TIME OF THE CALL. THE LICENSEE PLANS TO INFORM THE NRC | | RESIDENT INSPECTOR. (REFER TO THE HOO LOG FOR ADDITIONAL DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 19:54 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 18:00[CDT]| |NRC NOTIFIED BY: JIM LABIS |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 75 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQD PLANT S/D DUE TO 1 INOP CORE SPRAY LOOP AND 1 INOP EDG - | | | | AT 0500 CDT ON 10/09/97, THE LICENSEE DECLARED THE CORE SPRAY SYSTEM, | | LOOP 'B', INOPERABLE FOR PLANNED MAINTENANCE ACTIVITIES WHICH PLACED THE | | PLANT IN A 7-DAY LCO IN ACCORDANCE WITH TECH SPEC 3.5.A.2. | | | | AT 1345 CDT, THE LICENSEE DECLARED THE #2 EDG INOPERABLE DUE TO THE WRONG | | UNLOADER VALVE BEING INSTALLED IN THE ASSOCIATED START AIR COMPRESSOR. TECH | | SPEC LCO A/S 3.5.A.8 REQUIRES THE PLANT TO BE PLACED IN A COLD SHUTDOWN | | CONDITION WITHIN 24 HOURS IF BOTH EDGs ARE NOT OPERABLE WITH ONE CORE SPRAY | | LOOP INOPERABLE. | | | | AT 1800 CDT, THE LICENSEE BEGAN TO SHUT THE PLANT DOWN FROM 100% POWER. | | | | AT 1825 CDT, THE LICENSEE STOPPED THE POWER REDUCTION AT 75% POWER. | | | | AT 1930 CDT, THE LICENSEE REPLACED THE UNLOADER VALVE, SATISFACTORILY | | TESTED THE #2 EDG START AIR COMPRESSOR, DECLARED IT AND THE #2 EDG | | OPERABLE, AND EXITED TECH SPEC LCO A/S 3.5.A.8. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/09/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 23:22 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 23:10[EDT]| |NRC NOTIFIED BY: GREG RUPPERT |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BECKNER, NRR EO | | |STORER FEMA | | |JOE GIITTER AEOD | | |BILL BEECHER PAO | | |DUNCAN DOE | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - ALERT DECLARED DUE TO A FIRE IN #D21 EDG EXHAUST STACK - | | | | WHILE PERFORMING AN OPERABILITY TEST OF THE #D21 EDG WHICH WAS LOADED TO | | THE 4-KV EMERGENCY BUS, FLAMES SHOT OUT OF THE EDG EXHAUST STACK. | | | | AT 2310 ON 10/09/97, THE LICENSEE DECLARED AN ALERT DUE TO EMERGENCY CORE | | COOLING SYSTEM EQUIPMENT BEING INOPERABLE DUE TO A FIRE. | | | | THE LICENSEE STOPPED THE EDG, AND THE FLAMES EXTINGUISHED. THE ONSITE FIRE | | BRIGADE RESPONDED TO THE FIRE. THE FIRE LASTED 10 TO 15 MINUTES. THE | | LICENSEE POSTED A FIRE REFLASH WATCH. THERE WAS NO RELEASE OF RADIATION. | | THE WIND IS BLOWING FROM THE SOUTH AT 3.5 MPH. | | | | THERE WERE NO INJURIES TO PERSONNEL. | | | | UNIT 2 IS STABLE AT 100% POWER. THE OTHER THREE UNIT 1 EDGs ARE OPERABLE. | | OFFSITE POWER IS AVAILABLE AND STABLE. | | | | THE LICENSEE ACTIVATED THE TECHNICAL SUPPORT CENTER. | | | | THE #D21 EDG IS IN A 30-DAY LIMITING CONDITION FOR OPERATION. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR AND ISSUED A PRESS RELEASE. | | | | IN ADDITION TO THE ABOVE NOTIFICATIONS, THE NRC OPERATIONS OFFICER NOTIFIED | | USDA (BICKERTON), EPA (FLETCHER), AND HHS (GRAY). | | | | * * * UPDATE AT 0200 ON 10/10/97 BY JOLLIFFE * * * | | | | AN NRC CONFERENCE CALL WAS CONDUCTED AMONG REGION 1 (ANDERSON, HEHL, | | MILLER, WIGGINS, CHAWAGA, BURRITT, SHEEHAN, AND NICKELSON); RI (PERRY); NRR | | EO (BECKNER); AND AEOD (GIITTER). | | | | ***UPDATE ON 10/10/97 @ 0319 FROM RUPPERT TO GOULD*** | | | | THE ALERT WAS TERMINATED AT 0305 AFTER ELECTRICAL INSPECTIONS HAD BEEN | | SATISFACTORILY COMPLETED. THE FIRE REMAINED EXTINGUISHED, AND NO APPARENT | | DAMAGE TO THE OTHER THREE EDGs WAS DETECTED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED. THE NRR EO (BECKNER), R1DO | | (CONTE), DOE (DUNCAN), FEMA (STORER), EPA (FLETCHER), USDA (), AND HHS () | | WERE NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 22:08[CDT]| |NRC NOTIFIED BY: DRESSER |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT LEAKAGE THROUGH A REACTOR COOLANT SYSTEM | | PRESSURE ISOLATION VALVE EXCEEDED TECHNICAL SPECIFICATION (TS) LIMIT OF ONE | | GPM. | | | | DURING THE PERFORMANCE OF THE MONTHLY EMERGENCY CORE COOLING SYSTEM | | SURVEILLANCE, AIR WAS FOUND IN THE SAFETY INJECTION DISCHARGE PIPING. IT | | WAS DETERMINED THAT THE SOURCE OF THE AIR WAS NITROGEN LEAKING FROM A | | SAFETY INJECTION ACCUMULATOR THROUGH A SAFETY INJECTION COLD LEG CHECK | | VALVE("1SI8819C"). WHEN TESTING WAS COMPLETED, THEY VERIFIED LEAKAGE | | THROUGH THIS REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE HAD EXCEEDED | | THE TS LIMIT OF 1 GPM. THE CALCULATED LEAK RATE WAS 5 GPM, WHICH IS NOT | | LEAKAGE OUT OF THE RCS AT THIS POINT SINCE THE LEAKING CHECK VALVE IS THE | | SECOND VALVE IN SERIES FROM THE RCS. THE FIRST CHECK VALVE DID NOT LEAK. | | THE CALCULATED LEAK RATE WAS BASED ON THE AMOUNT OF WATER THEY WERE LOSING | | FROM THE SI ACCUMULATOR WHEN THEY VENT THE LINE OFF. THE SI ACCUMULATOR | | LINE TAPS IN BETWEEN THE TWO CHECK VALVES. THE PLANT ENTERED AN LCO ACTION | | STATEMENT REQUIRING REPAIR OF THE VALVE TO BE COMPLETE WITHIN 4 HOURS OR | | COMMENCE SHUTDOWN AND BE IN HOT STANDBY WITHIN THE FOLLOWING 6 HOURS. THEY | | STARTED REDUCING POWER AT 2208 AT THE RATE OF 3MW/MIN AND PLAN TO TAKE THE | | PLANT TO MODE 5. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | HOO NOTE: SEE EVENT #33054 | +------------------------------------------------------------------------------+