U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/05/97 - 11/06/97 ** EVENT NUMBERS ** 33187 33213 33214 33215 33216 33217 33218 33219 33220 33221 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/30/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 02:39 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/30/97 | +------------------------------------------------+EVENT TIME: 01:02[EST]| |NRC NOTIFIED BY: GUY GRIFFIS |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR WATER SAMPLE ISOLATION VALVE RECEIVED AUTOMATIC SIGNAL TO CLOSE. | | | | DURING MAINTENANCE ACTIVITY TO MEASURE ACCUMULATOR VALVE ACTUATOR (F013C) | | STROKE, AN IMPROPERLY INSTALLED JUMPER CAUSED A GROUP I ISOLATION SIGNAL | | WHICH CAUSED CONTAINMENT ISOLATION VALVE (1B31-F019), A REACTOR WATER | | SAMPLE VALVE, TO CLOSE. THIS IS A SMALL BORE VALVE OFF THE RECIRC LINE, | | USED FOR REACTOR WATER SAMPLING DURING NORMAL OPERATION, AND WAS THE ONLY | | VALVE IN GROUP I TO BE OPEN. THE JUMPER WAS INSTALLED IN THE WRONG PANEL | | CAUSING THE GROUP I ISOLATION SIGNAL. | | | | TROUBLESHOOTING IS IN PROGRESS, A BLOWN FUSE HAS BEEN FOUND AND FURTHER | | INVESTIGATION IS IN PROGRESS TO INSURE THERE IS NO OTHER PROBLEMS. THE | | PROBLEM WILL BE CORRECTED BEFORE THE PLANT IS RESTARTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1635EST 11/5/97 FROM FRANK GORLEY TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER REVIEWING THE SAFETY PARAMETER | | DISPLAY SYSTEM TAPE WHICH INDICATED THAT VALVE "1B31-F019" WAS ALREADY IN | | THE CLOSED POSITION PRIOR TO THE ISOLATION SIGNAL. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(SHYMLOCK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33213 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: XRI INC. |NOTIFICATION DATE: 11/05/97 | | CITY: BATON ROUGE REGION: 4 |NOTIFICATION TIME: 11:18 [ET]| | COUNTY: STATE: LA |EVENT DATE: 11/05/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 10:23[CST]| | DOCKET: |LAST UPDATE DATE: 11/05/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROSS SCARANO RDO | | |DON COOL (NMSS) EO | +------------------------------------------------+RICH BARRETT (MGR) IRD | |NRC NOTIFIED BY: MIHAEL E. HENRY |FRANK CONGEL (IRD) AEOD | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PATRICIAN LARKINS SEND A FACSIMILE TO THE OPERATION CENTER ABOUT AN EVENT | | NOTIFICATION SHE RECEIVED FROM THE STATE OF LOUISIANA OF A LOST RADIOGRAPHY | | EXPOSURE DEVICE. | | | | | | THE FOLLOWING IS TAKEN FROM THE FACSIMILE SENT TO THE OPERATION FROM US NRC | | OFFICE OF STATE PROGRAMS PAT LARKINS: | | | | THE RADIATION OF PROTECTION DIVISION, LOUISIANA OFFICE OF AIR QUALITY AND | | RADIATION PROTECTION GAVE THE FOLLOWING INFORMATION: | | | | "THE LICENSEE, XRI INC. REPORTED THAT A RADIOGRAPHY EXPOSURE DEVICE | | CONTAINING 103 CURIES OF IRIDIUM-192, FELL OFF A TRUCK WHILE IN ROUTE TO | | EMPIRE, LA. THE DRIVER WAS UNSUCCESSFUL IN HIS ATTEMPTS TO LOCATE THE | | MISSING DEVICE WHICH WAS NOT PROPERLY SECURED. THE STATE IS CURRENTLY IN | | INVESTIGATING AND WILL KEEP NRC INFORMED. | | | | INFORMED LA STAFF TO CALL NRC OPERATIONS CENTER WITH ANY ADDITIONAL | | INFORMATION AS IT IS GATHERED." | | | | * * * UPDATE 1555EST 11/5/97 FROM REGION 4 (SPITZBERG) TO S.SANDIN * * * | | | | LA STATE DEPARTMENT OF TRANSPORTATION PERSONNEL FOUND THE MISSING CAMERA | | INTACT ALONGSIDE THE ROAD. ESTABLISHED CONFERENCE BRIDGE INVOLVING | | R4(SPITZBERG), NMSS(COOL) AND IRD(BARRETT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33214 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/05/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 12:25 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 12:15[EST]| |NRC NOTIFIED BY: DANNY DURHAM |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNAUTHORIZED ENTRY INTO VITAL AREA ON 10/30/97. | | | | UNAUTHORIZED ENTRY INTO VITAL AREA. IMMEDIATE COMPENSATORY MEASURES TAKEN | | UPON DISCOVERY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. REFER TO | | THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33215 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NEW YORK CITY BUREAU OF RAD HEALTH |NOTIFICATION DATE: 11/05/97 | | CITY: NEW YORK CITY REGION: 1 |NOTIFICATION TIME: 13:49 [ET]| | COUNTY: STATE: NY |EVENT DATE: 11/05/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/05/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEANNE HARRISON RDO | | |JOSEY PICCONE EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: DUNCAN WHITE (REGION I) | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NEW YORK CITY NOTIFICATION TO NRC REGION I OFFICE. | | | | "ON NOVEMBER 5, 1997, THE NEW YORK CITY'S BUREAU OF RADIOLOGICAL HEALTH | | (NYC-BRH) INFORMED THE REGION I OFFICE THAT EARLIER IN THE DAY, NEW YORK | | UNIVERSITY (NYU) REPORTED TO BRH THAT A PACKAGE CONTAINING APPROXIMATELY | | 2.7 MILLICURIES OF YTTRIUM 90 (Y-90) WAS ACCIDENTLY LEFT IN A COMMERCIAL | | TAXI CAB BY A UNIVERSITY TECHNICIAN. THE TECHNICIAN WAS TRANSFERRING THE | | LICENSED MATERIAL FROM ONE NYU CAMPUS TO ANOTHER AT THE TIME OF THE | | INCIDENT. Y-90 EMITS BETA RADIATION AND HAS A RADIOACTIVE HALF-LIFE OF 64 | | HOURS. | | | | "NYU IS AN AGREEMENT STATE LICENSEE UNDER THE JURISDICTION OF THE NYC-BRH. | | THE NYC-BRH IS ONE OF FOUR NEW YORK AGENCIES WHICH HAVE JURISDICTION OVER | | BYPRODUCT MATERIAL IN THE STATE OF NEW YORK UNDER SECTION 274 OF THE ATOMIC | | ENERGY ACT. | | | | "NYC-BRH HAS CONTACTED THE POLICE AND COMMERCIAL TAXI COMPANIES IN THE CITY | | IN AN EFFORT TO LOCATE THE MISSING PACKAGE." | | | | * * * UPDATE 1545EST 11/5/97 FROM DUNCAN WHITE (REGION I) TO S.SANDIN * * * | | | | THE SOURCE WAS FOUND INTACT AND RETURNED IN THE EARLY AFTERNOON TO THE | | LICENSEE. NOTIFIED R1DO(HARRISON), EO(COMBS) AND IRD(BARRETT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33216 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:29 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/04/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/05/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MIKE JORDAN RDO | | DOCKET: 0707001 |FRED COMBS EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 NOTIFICATION | | | | "IN A GASEOUS DIFFUSION PROCESS, A BINARY COOLING SYSTEM IS USED. THIS | | BINARY SYSTEM CONSISTS OF TWO COOLING LOOPS. ONE COOLANT LOOP USES A | | REFRIGERANT (R-114) AND THE OTHER USES WATER (WHICH IS REMOTE FROM THE | | UF6). SEE SAR SECTION 3.3.5.5. ON NOVEMBER 4, 1997, OPERATIONS AT PGDP | | WAS REVIEWING A RECENT VIOLATION THAT OCCURRED AT PORTS INVOLVING THE | | ISOLATION OF RECIRCULATING COOLING WATER (RCW) FOR PROCESS GAS COOLERS THAT | | HAVE BEEN SHUTDOWN. IN REVIEWING THIS ISSUE IT WAS DISCOVERED THAT THE | | PGDP NCSA REQUIRED THE RCW TO BE VALVED OFF ONLY FOR CELLS. IN FURTHER | | DISCUSSIONS WITH PLANT NCS PERSONNEL, IT WAS DETERMINED THAT THIS | | REQUIREMENT SHOULD ALSO BE APPLIED TO OTHER PROCESS GAS COOLERS (e.g., | | PURGE & EVACUATION COOLERS, A BOOSTER COOLERS, ETC.) SINCE THE NCSA | | REQUIREMENT IS INTENDED TO MINIMIZE THE POSSIBILITY OF GETTING A MODERATOR | | (i.e., RCW) INTO THE PROCESS GAS SYSTEM DUE TO COOLER LEAKS. | | | | "NCSE 3971-01 ADDRESSES ALL OF THE CASCADE PROCESS GAS COOLERS, HOWEVER, | | NCSA 3971-01 REQUIREMENT WAS INADEQUATELY WRITTEN TO ONLY REQUIRE 'WHEN A | | CELL IS SHUTDOWN TO REPAIR A LEAKING R-114 SYSTEM (INTERNAL TO PROCESS GAS | | PIPING), THE RCW SUPPLY SHALL BE VALVED OFF PRIOR TO REMOVING R-114,' AND | | FAILED TO ADDRESS OTHER COOLERS (i.e., P&E AND BOOSTER). | | | | "PROCESS GAS COOLERS ABOVE 1 WT.%235U KNOWN TO HAVE LEAKS TO THE PROCESS | | STREAM HAVE BEEN IDENTIFIED. EACH COOLER WAS FOUND TO HAVE THE RCW VALVED | | OFF OR THE R-114 SYSTEM WAS CUT AND CAPPED (i.e., ISOLATED). | | | | "THIS EVENT IS REPORTABLE PER PROCEDURE UE2-RA-RE1030, APPENDIX D, CRITERIA | | A.4.b." | | | | "SAFETY SIGNIFICANCE: THE OPERATION OF THE CASCADE IS A SINGLE CONTINGENT | | OPERATION PER SAR SECTION 5.2.2.3. MODERATION IS THE CRITICALITY SAFETY | | PARAMETER BEING CONTROLLED. ONE METHOD OF MODERATION CONTROL INVOLVES | | PREVENTING RCW FROM ENTERING THE PROCESS GAS SYSTEM. FOR THE CONDITION | | WHEN THE R-114 SYSTEM IS LEAKING TO THE PROCESS, THE INTEGRITY OF THE | | CONDENSER TUBES IS THE PRIMARY BARRIER FOR ENSURING THAT THE RCW DOES NOT | | ENTER THE PROCESS GAS SYSTEM. THE CONTROL TO VALVE OFF THE RCW BEING | | FORCED THROUGH THE R-114 LEAK IS INTENDED TO FURTHER REDUCE THE LIKELIHOOD | | OF RCW BEING FORCED THROUGH THE R-114 TUBES (i.e., IN THE EVENT OF A | | CONDENSER TUBE FAILURE) INTO THE PROCESS GAS PIPING. THE FAILURE TO | | REQUIRE THE RCW TO BE VALVED OFF FOR ALL PROCESS GAS COOLERS DID NOT RESULT | | IN THE LOSS OF THE PRIMARY BARRIER (i.e., CONDENSER TUBE INTEGRITY)." | | | | "POTENTIAL CRITICAL PATHWAYS: THERE ARE MANY FACTORS WHICH MAKE THE | | PROBABILITY OF A CRITICALITY EXTREMELY SMALL. EVEN IF A MODERATOR ENTERS A | | SYSTEM THAT HAS BEEN SHUTDOWN, A LARGE MASS OF URANIUM WOULD HAVE TO BE | | PRESENT BEFORE A CRITICALITY COULD BE POSSIBLE. SINCE UF6 IS REMOVED FROM | | A SYSTEM SHUTDOWN TO REPAIR A R-114 LEAK, THE URANIUM WOULD HAVE TO BE IN | | THE FORM OF A DEPOSIT. THE CASCADE IS DESIGNED AND OPERATED WITH THE | | INTENT TO PREVENT THE FORMATION OF DEPOSITS. BECAUSE OF THE DESIGN OF THE | | PROCESS GAS COOLERS, A LARGE DEPOSIT SHOULD BE INDICATED BY THE INABILITY | | OF THE COOLER TO PERFORM ITS FUNCTION. IN THE EVENT AN UNSAFE MASS IS | | PRESENT, THE CASCADE WET AIR INLEAKAGE TSR 2.4.4.4 REQUIRES THE RCW TO BE | | DRAINED FROM THE PROCESS GAS COOLER SYSTEMS THAT DO NOT HAVE A FLUORINATING | | ENVIRONMENT AND CANNOT MAINTAIN THE R-114 PRESSURE ABOVE THE RCW PRESSURE. | | THEREFORE, HAD THE LARGE MASS OF URANIUM REQUIRED FOR A CRITICALITY BEEN | | IDENTIFIED, THE RCW WOULD HAVE BEEN REMOVED IN COMPLIANCE WITH TSR 2.4.4.4. | | | | IN SUMMARY, THE FOLLOWING SEQUENCE OF EVENTS WOULD HAVE TO OCCUR BEFORE A | | CRITICALITY WOULD HAVE BEEN POSSIBLE: | | | | 1. A R-114 LEAK OCCURS IN A PROCESS GAS COOLER. | | 2. THE SYSTEM IS SHUTDOWN, THE R-114 IS REMOVED, AND EITHER THE UF6 IS NOT | | REMOVED OR AN UNSAFE DEPOSIT EXISTS IN THE SYSTEM. | | 3. IF AN UNSAFE DEPOSIT EXIST, THE TSR 2.4.4.4 WOULD HAVE TO BE VIOLATED. | | 4. THEN A LEAK MUST OCCUR IN THE TUBES LOCATED IN THE CONDENSER. | | 5. THE RCW WOULD HAVE TO CROSS BOTH BOUNDARIES OF THE BINARY SYSTEM AND | | MIX WITH THE UNSAFE MASS OF URANIUM LOCATED IN THE UF6 SYSTEM." | | | | "CONTROLLED PARAMETERS: THE OPERATION OF THE CASCADE IS A SINGLE | | CONTINGENT OPERATION. MODERATION IS THE CRITICALITY SAFETY PARAMETER BEING | | CONTROLLED." | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL: THIS DISCOVERY | | DID NOT INVOLVE THE PRESENCE OF FISSILE MATERIAL." | | | | "NUCLEAR CRITICALITY SAFETY CONTROLS: NCSE 3971-0 ADDRESSES ALL OF THE | | CASCADE PROCESS GAS COOLERS, HOWEVER, NCSA 3971-01 REQUIREMENTS WERE | | INADEQUATELY WRITTEN TO ONLY REQUIRE 'WHEN A CELL IS SHUTDOWN TO REPAIR A | | LEAKING R-114 SYSTEM (INTERNAL TO PROCESS PIPING), THE RCW SUPPLY SHALL BE | | VALVED OFF PRIOR TO REMOVING THE R-114'." | | | | "CORRECTIVE ACTIONS: ON NOVEMBER 4, 1997, ACTIONS WERE INITIATED TO | | IDENTIFY OTHER PROCESS GAS COOLERS ABOVE 1 WT.%235U KNOWN TO HAVE LEAKS TO | | THE PROCESS GAS SYSTEM. EACH COOLERS ASSOCIATED CONDENSER WAS FOUND TO | | HAVE THE RCW VALVED OFF OR THE R-114 SYSTEM WAS CUT AND CAPPED (i.e., | | ISOLATED). THEREFORE, THE ACTUAL CONDITIONS OF THESE OTHER PROCESS GAS | | COOLING SYSTEMS WERE FOUND TO COMPLY WITH THE INTENT OF THE NCSA | | REQUIREMENT. ON NOVEMBER 4, 1997, AS A COMPENSATORY MEASURE, LONG TERM | | ORDERS WERE ISSUED REQUIRING COMPLIANCE WITH THE NCSA REQUIREMENTS FOR ALL | | PROCESS GAS COOLERS. THE NCSA IS BEING UPDATED TO CLARIFY THAT THE | | REQUIREMENT APPLIES TO ALL PROCESS GAS COOLER SYSTEMS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33217 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/05/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 16:50[EST]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ATWS BLOCKING SETPOINTS SET NONCONSERVATIVELY | | | | "NORTH ATLANTIC ENERGY SERVICE CORPORATION (NORTH ATLANTIC), THE OPERATOR | | OF SEABROOK STATION, HAS DETERMINED THAT THE EXISTING SETPOINT FOR | | AUTOMATICALLY BLOCKING THE ATWS MITIGATING SYSTEM ACTUATION CIRCUITRY | | (AMSAC) ACTUATION IS NON-CONSERVATIVE, AND THEREFORE CONSTITUTES A | | CONDITION OUTSIDE OF THE DESIGN BASIS OF THE PLANT PURSUANT TO | | 10CFR50.72(b)(1)(ii)(B). | | | | "DURING A REVIEW OF AMSAC DESIGN DOCUMENTS AS A RESULT OF A CONDITION | | PREVIOUSLY REPORTED BY OTHER UTILITIES, NORTH ATLANTIC DETERMINED THAT THE | | AMSAC C-20 INTERLOCK IS SET TO ENABLE AMSAC AT 40 PERCENT TURBINE POWER | | RATHER THAN AT 40 PERCENT REACTOR THERMAL POWER AS STATED IN THE NRC AMSAC | | SER. NORTH ATLANTIC DOES NOT HAVE AN ANALYSIS THAT DETERMINES THE EFFECT | | OF VOIDING IN THE REACTOR VESSEL AT 44 PERCENT REACTOR THERMAL POWER, WHICH | | CORRESPONDS TO APPROXIMATELY 40 PERCENT TURBINE POWER. THUS, IT HAS BEEN | | DETERMINED THAT THE EXISTING C-20 INTERLOCK SETPOINT FOR AUTOMATICALLY | | BLOCKING/ENABLING AMSAC ACTUATION IS NON-CONSERVATIVE. THIS CONDITION HAS | | THE EFFECT OF NOT PERMITTING AN AMSAC ACTUATION UNTIL INCREASING ABOVE | | APPROXIMATELY 44 PERCENT REACTOR THERMAL POWER INSTEAD OF THE REQUIRED 40 | | PERCENT REACTOR THERMAL POWER. THIS CONDITION HAS EXISTED SINCE INITIAL | | AMSAC INSTALLATION." | | | | CORRECTIVE ACTIONS INCLUDE PERFORMING AN OPERABILITY DETERMINATION AND | | CALCULATIONS TO DETERMINE NECESSARY SETPOINT ADJUSTMENTS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENTS #33132 AND #33205. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33218 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/05/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 17:05[EST]| |NRC NOTIFIED BY: MICHAEL EMPEY |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED DISCREPANCIES IN AS-BUILT CONFIGURATION OF THE | | DOWNCOMER AFFECTING EXPECTED LOADING OF THE MARK I CONTAINMENT FOLLOWING A | | LOCA. | | | | "DURING THE DEVELOPMENT OF SPECIFICATIONS FOR AN UPCOMING ECCS STRAINER | | REPLACEMENT, DISCREPANCIES WERE FOUND BETWEEN THE PLANT AS-BUILT DATA AND | | THE DATA USED IN THE DEVELOPMENT OF GE MARK I CONTAINMENT LOAD CALCULATIONS | | FOR VY. VY CURRENTLY MAINTAINS CONTAINMENT TORUS LEVELS IN ORDER TO ASSURE | | TORUS VOLUME AND TORUS DIFFERENTIAL PRESSURE ARE 68,000 TO 70,000 CUBIC | | FEET AND > 1.7 PSID, RESPECTIVELY. BASED ON VY CALCULATIONS, DOWNCOMER | | SUBMERGENCE COULD BE .4 FEET GREATER THAN EXPECTED BY TECHNICAL | | SPECIFICATIONS. PLANS ARE BEING FORMULATED TO REVIEW ALL CALCULATIONS | | INVOLVED." | | | | AN OPERABILITY DETERMINATION PERFORMED BY ENGINEERING CONCLUDED THAT THE | | ADDITIONAL LOADING WOULD BE SMALL IN RELATION TO THE CONSERVATISM | | INCORPORATED IN THE MARK I DESIGN MARGIN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:29 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/05/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:15[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/05/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN RDO | | DOCKET: 0707002 |CHARLEY HAUGHNEY EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR NRC BULLETIN 91-01 NOTIFICATION INVOLVING DEFICIENT NUCLEAR | | CRITICALITY SAFETY ANALYSES AFFECTING APPROXIMATELY THIRTY OPERATIONS | | ONSITE. | | | | "ON 11/5/97 AT 1715 HOURS, IT WAS DETERMINED BY NUCLEAR REGULATORY AFFAIRS | | THAT THE USE OF ENGINEERING NOTICES (ENs) TO MODIFY NCSA REQUIREMENTS | | CONSTITUTED A REPORTABLE EVENT, REPORTABLE TO THE NRC VIA A 4 HOUR EVENT | | NOTIFICATION PER NUCLEAR REGULATORY EVENT REPORTING PROCEDURE | | UE2-RA-RE1030, APPENDIX D, CRITERIA A, PARAGRAPH 2c-1. ON 10/15/97, IT WAS | | DISCOVERED THAT ENs WERE USED TO IMPLEMENT NCS REQUIREMENTS WHICH IS IN | | VIOLATION OF APPROVED PLANT PROCEDURES. | | | | "ENs DO NOT PROVIDE THE NECESSARY CRITICALITY SAFETY ANALYSIS THAT IS | | NEEDED TO ESTABLISH NCS CONTROLS. AS A RESULT NUMEROUS FACILITY OPERATIONS | | HAVE BEEN CONDUCTED WITH NCS CONTROL THAT WERE NOT FORMERLY ESTABLISHED IN | | ACCORDANCE WITH CRITICALITY SAFETY ANALYSIS APPROVAL REPORTS. THE AFFECTED | | OPERATIONS IN THESE FACILITIES HAVE BEEN SUSPENDED UNTIL FORMAL NCS | | CONTROLS CAN BE ESTABLISHED. | | | | "THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURE ASSOCIATED WITH THIS EVENT." | | | | THE LICENSEE WILL INFORM THE ONSITE DOE REPRESENTATIVE AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/05/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 21:07 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 18:10[EST]| |NRC NOTIFIED BY: JEFF FOX |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | 65 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT EXPERIENCED A "B" RECIRCULATION PUMP TRIP DURING SURVEILLANCE TESTING. | | | | WHILE PERFORMING AN I&C LOGIC SEQUENCE FUNCTIONAL TEST (LSFT) INVOLVING AN | | RHR "B" EDG INITIATION SURVEILLANCE, THE "B LPCI LOOP SELECTION LOGIC IS | | INITIATED. DURING RESET AND RESTORATION, THE "B" RECIRC PUMP TRIPPED. THE | | LICENSEE BELIEVES THAT THE OPERATOR MAY NOT HAVE BEEN DELIBERATE ENOUGH IN | | RESETTING THE LPCI LOOP SELECTION LOGIC TO ALLOW FOR A FULL RESET. THERE | | IS NO CONTROL BOARD OR ANNUNCIATOR INDICATION AVAILABLE FOR OPERATORS TO | | VERIFY THAT THE AFFECTED RELAYS HAVE BEEN RESET. WHEN THE RHR LPCI LOGIC | | TEST SWITCHES WERE PROCEDURALLY RETURNED TO RESET, THE "B" RECIRC PUMP | | TRIPPED RESULTING IN A POWER REDUCTION FROM 100% TO APPROXIMATELY 65%. | | OPERATORS ENTERED ABNORMAL OPERATING PROCEDURE 2.4.17 TAKING IMMEDIATE AND | | SUBSEQUENT ACTIONS. THE LICENSEE IS PRESENTLY LOWERING POWER IN | | PREPARATION OF RECOVERY OF THE "B" RECIRC PUMP. THE "A" RECIRC PUMP MUST | | BE REDUCED FROM ITS PRESENT 80% TO LESS 35% SPEED PRIOR TO STARTING THE "B" | | RECIRC PUMP. THIS WILL REDUCE REACTOR POWER WHICH IS CURRENTLY 38% TO | | APPROXIMATELY 30% AND IS EXPECTED TO BE COMPLETED WITHIN AN HOUR. THE TRIP | | OF ONE RECIRC PUMP PLACES THE UNIT IN A 24 HOUR LCO AS DESCRIBED IN | | PARAGRAPH E OF THEIR LICENSE. DURING THIS TRANSIENT THE UNIT ENTERED THE | | CAUTION ZONE ON THE POWER-FLOW DIAGRAM. A DEDICATED OPERATOR OBSERVED NO | | POWER-TO-FLOW INSTABILITIES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 11/05/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 21:25 [ET]| |RX TYPE: [3] CE |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 18:12[CST]| |NRC NOTIFIED BY: ARTHUR WEMETT |LAST UPDATE DATE: 11/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF CSP INVENTORY FOLLOWING A SINGLE FAILURE. | | | | "THE COMPONENT COOLING WATER (CCW) MAKEUP PUMPS START WHEN LEVELS IN THE | | CCW SURGE TANK, EMERGENCY DIESEL GENERATOR (EDG) STANDPIPES OR THE CHILLED | | WATER EXPANSION TANKS REACH A PREDETERMINED SETPOINT. ONCE STARTED, THE | | PUMPS CONTINUE TO RUN UNTIL SECURED BY PLANT OPERATORS. A SINGLE FAILURE | | OF ONE OF SEVERAL COMPONENTS COULD RESULT IN A CONTINUOUS DEMAND FOR | | MAKEUP. THE CCW SURGE TANK, EDG STANDPIPES AND THE CHILLED WATER EXPANSION | | TANKS ARE EACH VENTED. SINCE THE CCW MAKEUP PUMPS TAKE SUCTION FROM THE | | CONDENSATE STORAGE POOL (CSP), CONTINUOUS MAKEUP TO ANY OF THESE LOCATIONS | | COULD RESULT IN OVERFLOW AND LOSS OF AVAILABLE INVENTORY. THIS WATER | | INVENTORY IS CREDITED FOR USE IN RESPONSE TO DESIGN BASES ACCIDENTS. | | | | "IT HAS BEEN DETERMINED THAT OPERATOR ACTION WOULD NOT BE REQUIRED ANY | | SOONER THAN 2 HOURS AFTER A POSTULATED EVENT TO SECURE THE FAILED MAKEUP | | PATHWAY(S) AND PRESERVE SAFETY FUNCTION. THE ADMINISTRATIVE CONTROLS TO | | ENSURE THIS ACTION ARE BEING PUT IN PLACE. ADDITION ENGINEERING REVIEW AND | | EVALUATION IS IN PROGRESS." | | | | THE LICENSEE WILL INFORM REGION 4(HARRELL) AND HAS INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+