U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/29/95 - 03/30/95 ** EVENT NUMBERS ** 28552 28605 28606 28607 28608 28609 28610 28611 28612 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |RESEARCH REACTOR | |EVENT NUMBER: 28552 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON STATE UNIVERSITY |NOTIFICATION DATE: 03/17/95 | | RXTYPE: 1000 KW TRIGA (CONVERSION) |NOTIFICATION TIME: 17:29 [ET]| |COMMENTS: |EVENT DATE: 01/11/95 | | |EVENT TIME: 00:00[PST]| | |LAST UPDATE DATE: 03/29/95 | | CITY: PULLMAN REGION: 4 +-----------------------------+ | COUNTY: WHITMAN STATE: WA |PERSON ORGANIZATION| |LICENSE#: R-76 AGREEMENT: Y |BLAINE MURRAY RDO | | DOCKET: 05000027 | | +------------------------------------------------+ | |NRC NOTIFIED BY: GERALD TRIPARD | | |HQ OPS OFFICER JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE2 20.2202(b)(2) EXCESSIVE RELEASE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING THIS REPORT DUE TO EXCEEDING THE SEWER LIMIT RELEASE | | OF 10 CFR PART 20 APPENDIX B LIMITS. | | | | ON JANUARY 11, THE FACILITY'S LIQUID WASTE TANK WAS SAMPLED, ANALYZED AND | | DISCHARGED TO THE SEWER SYSTEM IN ACCORDANCE WITH PROCEDURES. SINCE THE | | CALCULATED ACTIVITY OF THE TANK CONTENTS WAS 1.65E-7 ęCi/ml WHICH WAS | | GREATER THAN THE 10 CFR 20 LIMIT OF 2.O E-8 ęCi/ml, THE REACTOR TECHNICIAN | | DISCHARGED THE WASTE TANK USING THE EDUCTOR DILUTION SYSTEM. THE EDUCTOR | | SYSTEM GIVES AN AVERAGE DILUTION FACTOR OF 0.25 WHICH WOULD YIELD AN | | AVERAGE DISCHARGE CONCENTRATION OF 4.2 E-8 ęCi/ml, WHICH IS GREATER THAN | | THE 10 CFR PART 20 LIMIT. THE CONCENTRATION ACTIVITY DOES NOT TAKE INTO | | ACCOUNT THE DILUTION FACTOR FROM THE REST OF CAMPUS OR THE CITY OF PULLMAN. | | | | AN OPERATOR THOUGHT BY THROTTLING A VALVE A LARGER DILUTION FACTOR COULD BE | | ACHIEVED. IT WAS DISCOVERED AFTER THE DISCHARGE TO THE SEWER THAT THE | | THROTTLING OF THE VALVE HAD NO AFFECT ON DILUTION. A TOTAL OF 3.69 ęCi AT | | A CONCENTRATION OF 4.2 E-8 ęCi/ml WAS RELEASED TO THE SEWER. | | | | THE LICENSEE DID ANALYZE THE CONTENTS OF THE TANK AT THE TIME OF THE | | DISCHARGE. A GERMANIUM LITHIUM (GeLi) DETECTOR WAS USED AND IT SHOWED NO | | GAMMA PEAKS OR LEVELS ABOVE NORMAL BACKGROUND. AT THE TIME OF THE | | DISCHARGE THE REACTOR SUPERVISOR MADE A NOTE THAT THE ACTIVITY MAY BE DUE | | TO A PURE BETA EMITTER. | | | | THE LICENSEE IS INVESTIGATING THE SOURCE OF THE ACTIVITY AND AT THIS TIME | | DOES NOT SUSPECT THAT THE SOURCE IS FROM THE REACTOR BECAUSE THE GeLi | | DETECTOR RESULTS DID NOT INDICATE THIS. THE LICENSEE SUSPECTS THAT THE | | SOURCE MAY BE CAUSED FROM RADIOACTIVE WASTE THAT IS HANDLED IN A SHED IN | | THE BACK OF THE FACILITY. THE SHED'S DRAIN GOES TO THE LIQUID WASTE TANK. | | | | THE LICENSEE DISCOVERED THAT THE EVENT SHOULD HAVE BEEN REPORTED DURING A | | RECENT RECORDS REVIEW. THE LICENSEE HAS DISCUSSED THIS EVENT WITH THE | | REGION (MURRAY). | | | | * * * UPDATE 1140 3/29/95 FROM TRIPARD TAKEN BY STRANSKY * * * | | | | LICENSEE IS RETRACTING THIS NOTIFICATION. BASED UPON DISCUSSIONS WITH NRC | | (M. MENDONSA), THE LICENSEE HAS DECIDED THAT CREDIT CAN BE TAKEN FOR THE | | TOTAL CAMPUS SEWAGE DISCHARGE OF APPROXIMATELY 1.5 MILLION GALLONS/DAY IN | | DETERMINING THE DILUTION FACTOR. USING THIS DILUTION FACTOR, THE RELEASE | | IS WELL BELOW 10 CFR PART 20 LIMITS. NOTIFIED R4DO (HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28605 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 03:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/28/95 | +------------------------------------------------+EVENT TIME: 12:30[CST]| |NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTACT FOR THE EDG LOAD SEQUENCER WAS NOT PROPERLY TESTED DURING | | SURVEILLANCE TESTING. | | | | THE LICENSEE REPORTED THE FOLLOWING EVENT AS A CONDITION OF THEIR LICENSE. | | THE LICENSEE DETERMINED THAT A FAILURE TO TEST A CONTACT OFF SEQUENCER | | RELAY "K-243" WAS REPORTABLE. DURING THE PERFORMANCE OF THE LOSS OF | | OFF-SITE POWER (LOOP) ESF TEST, A PARTICULAR CONTACT RELAY THAT STARTS | | "VARIOUS COMPONENTS" WAS NOT PROPERLY DOCUMENTED AS BEING CHECKED. THIS | | CONDITION AFFECTS THE SURVEILLANCE TEST PROCEDURE AT BOTH UNITS. | | | | THE LICENSEE HAS NOT DECLARED ANY EQUIPMENT INOPERABLE. A REVIEW ON THE | | COMPUTER SYSTEM OF THE LAST SURVEILLANCE TEST HAS VERIFIED THAT THE | | COMPONENTS FUNCTIONED CORRECTLY. CORRECTIVE ACTIONS WILL ENSURE THE | | PROCEDURE PROPERLY CHECKS AND DOCUMENTS THE TESTING OF THE CONTACT. THE | | LICENSEE WILL BE FOLLOWING UP WITH AN LER. THE LICENSEE WILL INFORM THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28606 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 08:57 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/29/95 | +------------------------------------------------+EVENT TIME: 08:57[EST]| |NRC NOTIFIED BY: MALONE |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |HAASS RVIB | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PUBLIC SERVICE ELECTRIC AND GAS (PSE&G) PROVIDED A PART 21 EVALUATION | | DOCUMENTING A DEFICIENCY IN ANCHOR-DARLING CHECK VALVES DUE TO INCORRECT | | DIMENSIONAL TOLERANCES OF VALVE COMPONENTS. | | | | SPECIFICALLY, THE 12" CORE SPRAY PUMP "B" DISCHARGE CHECK VALVE (1BEV-015) | | FAILED TO CLOSE DURING PERFORMANCE OF A SURVEILLANCE PROCEDURE IN NOVEMBER, | | 1994. INSPECTION OF THE VALVE DETERMINED THAT THE VALVE DISC CONTACTED THE | | BODY IN SUCH A WAY AS TO PINCH THE DISC, CAUSING IT TO STICK IN THE OPEN | | POSITION. THE VALVE DESIGN INCLUDES A BUTT STOP HINGE TO PREVENT THE DISC | | FROM CONTACTING THE VALVE BODY. BASED ON THE INSPECTION, IT WAS DETERMINED | | THAT THE BUTT STOP ON THE HINGE ARM WAS NOT OF SUFFICIENT LENGTH TO CONTACT | | THE VALVE BODY AND PREVENT DISC-TO-BODY CONTACT. TO CORRECT THE | | DEFICIENCY, A NEW BUTT STOP HINGE ARM, HINGE PIN AND DISC WERE INSTALLED, | | AND THE VALVE WAS SUCCESSFULLY RETESTED IN ACCORDANCE WITH THE SURVEILLANCE | | TEST PROCEDURE. | | | | AS A RESULT, PSE&G INITIATED INSPECTIONS OF ANCHOR-DARLING CHECK VALVES | | WITH A SIMILAR HINGE STYLE TO DETERMINE IF A GENERIC DEFICIENCY EXISTS. A | | TOTAL OF 15 ADDITIONAL VALVES MAY BE AFFECTED. PSE&G'S EVALUATION OF THE | | CHECK VALVES HAS DETERMINED THAT THIS ISSUE IS NOT CONSIDERED AN IMMEDIATE | | OPERABILITY CONCERN FOR SEVERAL REASONS. THE PART 21 SUBMITTAL PROVIDES | | ADDITIONAL DETAILS REGARDING THE ADDITIONAL INSPECTIONS, OPERABILITY | | EVALUATIONS, AND VERIFICATION OF CONTINUED OPERABILITY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28607 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 10:21 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/29/95 | +------------------------------------------------+EVENT TIME: 08:50[EST]| |NRC NOTIFIED BY: FOWLKES |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A VISITING NRC INSPECTOR FELL ABOUT 7'-8' WHILE ASCENDING A LADDER BETWEEN | | FLOORS IN THE AUXILIARY BUILDING. THE INSPECTOR WAS TRANSPORTED TO THE | | RICHLAND MEMORIAL HOSPITAL IN COLUMBIA, SC, DUE TO INJURIES (PRIMARILY BACK | | PAIN). THE INSPECTOR WAS NOT CONTAMINATED, AND WAS FULLY CONSCIOUS. | | | | NOTIFICATION WAS MADE TO THE STATE AND LOCAL EMERGENCY PREPAREDNESS | | AGENCIES, AND NRC MANAGEMENT IN REGION 2. THE LICENSEE INFORMED THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28608 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:10 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/29/95 | +------------------------------------------------+EVENT TIME: 10:05[CST]| |NRC NOTIFIED BY: DOUGLAS BRITZ |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL JORDAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) FAILED A QUARTERLY SURVEILLANCE | | TEST. | | | | DURING PERFORMANCE OF THE QUARTERLY HPCI PUMP OPERABILITY TEST (QCOS | | 2300-5), THE HPCI MOTOR SPEED CHANGER FAILED TO MOVE OFF THE LOW SPEED | | STOP. THE SURVEILLANCE WAS HALTED AND THE HPCI SYSTEM WAS DECLARED | | INOPERABLE. FURTHER TROUBLE SHOOTING IS IN PROGRESS. THE LICENSEE ENTERED | | A 14 DAY LCO PER TECHNICAL SPECIFICATION 3.5.C.3. ALL OTHER ECCS SYSTEMS | | AND THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ARE OPERABLE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 28609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FEDERAL EXPRESS |NOTIFICATION DATE: 03/29/95 | | CITY: SOUTHFIELD REGION: 3 |NOTIFICATION TIME: 13:19 [ET]| | COUNTY: STATE: MI |EVENT DATE: 03/29/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 08:04[EST]| | DOCKET: |LAST UPDATE DATE: 03/29/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MICHAEL JORDAN RDO | | |DON COOL EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHEN (NATIONAL RESPONSE) |SPIROS DROGGITIS SP | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER CALLED TO REPORT A TRANSPORTATION ACCIDENT | | THAT INVOLVED RADIOACTIVE MATERIAL. | | | | A RADIOACTIVE PACKAGE CONTAINING 29 MILLICURIES OF THALLIUM 201 WAS HIT BY | | A VEHICLE AFTER FALLING OUT OF A FEDERAL EXPRESS DELIVERY TRUCK. THE | | INCIDENT OCCURRED IN SOUTHFIELD, MICHIGAN AT 0804 EST. THE LOCAL FIRE | | DEPARTMENT RESPONDED TO THE EVENT. | | | | THE MATERIAL WAS CLEANED UP, AND THEN THE ROADWAY WAS WASHED DOWN. IT IS | | ESTIMATED THAT ABOUT 12 MILLICURIES WAS RELEASED TO THE ENVIRONMENT. NRC | | ASSISTANCE IS NOT BEING REQUESTED AT THIS TIME. | | | | ***UPDATE 3/29/95 @ 1400 FROM PARKER TAKEN BY SEBROSKY *** | | THE FOLLOWING INFORMATION WAS SUPPLIED BY ROY PARKER OF FEDERAL EXPRESS. | | THE MATERIAL INVOLVED IN THE EVENT WAS ACCELERATOR PRODUCED MATERIAL AND | | NOT BYPRODUCT MATERIAL. THEREFORE IT IS NOT LICENSED BY THE NRC. | | | | THE ENTIRE CONTENTS OF THE PACKAGE WERE RELEASED TO THE ENVIRONMENT. THE | | PACKAGE ORIGINALLY CONTAINED 29 MILLICURIES BUT BY THE TIME OF THE ACCIDENT | | IT HAD DECAYED TO 12 MILLICURIES. THERE WERE NO INJURIES INVOLVED IN THE | | ACCIDENT. ONE INDIVIDUAL HAD SOME CONTAMINATION ON THE HANDS AND WAS | | DECONTAMINATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/28/95 | +------------------------------------------------+EVENT TIME: 22:10[EST]| |NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO OIL OVERFLOWING A TANK. | | | | APPROXIMATELY 200 GALLONS OF MAIN TURBINE LUBRICATING OIL OVERFLOWED A | | BATCH OIL TANK DURING TRANSFER. THE ENTIRE VOLUME WAS MAINTAINED WITHIN A | | DESIGNED BERM. ALTHOUGH THE OIL WAS NOT RELEASED TO THE ENVIRONMENT IT MET | | THE DEFINITION OF A REPORTABLE RELEASE UNDER 25 PA CODE 245.1. | | | | THE LICENSEE IS IN THE PROCESS OF CLEANING UP THE AREA. THE LICENSEE | | NOTIFIED THE PENNSYLVANIA DEPARTMENT OF ENVIRONMENTAL RESOURCES AND THE | | LUZERNE COUNTY EMERGENCY MANAGEMENT AGENCY. THE LICENSEE HAS ALSO INFORMED | | THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 17:01 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/29/95 | +------------------------------------------------+EVENT TIME: 14:00[MST]| |NRC NOTIFIED BY: DUANE KANITZ |LAST UPDATE DATE: 03/29/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 85 POWER OPERATION | 85 POWER OPERATION | | 2 | N Y 9 STARTUP | 9 STARTUP | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT ELECTRICAL PENETRATION PROTECTIVE CIRCUITS WERE FOUND TO NOT | | MEET DESIGN REQUIREMENTS. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "34 CONTAINMENT ELECTRICAL PENETRATION CIRCUITS WERE FOUND DURING A DESIGN | | BASIS REVALIDATION EFFORT TO BE NOT IN COMPLIANCE WITH REG GUIDE 1.63 AND | | IEEE 317-1976, WHICH REQUIRE 2 PROTECTIVE DEVICES ON THE CIRCUITS OUTSIDE | | THE CONTAINMENT PENETRATION SPECIFICALLY CREDITED FOR CONTAINMENT | | PENETRATION FEED THROUGH PROTECTION. THESE FINDINGS PLACED UNITS 1, 2 AND | | 3 OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | THE SYSTEMS AFFECTED INCLUDE CONTAINMENT PURGE, GASEOUS RADWASTE, | | CONTAINMENT VENTILATION, HYDROGEN PURGE, INSTRUMENT AIR, NUCLEAR COOLING | | WATER, COMMUNICATIONS, REACTOR COOLANT, RADIOACTIVE DRAINS, INCORE | | DETECTORS, STEAM GENERATOR, SAFETY INJECTION, AND POOL COOLING. THERE WERE | | NO ACTUATIONS AND NONE WERE REQUIRED. THE CAUSE WAS INADEQUATE INITIAL | | DESIGN VALIDATION. THERE ARE NO IMMEDIATE EFFECTS ON THE PLANT. DESIGN | | CHANGE PACKAGES ARE BEING DEVELOPED AND CORRECTIVE MAINTENANCE WILL BE | | PERFORMED TO RESTORE THE DESIGN TO THE CORRECT DESIGN CONFIGURATION." END | | OF TEXT. | | | | THE PROTECTIVE DEVICES SERVE AS FAULT PROTECTION ON ELECTRICAL LINES | | PENETRATING CONTAINMENT. IF AN ELECTRICAL FAULT OCCURRED IN THE | | CONTAINMENT PENETRATION THESE DEVICES WOULD DEENERGIZE THE PARTICULAR | | CIRCUIT THAT HAD THE FAULT. | | | | ALL THREE UNITS ARE IN A 72 HOUR SHUTDOWN ACTION STATEMENT PER TECHNICAL | | SPECIFICATION 3.8.4.1 BECAUSE OF THIS PROBLEM. THE ACTION STATEMENT | | REQUIRES THE LICENSEE TO RESTORE THE CIRCUITS PROTECTIVE FEATURES OR TO | | DEENERGIZE THE CIRCUIT. SEVEN OF THE 34 CONTAINMENT PENETRATIONS ARE | | REQUIRED TO BE ENERGIZED FOR PLANT POWER OPERATION. THE REMAINING | | PENETRATIONS MAY BE DEENERGIZED WITHOUT AFFECTING PLANT POWER OPERATION. | | | | THE LICENSEE BELIEVES THEY CAN FIX THE PROBLEM PRIOR TO EXPIRATION OF THE | | LCO. HOWEVER, THEY ARE PREPARING AN EMERGENCY TECHNICAL SPECIFICATION | | CHANGE AND A REQUEST FOR A NOTICE OF ENFORCEMENT DISCRETION AS A | | CONTINGENCY. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 03/29/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 21:10 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 03/29/95 | +------------------------------------------------+EVENT TIME: 21:00[EST]| |NRC NOTIFIED BY: MICHAEL BOURASSA |LAST UPDATE DATE: 03/30/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEE SPESSARD EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |AL AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN. | | | | ON 3/28/95 THE LICENSEE ENTERED A 24 HOUR LCO PER TECHNICAL SPECIFICATION | | 11.3.1.4.E. THE LICENSEE ENTERED THIS LCO BECAUSE A VALVE IN THE REDUNDANT | | CORE SPRAY LINE FAILED TO STROKE DURING A 30 DAY SURVEILLANCE TEST. THE | | TECH SPEC STATES THAT IF THE LINE IS NOT RETURNED TO OPERABLE STATUS WITHIN | | 24 HOURS THE PLANT MUST BE SHUTDOWN WITHIN THE NEXT 12 HOURS. | | | | THE CORE SPRAY SYSTEM AT BIG ROCK POINT CONSISTS OF TWO FIRE PROTECTION | | PUMPS (ONE MOTOR-DRIVEN AND ONE DIESEL-DRIVEN) THAT DELIVER WATER FROM THE | | INTAKE STRUCTURE TO THE REACTOR VESSEL VIA A CORE SPRAY RING OR A REDUNDANT | | CORE SPRAY NOZZLE. THE VALVE THAT FAILED IS THE OUTBOARD ISOLATION VALVE | | (MO-7070) IN THE REDUNDANT CORE SPRAY LINE. | | | | THE LICENSEE CONTINUES TO TROUBLESHOOT THE PROBLEM. THE VALVE IS CURRENTLY | | STROKING PROPERLY, HOWEVER, THE LICENSEE HAS NOT IDENTIFIED A CAUSE FOR THE | | FAILURE OF THE VALVE TO STROKE ON 3/28/95. THE BASIS FOR TERMINATING THE | | UNUSUAL EVENT WILL BE WHEN ALL RODS (OR ALL BUT ONE ROD) ARE INSERTED, OR | | WHEN THE REDUNDANT CORE SPRAY SYSTEM HAS BEEN DECLARED OPERABLE. ALL OTHER | | ECCS's ARE OPERABLE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR, AND STATE AND LOCAL | | OFFICIALS OF THE EVENT. | | | | ** UPDATE DATE/TIME:3/30/95 @ 0427 EST ***FROM LICENSEE:SHEA BY:McGINTY** | | THE GENERATOR WAS TAKEN OFF-LINE THROUGH AN ORDERLY SHUTDOWN AT 0413 EST, | | AND OPERATORS WERE INSERTING RODS TO COMPLETE THE SHUTDOWN AT THE TIME OF | | THE MORNING STATUS CALL. THE CAUSE OF THE VALVE STROKING PROBLEM HAS YET | | TO BE DETERMINED. THE LICENSEE ANTICIPATES TERMINATING THE UNUSUAL EVENT | | LATER THIS MORNING. | +------------------------------------------------------------------------------+