U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/13/95 - 09/14/95 ** EVENT NUMBERS ** 29325 29326 29327 29328 29329 29330 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/13/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 13:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/13/95 | +------------------------------------------------+EVENT TIME: 08:20[CDT]| |NRC NOTIFIED BY: REED |LAST UPDATE DATE: 09/13/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARNES RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | |BLANCHARD EPA | | |GEORGE PANGBORN NMSS | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATE OF NEBRASKA NOTIFIED OF A CONTAMINATED SHIPMENT. | | | | AT 08:20 ON 9/13/95, THE STATE OF NEBRASKA DEPARTMENT OF PUBLIC HEALTH WAS | | NOTIFIED OF THE RECEIPT OF A CONTAMINATED SHIPMENT ONSITE. THE SHIPMENT | | CONSISTED OF SCAFFOLDING WHICH WAS TRANSPORTED TO THE SITE BY A CARRIER | | WHICH WAS NOT LICENSED TO SHIP RADIOACTIVE MATERIALS. THE SHIPMENT WAS NOT | | EXPECTED TO BE CONTAMINATED. | | | | AT 16:00 ON 9/12/95, A CONTRACT EMPLOYEE WORKING IN THE AREA WHERE THE | | SCAFFOLDING WAS STAGED NOTICED THE REMNANTS OF "CONTAMINATED MATERIAL" | | STICKERS ON THE SCAFFOLDING AND NOTIFIED RADIOLOGICAL PROTECTION PERSONNEL. | | AT 16:15, THE SCAFFOLDING WAS SURVEYED, AND VARIOUS LEVELS OF FIXED | | CONTAMINATION WERE DETECTED (UP TO 150,000 DPM/100 CMý). NO LOOSE | | CONTAMINATION WAS FOUND. THE LICENSEE HAS ERECTED RADIOLOGICAL BARRIERS | | AROUND THE SCAFFOLDING. FURTHER SURVEYS HAVE FOUND NO TRANSFER OF | | CONTAMINATION TO PLANT PERSONNEL OR EQUIPMENT. | | | | THE LICENSEE IS CURRENTLY ATTEMPTING TO CONTACT THE SHIPPER REGARDING THIS | | EVENT. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 09/13/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 13:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/13/95 | +------------------------------------------------+EVENT TIME: 10:10[EDT]| |NRC NOTIFIED BY: TOWER |LAST UPDATE DATE: 09/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONCERN ABOUT A POTENTIAL INTERACTION DURING THE | | USE OF THE CONTAINMENT HYDROGEN ANALYZERS WHICH COULD AFFECT CONTAINMENT | | INTEGRITY. | | | | DURING OPERATION, THE HYDROGEN ANALYZERS ARE ISOLATED FROM CONTAINMENT WITH | | VALVES THAT ARE TYPE "C" TESTED. CONTAINMENT INTEGRITY IS MAINTAINED IN | | THIS CONFIGURATION. IN AN ACCIDENT, THE EMERGENCY PROCEDURES DIRECT | | OPERATORS TO OPEN THE ISOLATION VALVES TO THE HYDROGEN ANALYZERS TO PLACE | | THEM IN SERVICE. GIVEN THE EXISTENCE OF A LEAK WITHIN THE INSTRUMENT PANEL | | OR SAMPLE FLOW PATH, THIS ACTION WOULD CAUSE LEAKAGE FROM CONTAINMENT UNTIL | | SUCH TIME THAT THE LEAK WOULD BE RECOGNIZED AND ISOLATED. IT IS | | UNDETERMINED IF THIS LEAKAGE WOULD GO UNDETECTED LONG ENOUGH TO EXCEED | | ALLOWABLE LIMITS. THEREFORE, THERE IS A POTENTIAL THAT THIS SITUATION | | ALONE COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY FUNCTION. | | | | A DETAILED REVIEW OF THE HYDROGEN ANALYZER CONTAINMENT PENETRATIONS AND THE | | CONFIGURATION OF THE SYSTEM REVEALED THAT THE WORK HAD BEEN PERFORMED ON | | THE HYDROGEN ANALYZERS THAT AFFECTED THE CONTAINMENT BOUNDARY, AND POST | | MAINTENANCE TESTING FOR LEAKAGE WAS NOT PERFORMED. ALL HYDROGEN ANALYZER | | BOUNDARIES ON BOTH UNITS WERE LEAK TESTED. THE "2B" ANALYZER WAS | | DETERMINED TO HAVE SOME LEAKAGE, BUT IT WAS WITHIN ALLOWABLE LIMITS. | | FURTHER REVIEW DETERMINED THAT THE TYPE "C" TESTING THAT WAS PERFORMED ON | | THE SYSTEM HAS NOT BEEN ADEQUATE TO LEAK TEST THE ENTIRE CONTAINMENT | | BOUNDARY ASSOCIATED WITH THESE PENETRATIONS. ADDITIONAL TESTING IDENTIFIED | | HYDROGEN ANALYZER "1A" WITH LEAKAGE. THIS LEAKAGE COULD POTENTIALLY EXCEED | | ALLOWABLE LIMITS DURING AN ACCIDENT, IF UNDETECTED. | | | | WHILE VALVES EXIST WHICH COULD BE USED TO ISOLATE THE HYDROGEN ANALYZERS, | | QUESTIONS ABOUT THE ABILITY TO READILY DETECT LEAKAGE WHILE THE ANALYZER IS | | IN SERVICE HAVE LED TO THE CONCLUSION THAT THE POTENTIAL FOR LEAKAGE TO | | EXCEED TECHNICAL SPECIFICATION LIMITS (0.07 La) MAY EXIST. THIS POTENTIAL | | MAY ALSO EXIST FOR OTHER PLANTS USING THE SAME OR SIMILAR | | OUTSIDE-CONTAINMENT ANALYZERS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29327 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/13/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:22 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/13/95 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: HENRY |LAST UPDATE DATE: 09/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE COMPONENT COOLING WATER SYSTEM FOR | | UNIT 3 IS INOPERABLE. | | | | DURING PERFORMANCE OF COMPONENT COOLING WATER (CCW) FLOW BALANCING ANALYSES | | TO SUPPORT A THERMAL UP-RATE PROJECT, CERTAIN CCW FLOW CONFIGURATIONS WERE | | IDENTIFIED WHICH COULD RESULT IN MAXIMUM ACCIDENT CCW FLOW RATES THAT | | EXCEED THE CCW HEAT EXCHANGER FLOW LIMITS ON UNIT 3. UNIT 3 IS IN | | REFUELING OUTAGE, AND CCW IS NOT REQUIRED TO BE OPERABLE UNTIL THE UNIT | | ENTERS MODE 4. THESE LIMITS ARE BASED ON THE CRITICAL CROSS-FLOW VELOCITY | | AT WHICH TUBE RESONANT VIBRATION IS EXPECTED. AS THE CRITICAL VELOCITY IS | | APPROACHED, TUBE VIBRATION MAY RESULT IN TUBE FAILURE. THE FLOW LIMITS ARE | | NOT APPROACHED DURING NORMAL OPERATION, NOR ARE THEY APPROACHED DURING | | DESIGN BASIS CONDITIONS WITH THE ASSUMED SINGLE FAILURE. HOWEVER, IF ALL | | COMPONENTS START AS EXPECTED DURING AN ESF ACTUATION (SPECIFICALLY TWO CCW | | PUMPS AND THREE EMERGENCY CONTAINMENT COOLERS), WITH ONLY TWO OF THE THREE | | CCW HEAT EXCHANGERS IN SERVICE, FLOW IN THOSE TWO CCW HEAT EXCHANGERS WILL | | EXCEED THEIR DESIGN LIMITS. THUS THE FLOW BALANCE EXISTING IN UNIT 3 COULD | | HAVE ALLOWED CCW FLOW RATES DURING THE COURSE OF AN ACCIDENT HIGH ENOUGH TO | | RESULT IN DAMAGE TO THE CCW HEAT EXCHANGERS. THEREFORE, THE PLANT COULD | | HAVE OPERATED IN AN UNANALYZED CONFIGURATION. CORRECTIVE ACTIONS WILL BE | | TAKEN TO RESOLVE THIS ISSUE BEFORE UNIT 3 ENTERS MODE 4. | | | | THIS CONDITION IS NOT A PRESENT CONCERN ON UNIT 4, BECAUSE THE UNIT 4 HEAT | | EXCHANGERS WERE MODIFIED WITH TUBES OF A DIFFERENT MATERIAL AND CLOSER TUBE | | SUPPORT SPAN SPACING SEVERAL YEARS AGO. THE RESULTING NATURAL FREQUENCY IS | | ABOVE ANY POSTULATED FLOW VELOCITIES FOR UNIT 4. THEREFORE THE UNIT 4 CCW | | SYSTEM REMAINS OPERABLE. THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29328 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CANADIAN WORCESTER CONTROLS LTD |NOTIFICATION DATE: 09/13/95 | | CITY: SCARBOROUGH REGION: 0 |NOTIFICATION TIME: 17:31 [ET]| | COUNTY: STATE: |EVENT DATE: 09/13/95 | |LICENSE#: AGREEMENT: |EVENT TIME: 00:00[ ]| | DOCKET: |LAST UPDATE DATE: 09/13/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: KOTACK |VERN HODGE NRR | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CANADIAN WORCESTER CONTROLS LTD REPORTED THAT IT SUPPLIED 3/4" BALL VALVES | | TO COMANCHE PEAK AND BRUNSWICK POWER PLANTS THAT WERE DEFECTIVE. | | | | THE VALVES WHICH WERE SUPPLIED BY CANADIAN WORCESTER CONTROLS LTD (CWCL) | | CONTAIN BOLTING THAT ORIGINATED FROM A HEAT LOT CHARGE THAT CONTAINED A | | DEFECTIVE PRODUCT. THE SUSPECT MATERIAL IS A 3/8" - 16 SA 193 B7 HEX | | CAPSCREW PRODUCT MARKETING B7, C, TS6, S5. PRELIMINARY INVESTIGATION BY | | THE FASTENER SUPPLIER (CARDINAL INDUSTRIAL PRODUCTS) HAS REVEALED THAT AS | | MANY AS 25% OF THE FASTENERS FROM THE HEAT LOT CHARGE MAY HAVE MECHANICAL | | PROPERTIES BELOW THE SPECIFIED MINIMUM. A TEST BLANK FROM THE AFFECTED | | HEAT LOT WAS ORDERED BY CWCL AT THE TIME OF PURCHASE, AND THE SUBSEQUENT | | TESTING BY AN INDEPENDENT LAB PROVIDED RESULTS WHICH MEET THE MATERIAL | | SPECIFICATION REQUIREMENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29329 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 09/13/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 17:58 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/13/95 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: ROLAND |LAST UPDATE DATE: 09/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT COMMENCED A TECHNICAL SPECIFICATION 3.6.1.1 REQUIRED SHUTDOWN AT | | 17:30 DUE TO THE FAILURE OF A LLRT FOR DRYWELL AND SUPPRESSION CHAMBER | | NITROGEN/AIR PURGE CONTAINMENT PENETRATIONS. | | | | DURING THE PERFORMANCE OF A LLRT FOR THE DRYWELL AND SUPPRESSION CHAMBER | | NITROGEN/AIR PURGE PENETRATIONS OF THE PRIMARY CONTAINMENT, THE TEST VOLUME | | WAS NOT ABLE TO BE PRESSURIZED. THE ASSOCIATED VALVES WERE STROKED IN AN | | ATTEMPT TO IDENTIFY THE SOURCE OF THE LEAK. IN ADDITION, VALVE STROKES | | WERE ALSO ADJUSTED IN ATTEMPT TO ESTABLISH A GOOD SEAL, HOWEVER, WITHOUT | | SUCCESS. | | | | THE AS-FOUND LEAK RATE WAS GREATER THAN 200 STANDARD LITERS PER MINUTE | | (SLM). STROKING THE VALVES DROPPED THE LEAKAGE TO AS LOW AS 150 SLM. | | ADJUSTING THE TRAVEL STOPS ON THE VALVES HAS THE LEAKAGE CURRENTLY AT 190 | | SLM @ 42 PSIG. (THE LEAKAGE LIMIT IS <15.7 SLM.) | | | | THE LICENSEE WILL ENTER ITS REFUELING AND INSPECTION OUTAGE WHILE SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED, AND A PRESS RELEASE WILL BE MADE. | | | | * * * UPDATE @ 2:08 9/14/95 FROM FERNSLER TAKEN BY SEBROSKY * * * | | AT 23:32 ON 9/13/95 WITH THE PLANT AT 16% POWER, THE LICENSEE PLACED THE | | MODE SWITCH IN THE SHUTDOWN POSITION. THE POST-SCRAM RESPONSE WAS NORMAL. | | THE LICENSEE WAS ORIGINALLY SCHEDULED TO ENTER ITS REFUELING OUTAGE ON | | 9/15/95. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R1DO (RULAND). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29330 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERSHAM |NOTIFICATION DATE: 09/13/95 | | CITY: BURLINGTON REGION: 1 |NOTIFICATION TIME: 20:24 [ET]| | COUNTY: STATE: MA |EVENT DATE: 09/13/95 | |LICENSE#: 20-12836-01 AGREEMENT: N |EVENT TIME: 18:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/13/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM RULAND RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ROUGHAN | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AMERSHAM REPORTED THAT A TECHNICIAN WORKING IN THE RADIATION LAB DISCOVERED | | A HOT PARTICLE IN HIS PROTECTIVE CLOTHING WHEN EXITING THE CONTAMINATION | | CONTROL AREA. THE PARTICLE WAS NOT TAKEN OUT OF THE CONTAMINATION CONTROL | | AREA BUT FROM PRELIMINARY ASSESSMENTS THE INDIVIDUAL MAY HAVE RECEIVED A | | SKIN DOSE OF 342 RAD FROM THE IRIDIUM 192 PARTICLE. THE PARTICLE WAS | | PROBABLY IN CONTACT WITH THE CLOTHING FOR APPROXIMATELY 1 HOUR AND 15 | | MINUTES. THE LICENSEE ESTIMATES THAT THE WORST POSSIBLE WHOLE BODY | | EXPOSURE COULD BE 265 MILLIREM. FURTHER CALCULATIONS WILL BE MADE | | TOMORROW. | +------------------------------------------------------------------------------+