U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/26/97 - 08/27/97 ** EVENT NUMBERS ** 32804 32808 32817 32818 32819 32820 32821 32822 32823 32824 32825 32826 32827 +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32804 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIV. OF CINCINNATI HOSPITAL |NOTIFICATION DATE: 08/22/97 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 18:00 [ET]| | COUNTY: STATE: OH |EVENT DATE: 08/22/97 | |LICENSE#: 34-06903-05 AGREEMENT: N |EVENT TIME: 16:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MIKE JORDAN RDO | | |FRED COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: VICTORIA MORRIS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE IODINE-125 SEEDS POSSIBLY MISSING. | | | | THE RADIATION SAFETY OFFICER FOR THE UNIVERSITY OF CINCINNATI HOSPITAL | | RELAYED THE FOLLOWING INFORMATION. | | | | ON 08/19/97, A PATIENT AT THE UNIVERSITY OF CINCINNATI HOSPITAL (LOCATED AT | | 234 GOODMAN STREET) RECEIVED 37 IODINE-125 SEEDS TO HIS BRAIN TO CONTROL A | | BRAIN TUMOR. THE TOTAL ACTIVITY OF EACH SEED IS 0.7 mCi. WHILE INSERTING | | THE SEEDS INTO THE PATIENT'S BRAIN, PRESSURE FROM THE TUMOR CAUSED ONE SEED | | TO DROP ONTO THE FLOOR AND FIVE SEEDS TO GO INTO A SUCTION TUBE. A | | RADIATION SURVEY OF THE AREA DID NOT FIND ANY OTHER SEEDS. | | | | ON 08/22/97, THE PATIENT WAS X-RAYED TO FIND OUT HOW MANY IODINE-125 SEEDS | | HAD BEEN INSERTED INTO THE PATIENT. THEY FOUND THAT THE PATIENT HAD 37 | | IODINE-125 SEEDS IN HIS BRAIN. THE COMPANY (UNKNOWN) WHICH DELIVERED THE | | IODINE-125 SEEDS SAID THAT THEY DELIVERED 100 SEEDS. UPON PERFORMING AN | | INVENTORY ON THE NUMBER OF IODINE-125 SEEDS (NOT USED) THE HOSPITAL | | DISCOVERED THAT THEY HAD 54 IODINE-125 SEEDS INSTEAD OF THE 57 SEEDS | | EXPECTED. | | | | * * * 1658 08/26/97 UPDATE FROM MORRIS RECEIVED BY TROCINE * * * | | | | THREE IODINE-125 SEEDS WERE FOUND IN AN AUTOCLAVE AT APPROXIMATELY 1600 ON | | 08/25/97. THESE SEEDS WERE VERIFIED TO BE THE MISSING SEEDS ON 08/26/97. | | THE LICENSEE CURRENTLY BELIEVES THAT THE AUTOCLAVE HAD BEEN CLOSED THE | | ENTIRE TIME THAT THE SEEDS WERE MISSING. THE LICENSEE NOTIFIED NRC REGION | | 3 (JOHN MADERA). THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (JORDAN) AND | | NMSS EO (PICCONE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32808 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 08/23/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/23/97 | +------------------------------------------------+EVENT TIME: 09:40[CDT]| |NRC NOTIFIED BY: JIM SCHOTTEL |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | WESTINGHOUSE 4160 VOLT BREAKER LUBRICATION PROBLEM DISCOVERED. | | | | THE CLINTON POWER STATION HAS RECENTLY EXPERIENCED TWO FAILURES OF | | WESTINGHOUSE 4160 VOLT BREAKERS. THESE FAILURES HAVE BEEN ANALYZED TO | | DETERMINE A PROBABLE CAUSE. AS A RESULT OF THESE FAILURES, CORRECTIVE | | MAINTENANCE WAS INSTITUTED FOR ALL OF THE REMAINING WESTINGHOUSE 4160 VOLT | | BREAKERS (75 BREAKERS). WHILE PERFORMING THIS MAINTENANCE ON OTHER | | WESTINGHOUSE BREAKERS, CONDITIONS SIMILAR TO THE TWO FAILED BREAKERS WERE | | DETECTED. ALTHOUGH THE LICENSEE HAS NOT HAD ANY FAILURES ON THESE | | ADDITIONAL BREAKERS, THESE CONDITIONS COULD BE INDICATIVE OF PRECURSORS | | WITH THE POTENTIAL FOR FUTURE FAILURES. THE LICENSEE CONSIDERS THIS TO BE | | A SERIOUS DEGRADATION OF THE SAFETY RELATED ELECTRICAL SYSTEM. | | | | IT APPEARS THAT THE BREAKERS HAVE INADEQUATE LUBRICATION IN THE UPPER PART | | OF THE BREAKER MECHANISM WHERE THE CONTACTS ARE LOCATED. ACCORDING TO THE | | VENDOR MANUAL, THESE BREAKERS ARE SUPPOSED TO BE LIFE TIME COMPONENTS THAT | | DO NOT REQUIRE ANY MAINTENANCE BY THE OWNER UNLESS WORK IS PERFORMED ON THE | | BREAKER CONTACTS. A LICENSEE ANALYSIS HAS SHOWN THAT THE LUBRICATION IN | | THE BREAKERS AGES WITH TIME AND ALSO THAT THE BREAKER SPRING ALIGNMENT AND | | SPRING STRENGTH CHANGE OVER TIME. | | | | ALL THESE BREAKERS ARE LOCATED IN THE AUXILIARY BUILDING. THE AUXILIARY | | BUILDING IS AIR CONDITIONED AND THE AUXILIARY BUILDING TEMPERATURE IS | | MAINTAINED IN 70s. | | | | THE DIVISION 1 AND DIVISION 2 ELECTRICAL SYSTEMS ARE AFFECTED BY THE | | BREAKER PROBLEM SINCE THEY BOTH USE WESTINGHOUSE 4160 VOLT BREAKERS. THE | | DIVISION 3 ELECTRICAL SYSTEM DOES NOT UTILIZE THESE TYPE OF BREAKERS AND IS | | OPERABLE. | | | | THE REACTOR WATER CLEANUP SYSTEM COULD BE USED TO MAINTAIN INVENTORY USING | | THE BALANCE OF PLANT POWER SUPPLY. IF OFFSITE POWER IS LOST, THE | | DIVISION 3 (HIGH PRESSURE CORE SPRAY) PUMP COULD BE USED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * 1823 08/26/97 UPDATE FROM FUNKHOUSER RECEIVED BY TROCINE * * * | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "REPLACE THE FOLLOWING SENTENCES FROM THE PREVIOUS NOTIFICATION AS SHOWN | | BELOW:" | | | | "OLD SENTENCE: IT APPEARS THAT THE BREAKERS HAVE INADEQUATE LUBRICATION IN | | THE UPPER PART OF THE BREAKER MECHANISM WHERE THE CONTACTS ARE LOCATED." | | | | "REPLACE WITH: THE BREAKER EXHIBITED EXCESSIVE MECHANICAL FRICTION IN THE | | MOVING CONTACT HINGE POINTS AND THE MAIN CONTACTS. THIS WAS DUE TO | | DEGRADED LUBRICATION ON THE HINGE POINTS AND ROUGH SURFACES WITH NO | | LUBRICATION ON THE CONTACTS." | | | | "OLD SENTENCE: ACCORDING TO THE VENDOR MANUAL, THESE BREAKERS ARE SUPPOSED | | TO BE LIFETIME COMPONENTS THAT DO NOT REQUIRE ANY MAINTENANCE BY THE OWNER | | UNLESS WORK IS PERFORMED ON THE BREAKER CONTACTS." | | | | "REPLACE WITH: SENTENCE DELETED. (THIS SENTENCE WAS INCORRECT AND WAS | | DELETED.)" | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (JORDAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32817 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/26/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 11:17 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 10:57[EDT]| |NRC NOTIFIED BY: S. FREGEAU |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 50 APPENDIX R HOT SHORT ISSUE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AS PART OF CORRECTIVE ACTION TO LER 97-02, DUKE ENGINEERING AND SERVICES | | PERFORMED A TECHNICAL ASSESSMENT OF NMP2 CONTROL ROOM FIRE SAFE SHUTDOWN | | ANALYSIS TO VERIFY COMPLIANCE WITH NUREG-800 REQUIREMENTS, 'FIRE PROTECTION | | PROGRAM REQUIREMENTS PER 10CFR50 APPENDIX A CRITERION 3.'DURING THIS | | ASSESSMENT, IT WAS IDENTIFIED THAT GENERIC LETTER 86-10, 'IMPLEMENTATION OF | | FIRE PROTECTION PROGRAM REQUIREMENTS,' ENCLOSURE 1 (INTERPRETATIONS OF | | APPENDIX R) SECTION 5.3.10 REQUIRES THAT THE SAFE SHUTDOWN CAPABILITY NOT | | BE ADVERSELY AFFECTED BY A FIRE IN ANY PLANT AREA WHICH RESULTS IN SPURIOUS | | ACTUATION OF THE REDUNDANT VALVES IN ANY ONE HIGH/LOW PRESSURE INTERFACE | | LINE. | | | | THE REACTOR WATER CLEANUP SYSTEM (WCS) RELATED AIR OPERATED VALVES LISTED | | IN USAR TABLE 9B.5-1 ARE HIGH/LOW PRESSURE INTERFACE VALVES. THESE VALVES | | ARE NORMALLY CLOSED DURING NORMAL PLANT OPERATION AND ARE CONTROLLED FROM | | LOCAL PANELS 2WCS-PNL187 AND 188. THE MAJORITY OF THESE VALVES AND THE | | LOCAL PANELS ARE LOCATED IN FIRE SUB AREA (FSA) 35, FIRE ZONE 274SW IN | | REACTOR BUILDING ELEVATION 328FT. A SINGLE FIRE IN FSA 35, WITH OFFSITE | | POWER AVAILABLE, COULD SPURIOUSLY (DUE TO FIRE INDUCED HOT SHORTS) ENERGIZE | | THESE VALVES AND OPEN A HIGH/LOW PRESSURE INTERFACE LINE, CAUSING A FIRE | | INDUCED LOSS OF COOLANT ACCIDENT (LOCA). | | | | IMMEDIATE CORRECTIVE ACTIONS ARE TO STATION A CONTINUOUS FIRE WATCH AT | | LOCAL PANELS 2WCS-PNL187 AND 188, AND TO IMPLEMENT PROCEDURE CHANGES TO | | ISOLATE THE REACTOR WATER CLEANUP SYSTEM IF A FIRE IS CONFIRMED IN THE FIRE | | ZONE ASSOCIATED WITH THE REACTOR BUILDING." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32818 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:56 [ET]| |RX TYPE: [1] CE |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: BILL ROBERTS |LAST UPDATE DATE: 08/26/97 | |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 | | |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 | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH DIESEL GENERATORS DECLARED INOPERABLE DUE TO FAILURE TO ADEQUATELY | | TEST ONE RELAY CONTACT ON EACH TRAIN FOR EACH DIESEL GENERATOR | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THIS IS A PRELIMINARY NOTIFICATION OF [A] CONDITION POTENTIALLY REPORTABLE | | AS A CONDITION OUTSIDE THE DESIGN BASIS. DURING A REVIEW OF THE LOGIC | | CIRCUIT TESTING UNDER [GENERIC LETTER] 96-01, [TESTING OF SAFETY-RELATED | | LOGIC CIRCUITS,] ONE RELAY CONTACT IN THE LOAD SEQUENCING CIRCUITRY FOR | | EACH DIESEL GENERATOR WAS DISCOVERED NOT TO HAVE BEEN TESTED IN ACCORDANCE | | WITH TECHNICAL SPECIFICATION 4.7.1b. IT IS BELIEVED THAT THE RELAYS AND | | CONTACTS ARE FUNCTIONAL BASED ON OTHER SURVEILLANCE TESTS WHICH ACTUATE THE | | RELAYS AND VERIFY THE OTHER CONTACTS ON THE SAME RELAYS." | | | | "IN ACCORDANCE WITH [TECHNICAL SPECIFICATION] 4.0.3, BOTH DIESELS HAVE BEEN | | DECLARED INOPERABLE BECAUSE OF THE MISSED SURVEILLANCE, AND [TECHNICAL | | SPECIFICATION] 3.0.3 HAS BEEN ENTERED. UNDER [TECHNICAL SPECIFICATION] | | 4.0.3, THE PLANT HAS 24 HOURS TO TEST THESE CONTACTS BEFORE TAKING THE | | ACTIONS OF [TECHNICAL SPECIFICATION] 3.0.3. [THE LICENSEE] ANTICIPATE[S] | | [THAT] TESTING WILL [BE] COMPLETED AND THE DIESELS DECLARED OPERABLE WITHIN | | 24 HOURS WITH NO IMPACT ON CONTINUED PLANT OPERATION." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32819 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WEAVEXX |NOTIFICATION DATE: 08/26/97 | | CITY: WAKE FOREST REGION: 2 |NOTIFICATION TIME: 13:37 [ET]| | COUNTY: WAKE STATE: NC |EVENT DATE: 08/26/97 | |LICENSE#: 32-18405-02 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PAUL FREDRICKSON/R2 RDO | | |FREDERICK COMBS/NMSS EO | +------------------------------------------------+MIKE JORDAN/REGION 3 RDO | |NRC NOTIFIED BY: AURTHER BULLERWELL | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN NDC GAUGE CONTAINING 80 MILLICURIES OF AMERICIUM-241 WAS STOLEN FROM A | | VAN LOCATED IN COLUMBUS, OHIO. | | | | LAST NIGHT, A VAN CONTAINING AN NDC GAUGE (MODEL 104P) WITH 80 MILLICURIES | | OF AMERICIUM-241 WAS BROKEN INTO, AND THE GAUGE WAS STOLEN ALONG WITH OTHER | | EQUIPMENT. THE GAUGE WAS DISCOVERED TO BE MISSING THIS MORNING. THE VAN | | WAS PARKED AT A HOLIDAY INN LOCATED IN COLUMBUS, OHIO, AND THE COLUMBUS | | POLICE DEPARTMENT WAS CONTACTED. | | | | APPARENTLY, THE GAUGE WAS LABELLED AND LOCKED INSIDE A CASE WITH THE SOURCE | | IN THE SHIELDED POSITION. THE CASE WAS ALSO STRAPPED DOWN INSIDE THE VAN. | | THIS GAUGE IS NORMALLY USED TO MEASURE TOTAL MASS OF SHEET PAPER AND | | CLOTHING (A TEXTILE PRODUCT USED IN THE PRODUCTION OF PAPER). | | | | THE LICENSEE NOTIFIED THE REGION 2 OFFICE (JOHN POTTER) AND THE REGION 3 | | OFFICE (TONY GO). (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE | | NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32820 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:57 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 11:00[CDT]| |NRC NOTIFIED BY: JOHN LECHMAIER |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT A POSTULATED FIRE AFFECTING NON-SAFE SHUTDOWN LOAD CABLES | | COULD RESULT IN THE LOSS OF BUSES NEEDED TO POWER SAFE SHUTDOWN LOADS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE PERFORMING A CORRECTIVE ACTION REVIEW FOR A PROBLEM IDENTIFIED | | THROUGH A SELF ASSESSMENT, IT WAS FOUND THAT 4KV AND 480V ELECTRICALLY | | CONTROLLED BREAKERS FOR NON-SAFE SHUTDOWN LOADS WERE NOT ALWAYS BEING | | TRIPPED AND CONTROL CIRCUIT FUSES WERE NOT ALWAYS BEING REMOVED AS REQUIRED | | BY THE FIRE PROTECTION REPORT. A POSTULATED FIRE AFFECTING THE NON-SAFE | | SHUTDOWN LOAD CABLES COULD RESULT IN THE LOSS OF [THE] SWITCHGEAR PROVIDING | | POWER TO EQUIPMENT RELIED UPON FOR SAFE SHUTDOWN ACTIVITIES. THEREFORE, | | PROCEDURE STEPS THAT ASSURE AVAILABILITY OF POWER TO VARIOUS COMPONENTS | | NEEDED TO BRING THE REACTOR TO A SAFE SHUTDOWN CONDITION ARE NOW | | INADEQUATE." | | | | THE LICENSEE HAS NOT DECLARED ANY EQUIPMENT INOPERABLE AS A RESULT OF THIS | | ISSUE. HOWEVER, THE UNITS ARE IN 'ADDITIONAL SAFE SHUTDOWN PATHS' (67-DAY | | LIMITING CONDITIONS FOR OPERATION). | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32821 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:06 [ET]| |RX TYPE: [1] CE |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 12:15[CDT]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEFF SHACKELFORD 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMMENCEMENT OF A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO AN | | INOPERABLE INVERTER | | | | AT 1215 CDT ON AUGUST 26, 1997, THE LICENSEE CONSERVATIVELY COMMENCED A | | PLANT SHUTDOWN PRIOR TO EXPIRATION OF THE TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION (LCO) FOR TECHNICAL SPECIFICATION 2.7.o. THIS | | SPECIFICATION ALLOWS 1 OF 4 STATION INVERTERS TO BE INOPERABLE FOR UP TO 24 | | HOURS. THE 'A' INVERTER BECAME INOPERABLE DUE TO THE FAILURE OF ITS | | TRANSFER SWITCH AT 1342 CDT ON AUGUST 25, 1997. THE TECHNICAL | | SPECIFICATION LCO ALLOWS 12 HOURS TO REACH HOT SHUTDOWN (MODE 3). | | | | CURRENT PLANS ARE TO COMPLETE THE SHUTDOWN, REPAIR THE DEFECTIVE TRANSFER | | SWITCH, AND RETURN THE 'A' INVERTER TO SERVICE. UNIT RESTART IS CURRENTLY | | SCHEDULED FOR TODAY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE LICENSEE PLANS TO | | ISSUE A PRESS RELEASE ONLY IF THE SHUTDOWN EXCEEDS 24 HOURS. | | | | * * * 2330 EDT AUGUST 26, 1997, UPDATE FROM MATZKE RECEIVED BY TROCINE * * | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 2134 [CDT], THE FORT CALHOUN STATION VOLUNTARILY ENTERED TECHNICAL | | SPECIFICATION 2.0.1 ('MOTHERHOOD') WHICH REQUIRES THAT THE PLANT BE PLACED | | IN HOT SHUTDOWN WITHIN 6 HOURS OF ENTERING THE SPECIFICATION. TECHNICAL | | SPECIFICATION 2.0.1 WAS ENTERED TO ALLOW REPAIR OF THE 'A' INVERTER | | TRANSFER SWITCH WITHOUT DE-ENERGIZING THE 'A' INSTRUMENT BUS [FOR AN | | EXTENDED PERIOD OF TIME]. POWER FOR THE 'A' INSTRUMENT BUS WILL BE | | PROVIDED FROM A 480VAC POWER SUPPLY THROUGH A 480 TO 120VAC TRANSFORMER | | THROUGH ONE OF THE BUS CROSS TIE BREAKERS FROM THE 'C' INSTRUMENT BUS TO | | THE 'A' INSTRUMENT BUS. THIS CONFIGURATION REQUIRES FORT CALHOUN TO | | ADMINISTRATIVELY DECLARE THE 'A' INSTRUMENT BUS INOPERABLE AS WELL AS THE | | 'A' INVERTER. TECHNICAL SPECIFICATION 2.7 DOES NOT AUTHORIZE THIS | | CONFIGURATION. THIS ELECTRICAL CONFIGURATION IS BEING USED TO ALLOW THE | | 'A' INSTRUMENT BUS TO REMAIN ENERGIZED WHILE THE TRANSFER SWITCH FOR THE | | 'A' INVERTER IS BEING REPAIRED. [HOWEVER,] DE-ENERGIZING THE 'A' | | INSTRUMENT BUS AND ITS ASSOCIATED EQUIPMENT IS JUDGED TO INDUCE A LESS | | ACCEPTABLE TRANSIENT TO THE PLANT THAN INSTALLING THIS TEMPORARY | | MODIFICATION. IN ADDITION, WHEN THE 'A' INSTRUMENT BUS IS DE-ENERGIZED, A | | START SIGNAL IS RECEIVED BY ALL THREE CHARGING PUMPS. TO PREVENT ADDITION | | OF EXCESS INVENTORY TO THE REACTOR COOLANT SYSTEM, ALL THREE CHARGING PUMPS | | MUST BE PLACED IN PULL-TO-LOCK. TECHNICAL SPECIFICATIONS ONLY ALLOW TWO OF | | THE THREE PUMPS TO BE PLACED IN THIS CONDITION (INOPERABLE)." | | | | "THE INSTRUMENT BUS WAS RE-ENERGIZED AT 2137 CDT AS DESCRIBED ABOVE. ONE | | OF THE THREE CHARGING PUMPS [HAS] BEEN RESTORED TO AN OPERABLE CONDITION. | | THE OTHER TWO PUMPS ARE STILL IN PULL-TO-LOCK. THE REACTOR SHUTDOWN IS | | CONTINUING. THE REACTOR WILL BE IN HOT SHUTDOWN PRIOR TO 0142 CDT [ON] | | AUGUST 27, 1997[, UNLESS THE UNIT CLEARS THE REQUIRED MOTHERHOOD STATEMENTS | | AND THE PREVIOUS TECHNICAL SPECIFICATION LCO TIME LIMIT]." | | | | THE UNIT IS CURRENTLY ON LINE AT 25% REACTOR POWER. THE SWITCH HAS BEEN | | REPLACED, AND THE LICENSEE IS IN THE PROCESS OF CLEARING THE NECESSARY TAGS | | PRIOR TO POST-MAINTENANCE TESTING. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R4DO (SHACKELFORD). | | | | ***UPDATE ON 8/27/97 @ 0110 ET BY BLESSIE TO GOULD*** AT 2242 CT THE PLANT | | EXITED SHUTDOWN TS 2.0.1 AND 2.7. INVERTER "A" TRANSFER SWITCH REPLACEMENT | | AND ASSOCIATED POST-MAINTENANCE TESTING IS COMPLETE AND THE INSTRUMENT BUS | | "A" HAS BEEN RETURNED TO ITS NORMAL SOURCE(INVERTER "A"). REACTOR SHUTDOWN | | WAS HALTED AT 22% POWER AND PREPARATIONS ARE UNDERWAY TO RETURN TO 100% | | POWER. THE RESIDENT HAS BEEN NOTIFIED. THE REG 3 RDO(SHACKELFORD) HAS | | BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32822 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |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: 08/26/97 | |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT A NORMAL OPERATING PROCEDURE ALLOWED PLANT OPERATION WITH | | COMPONENT COOLING WATER HEAT EXCHANGER OUTLET TEMPERATURES GREATER THAN THE | | DESIGN LIMIT SPECIFIED IN THE FINAL SAFETY ANALYSIS REPORT | | | | DURING THE ONGOING NRC ARCHITECT-ENGINEER DESIGN INSPECTION, A QUESTION WAS | | ASKED RELATIVE TO A STATEMENT USED IN THE NORMAL OPERATING PROCEDURE FOR | | THE COMPONENT COOLING WATER (CCW) SYSTEM. THE STATEMENT ALLOWS FOR A HEAT | | EXCHANGER OUTLET TEMPERATURE FOR CCW TO REACH 120øF FOR A PERIOD OF 3 HOURS | | DURING NORMAL COOLDOWN ON THE RESIDUAL HEAT REMOVAL SYSTEM. INVESTIGATION | | REVEALED THAT THIS STATEMENT WAS IN THE ORIGINAL ISSUE OF THE PROCEDURE IN | | 1976. HOWEVER, NO 10 CFR 50.59 UNREVIEWED SAFETY EVALUATION DETERMINATION | | DOCUMENTATION COULD BE FOUND TO SUPPORT THIS DESIGN PARAMETER. | | | | THE LICENSEE'S FINAL SAFETY ANALYSIS REPORT (FSAR) STATES THAT THE CCW HEAT | | EXCHANGER OUTLET DESIGN TEMPERATURE IS 95øF. BASED ON THE FSAR REQUIRING | | THE 95øF OUTLET TEMPERATURE AND THE LACK OF AN UNREVIEWED SAFETY QUESTION | | DETERMINATION TO JUSTIFY OPERATION EXCEEDING 95øF, THE UNITS WERE IN A | | CONDITION THAT ALLOWED OPERATION OUTSIDE THE DESIGN BASIS BECAUSE THE | | PROCEDURE ALLOWED OPERATION UP TO 120øF FOR A PERIOD OF 3 HOURS DURING | | NORMAL COOLDOWN ON THE RESIDUAL HEAT REMOVAL SYSTEM. THE UNITS ARE NOT | | CURRENTLY IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS | | A RESULT OF THIS ISSUE. | | | | PROCEDURE CHANGES HAVE BEEN MADE TO REMOVE THE INAPPROPRIATE STATEMENT. A | | CONDITION REPORT HAS ALSO BEEN WRITTEN TO INITIATE AN INVESTIGATION INTO | | THIS EVENT AND DETERMINE APPROPRIATE PREVENTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 08/26/97 | |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 TIME TO BOIL EVENTS AND 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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32824 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |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: 08/26/97 | |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 TO PERFORM A 10 CFR 50.59 EVALUATION FOR A PROCEDURE CHANGE | | INVOLVING COMPONENT COOLING WATER HEAT EXCHANGER OUTLET TEMPERATURE LIMITS | | | | DURING THE ONGOING NRC ARCHITECT-ENGINEER DESIGN INSPECTION, A QUESTION WAS | | ASKED RELATIVE TO THE FACT THAT DURING THE LAST UNIT 2 REFUELING OUTAGE, AN | | ADMINISTRATIVE LIMIT OF 90øF WAS PLACED ON THE COMPONENT COOLING WATER | | (CCW) SYSTEM. THE THERMAL ANALYSIS INDICATED THAT A MAXIMUM CCW | | TEMPERATURE OF 90øF WOULD ELIMINATE ALL MARGIN ASSOCIATED WITH THE SPENT | | FUEL POOL (SFP) DESIGN ASSUMING A DESIGN FLOW OF 3,000 GPM. | | | | THE FOLLOWING INSPECTION QUESTION WAS ASKED: SINCE A CHANGE IN CCW | | TEMPERATURE WAS REQUIRED TO MEET THE FINAL SAFETY ANALYSIS REPORT (FSAR) | | VALUE OF 160øF FOR THE SFP, WAS A 10 CFR 50.59 UNREVIEWED SAFETY EVALUATION | | PERFORMED? | | | | THE LICENSEE REVIEWED THE CHANGE TO THE PROCEDURE TO LIMIT CCW TEMPERATURE | | TO 90øF. THE LICENSEE CONSIDERED THIS CHANGE TO BE AN ADMINISTRATIVE | | CHANGE ONLY TO LOWER THE ALLOWABLE TEMPERATURE TO THE SFP COOLING HEAT | | EXCHANGER. A 10 CFR 50.59 EVALUATION WAS NOT PERFORMED BECAUSE IT WAS NOT | | RECOGNIZED THAT THE 95øF REQUIREMENT WAS ESSENTIALLY BEING CHANGED. | | | | WITHOUT THE COMPLETION OF AN UNREVIEWED SAFETY QUESTION DETERMINATION, THE | | PLANT WAS IN A CONDITION OUTSIDE THE DESIGN BASIS. THE UNITS ARE NOT | | CURRENTLY IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS | | A RESULT OF THIS ISSUE. | | | | A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE ACTIONS TO INVESTIGATE THIS | | EVENT AND PROVIDE PREVENTIVE ACTIONS. THE 90øF LIMIT IS NO LONGER IN THE | | OPERATING PROCEDURES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32825 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 17:10 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: RANDALL D. SCHERER |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOSE CALVO, NRR EO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |BOB CALDWELL FEMA | | |JOHNS JAUDON, REG 2 IAT | | |EUGENE MCPEEK, NRR IAT | | |JOHN DAVIDSON, NMSS IAT | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DECLARATION OF AN UNUSUAL EVENT DUE TO THE DISCOVERY OF A SUSPECTED | | SABOTAGE DEVICE IN THE TURBINE BUILDING | | | | THE LICENSEE DECLARED AN UNUSUAL EVENT AT 1645 DUE TO THE SECURITY STAFF | | IMPLEMENTING ITS CONTINGENCY PLAN FOR A SUSPECTED SABOTAGE DEVICE IN THE | | TURBINE BUILDING. THE EMERGENCY DECLARATION WAS MADE AS A CONSERVATIVE | | MEASURE UNTIL THE SITUATION CAN BE PROVED OTHERWISE. (REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS.) THE LICENSEE STATED THAT NO SYSTEMS WERE | | EFFECTED, NO INITIATION SIGNALS WERE REQUIRED TO FUNCTION, AND ALL SYSTEMS | | WERE IN THEIR NORMAL CONFIGURATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. AT THE TIME OF THIS NOTIFICATION, IT WAS UNKNOWN | | WHETHER OR NOT A PRESS RELEASE WOULD BE ISSUED. IN ADDITION TO THE | | NOTIFICATIONS REFERENCED ABOVE, THE NRC OPERATIONS CENTER NOTIFIED THE AEOD | | IRD (JOSEPH GIITTER). (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE | | NUMBER.) | | | | * * * 1738 08/26/97 UPDATE FROM SCHERER RECEIVED BY TROCINE * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 1733 FOLLOWING CONFIRMATION | | THAT THE SUSPECTED OBJECT WAS NOT A SABOTAGE DEVICE. (REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE REGION 2 IAT | | (JAUDON), NRR IAT (MCPEEK), NMSS IAT (DAVIDSON), R2DO (FREDRICKSON), NRR EO | | (CALVO), AEOD IRD (GIITTER), AND FEMA (CALDWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32826 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ARCO ENG. & TESTING CONSULTANTS |NOTIFICATION DATE: 08/26/97 | | CITY: MIAMI REGION: 2 |NOTIFICATION TIME: 17:11 [ET]| | COUNTY: DADE STATE: FL |EVENT DATE: 08/26/97 | |LICENSE#: 1622-1 AGREEMENT: Y |EVENT TIME: 16:15[EDT]| | DOCKET: |LAST UPDATE DATE: 08/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PAUL FREDRICKSON RDO | | |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHARLIE ADAMS/FLORIDA BRC | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FLORIDA BUREAU OF RADIATION CONTROL REPORTED THAT A TROXLER GAUGE OWNED | | BY ARCO ENGINEERING & TESTING CONSULTANTS WAS STOLEN FROM A CONSTRUCTION | | SITE LOCATED IN MIAMI, FLORIDA. | | | | AT APPROXIMATELY 1615, IT WAS DISCOVERED THAT A TROXLER GAUGE (MODEL 3411B, | | SERIAL NUMBER 15395) WAS STOLEN FROM A CONSTRUCTION SITE LOCATED IN MIAMI, | | FLORIDA. THE GAUGE WAS INSIDE ITS CASE, AND THE CASE WAS CHAINED TO A | | VEHICLE LOCATED AT THE CONSTRUCTION SITE. APPARENTLY, THE CHAIN WAS CUT, | | AND THE GAUGE WAS STOLEN BETWEEN 1600 AND 1615. | | | | THE METRO DADE POLICE DEPARTMENT IS INVESTIGATING THIS EVENT. | | | | THE GAUGE CONTAINED 8 MILLICURIES OF CESIUM-137 AND 40 MILLICURIES OF | | AMERICIUM-241/BERYLLIUM. | | | | (REFER TO THE HOO LOG FOR A FLORIDA BUREAU OF RADIATION CONTROL CONTACT | | TELEPHONE NUMBER, A LICENSEE CONTACT NAME AND TELEPHONE NUMBER, AND THE | | CONSTRUCTION SITE STREET ADDRESS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32827 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 18:52 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 15:33[CDT]| |NRC NOTIFIED BY: RICK PARLATO |LAST UPDATE DATE: 08/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE LOW SUCTION PRESSURE TRIPS FOR THREE OF FOUR AUXILIARY | | FEEDWATER PUMPS ARE POWERED FROM THE SAME DC SOURCE | | | | ON AUGUST 26, 1997, IT WAS DETERMINED THAT THE LOW SUCTION PRESSURE TRIPS | | FOR AUXILIARY FEEDWATER PUMPS P-38A, 1P-29, AND 2P-29 ARE POWERED FROM THE | | SAME DC SOURCE (D-17). PUMPS P-38B, 1P-29, AND 2P-29 ARE POWERED FROM DC | | SOURCE D-19, AND THE INSTRUMENT LOOP POWER SUPPLIES FOR P-38A, 1P-29, AND | | 2P-29 COME FROM D-03. THEREFORE, A LOSS OF D-03, D-17, OR D-19 COULD | | DISABLE THE LOW SUCTION PRESSURE TRIPS. COMBINED WITH A TORNADO OR SEISMIC | | EVENT WHICH DISABLES THE CONDENSATE STORAGE TANKS, THREE OF THE FOUR | | AUXILIARY FEEDWATER PUMPS COULD BE DAMAGED. | | | | UNIT 1 IS NOT IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION | | AS A RESULT OF THIS ISSUE BECAUSE IT IS CURRENTLY IN A COLD SHUTDOWN | | CONDITION. AN OPERABILITY DETERMINATION FOR UNIT 2 (WHICH IS CURRENTLY | | OPERATING AT APPROXIMATELY 100% POWER) IS BEING PERFORMED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+