U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/24/96 - 10/25/96 ** EVENT NUMBERS ** 31066 31099 31202 31203 31204 31205 31206 31207 31208 31209 31210 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 09/26/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: JOHN KONOALCHICK |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INTERMEDIATE HEAD SAFETY INJECTION PUMP OPERATED ABOVE ITS MAXIMUM | | ANALYZED RANGE - | | | | WITH BOTH UNITS DEFUELED, THE LICENSEE WAS EVALUATING THE HIGH PRESSURE | | OUTPUT FROM THE UNIT 2 #22 SAFETY INJECTION PUMP. THE LICENSEE DISCOVERED | | THAT THE #22 PUMP OPERATES ABOVE THE MAXIMUM ANALYZED RANGE (PUMP HEAD | | CURVE) AS DETERMINED BY WESTINGHOUSE IN THE SALEM DESIGN BASIS (REF: LCR | | #91-03). | | | | THIS PUMP HAD PREVIOUSLY BEEN INSTALLED IN UNIT 1 AS THE #12 SAFETY | | INJECTION PUMP. WHILE INSTALLED IN UNIT 1, THE #12 SAFETY INJECTION PUMP | | HAD OPERATED ABOVE THE ANALYZED RANGE OF THE WESTINGHOUSE ACCIDENT | | ANALYSIS. | | | | THIS EVENT IS BEING REPORTED AS AN EVENT FOUND WHILE THE REACTOR WAS | | SHUTDOWN. HAD THIS EVENT BEEN DISCOVERED WHILE THE PLANT WAS OPERATING, | | IT WOULD HAVE RESULTED IN THE PLANT, INCLUDING ITS SAFETY BARRIERS, BEING | | IN AN UNANALYZED CONDITION THAT SIGNIFICANTLY COMPROMISED PLANT SAFETY. | | | | LICENSEE SYSTEM ENGINEERING PERSONNEL ARE EVALUATING THE PERFORMANCE OF | | THE #22 SAFETY INJECTION PUMP TO DETERMINE APPROPRIATE CORRECTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND WILL INFORM THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE 1713 10/24/96 FROM PRIESTLY TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. | | | | "FURTHER EVALUATION OF THIS CONDITION DETERMINED THAT THE MAXIMUM FLOW | | DELIVERY FROM THE SAFETY INJECTION PUMPS IN THE 1500 TO 1600 PSI RANGE IS | | USED IN THE LARGE BREAK LOCA PEAK CLAD TEMPERATURE AND MASS/ENERGY RELEASE | | ANALYSIS. FOR THE PEAK CLAD TEMPERATURE ANALYSIS, A CASE WITH MAXIMUM | | SAFEGUARDS FLOW RATES IS RUN TO DEMONSTRATE THAT THE MINIMUM SAFEGUARDS | | CASE IS LIMITING. SINCE THE ANALYSIS DOES NOT SPECIFICALLY MODEL RCS | | PRESSURES IN THE 1400 TO 1600 PSI RANGE, THERE IS NO IMPACT FROM THE | | INCREASED PUMP FLOW IN THIS RANGE. SIMILARLY, THE MODEL FOR THE MASS/ENERGY | | ANALYSIS DOES NOT INCLUDE THIS INTERMEDIATE PRESSURE RANGE AND DOES NOT | | IMPACT THE ACCIDENT ANALYSIS SAFETY INJECTION FLOW RATES ADVERSELY. BASED | | ON FEEDBACK FROM THE VENDOR ANALYSIS, THE PLANT WAS NOT OPERATED IN AN | | UNANALYZED CONDITION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31099 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 10/04/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 20:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 19:35[CDT]| |NRC NOTIFIED BY: MIKE SICARD |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL TO EXCEED EXPOSURE LIMITS IN THE TSC AND THE CONTROL ROOM DURING | | A LOCA | | | | TRAIN "C" HIGH HEAD SAFETY INJECTION (HHSI) DISCHARGE FLUSH LINE VALVE | | SI-0120C HAD EXCESSIVE LEAKAGE WITH THE VALVE CLOSED. THE LEAKAGE DRAINED | | TO THE FUEL HANDLING BUILDING SUMP. ENGINEERING CALCULATIONS VERIFIED THIS | | LEAKAGE COULD HAVE EXCEEDED THE 10 CFR 50 APPENDIX A, GDC 19 LIMITS FOR THE | | TECHNICAL SUPPORT CENTER AND CONTROL ROOM ENVELOPE. THE PERIOD OF CONCERN | | IS DURING THE POST LOSS OF COOLANT ACCIDENT (LOCA) CONTAINMENT | | RECIRCULATION PHASE OF A LARGE BREAK LOCA. | | | | THE VALVE HAS BEEN REPAIRED AND RETESTING IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1210 10/24/96 FROM PINZON TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. A DETAILED DOSE ASSESSMENT | | HAS DETERMINED THAT DOSE LIMITS WOULD NOT BE EXCEEDED. NOTIFIED R4DO | | (VANDENBURGH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 05:00 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 03:19[EDT]| |NRC NOTIFIED BY: MICHAEL BECKER |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP - REACTOR TRIP | | | | AT 0319 ON 10/24/96, UNIT ONE TRIPPED WHEN THE GENERATOR OUTPUT BREAKER | | OPENED DUE TO "GENERATOR NEGATIVE PHASE SEQUENCE". ALL SYSTEMS OPERATED AS | | DESIGNED. ALL THREE AFW PUMPS STARTED ON STEAM GENERATOR LOW LEVEL. STEAM | | GENERATOR LEVEL HAS BEEN RECOVERED AND THE STEAM GENERATORS ARE NOW BEING | | FED BY MAIN FEEDWATER. ALL RODS FULLY INSERTED. STEAM IS BEING DUMPED AS | | NECESSARY TO THE MAIN CONDENSER TO REMOVE DECAY HEAT. | | | | NO OBVIOUS GENERATOR PROBLEM EXISTED TO CAUSE THE GENERATOR TRIP AND THE | | CAUSE OF THE TRIP IS UNDER INVESTIGATION. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31203 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:23 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: JERE FREEMAN |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE WELLING 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 63 POWER OPERATION | 63 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - PRESS RELEASE | | | | OYSTER CREEK ISSUED A PRESS RELEASE AT 1000 AM STATING THAT THE PLANT WENT | | BACK ON LINE AT 7:57 PM ON 10/23/96. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31204 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BABCOCK & WILCOX CO. |NOTIFICATION DATE: 10/24/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 12:47 [ET]| |COMMENTS: AUTHORIZED DECONTAMINATION |EVENT DATE: 10/24/96 | | FACILITY BEING DECOMMISSIONED |EVENT TIME: 00:00[EDT]| | |LAST UPDATE DATE: 10/24/96 | | CITY: APOLLO REGION: 1 +-----------------------------+ | COUNTY: ARMSTRONG STATE: PA |PERSON ORGANIZATION| |LICENSE#: SNM-145 AGREEMENT: N |WELLING RDO | | DOCKET: 07000135 | | +------------------------------------------------+ | |NRC NOTIFIED BY: SGARLATA | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FORMER EMPLOYEE TOOK POSSESSION OF CONTAMINATED EQUIPMENT. | | | | THE LICENSEE REPORTED THAT, APPROXIMATELY ONE WEEK AGO, THE HUSBAND OF A | | FORMER B&W EMPLOYEE RETURNED AN ELECTRIC FLOOR SCRUBBER THAT THE EMPLOYEE | | HAD TAKEN HOME SOME YEARS BEFORE. THE LICENSEE PERFORMED A RADIATION SURVEY | | AND FOUND BOTH REMOVABLE (150 DPM à) AND FIXED (50,000 DPM à, 500,000 DPM | | á) CONTAMINATION ON THE UNIT. THE LICENSEE THEN USED A FILE TO REMOVE A | | SAMPLE OF THE FIXED CONTAMINATION IN ORDER TO PERFORM AN ISOTOPIC ANALYSIS. | | APPROXIMATELY 1.2 GRAMS OF MATERIAL WERE REMOVED FROM THE BASE OF THE | | SCRUBBER, AND THE LICENSEE DETERMINED THAT THE MATERIAL WAS PRIMARILY | | THORIUM AND ENRICHED (18% U-235 BY WEIGHT) URANIUM. THE LICENSEE REPORTED | | THAT, USING THE SUM OF RATIOS METHOD, THIS IS GREATER THAN 1000 TIMES THE | | QUANTITIES SPECIFIED IN 10 CFR PART 20, APPENDIX C. | | | | THE LICENSEE STATED THAT THE SCRUBBER MUST HAVE BEEN TAKEN A NUMBER OF | | YEARS AGO, BECAUSE THE FORMER EMPLOYEE HADN'T BEEN WORKING AT THE FACILITY | | FOR SEVERAL YEARS. THE LICENSEE WILL ATTEMPT TO CONTACT THE EMPLOYEE TO | | DETERMINE WHERE THE UNIT HAD BEEN USED. NRC REGION I (TODD JACKSON) HAS | | BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31205 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/24/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:40 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 14:25[EDT]| |NRC NOTIFIED BY: ROTHGEB |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF INSTRUMENT AIR DURING COLD WEATHER COULD CAUSE REACTOR PLANT CLOSED | | COOLING (CCP) SYSTEM TO EXCEED ALLOWABLE STRESSES. | | | | THE LICENSEE HAS DETERMINED THAT LOSS OF INSTRUMENT AIR, COMBINED WITH LOW | | SERVICE WATER TEMPERATURE, WHILE THE UNIT IS IN COLD SHUTDOWN, COULD RESULT | | IN THE CCP SYSTEM EXCEEDING ALLOWABLE STRESSES. THE CCP SYSTEM TEMPERATURE | | CONTROL VALVES WOULD FAIL OPEN UPON A LOSS OF AIR, CAUSING THE CCP SYSTEM | | TO COOL DOWN BELOW ITS DESIGN TEMPERATURE. THE LICENSEE INTENDS TO MAKE A | | CHANGE TO THE CCP SYSTEM BEFORE THE SERVICE WATER TEMPERATURE DROPS BELOW | | 50øF. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31206 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/24/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 17:10[EDT]| |NRC NOTIFIED BY: STRONG |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CERTAIN MAIN STEAM LINE BREAKS INSIDE CONTAINMENT COULD CAUSE RCS PIPING TO | | EXCEED ALLOWABLE STRESS LEVELS. | | | | THE LICENSEE HAS DETERMINED THAT, DUE TO INADEQUATE SNUBBERS, CERTAIN | | SECTIONS OF RCS PIPING COULD EXCEED THEIR ALLOWABLE STRESS LEVELS AS A | | RESULT OF POSTULATED MAIN STEAMLINE BREAKS INSIDE CONTAINMENT. THE SNUBBERS | | ORIGINALLY INSTALLED ON THESE SECTIONS OF PIPING DO NOT MEET DESIGN | | SPECIFICATIONS. THE LICENSEE PLANS TO MODIFY OR REPLACE THESE SNUBBERS | | BEFORE UNIT RESTART. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31207 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/24/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: WAHLENMAYER |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INTERACTION BETWEEN CONTROL AND PROTECTION FUNCTIONS OF STEAM GENERATOR | | LEVEL CONTROL SYSTEM COULD PREVENT RPS ACTUATION ON LOW-LOW S/G LEVEL. | | | | "AN ENGINEERING REVIEW WAS PERFORMED OF WESTINGHOUSE NUCLEAR SAFETY | | ADVISORY LETTER NSAL-96-004, WHICH ADDRESSES AN IEEE-279 CONCERN WITH | | DESIGNS THAT SHARE A COMMON STEAM GENERATOR TAP FOR STEAM GENERATOR LEVEL | | INSTRUMENTS AND MAIN STEAM FLOW INSTRUMENTS. BVPS UNIT 2 STEAM GENERATOR | | LEVEL INSTRUMENTS 2FWS-LT476, 486 AND 496 SHARE A COMMON STEAM GENERATOR | | TAP WITH STEAM FLOW INSTRUMENTS 2MSS-FT474, 484 AND 494. A POSTULATED | | FAILURE AT THE COMMON TAP, COMBINED WITH A SECOND POSTULATED FAILURE OF A | | SECOND LEVEL INSTRUMENT, AS REQUIRED BY IEEE-279, COULD PREVENT THE RPS | | FROM INITIATING A REACTOR TRIP AND AUXILIARY FEEDWATER (AFW) AUTOMATIC | | START. THIS IS POSTULATED TO OCCUR WHEN AN ACTUAL LOW-LOW LEVEL IS REACHED | | IN THE STEAM GENERATOR WHICH IS CAUSED BY THE STEAM GENERATOR WATER LEVEL | | CONTROL SYSTEM REACTING TO THE STEAM FLOW SIGNAL GENERATED FROM THE FAILED | | TAP, ASSUMING NO OPERATOR ACTION. | | | | THE APPARENT CAUSE OF THIS EVENT WAS INADEQUATE DESIGN REVIEW AND | | EVALUATION DURING THE DESIGN CHANGE WHICH IMPLEMENTED THE ELIMINATION OF | | THE STEAM FLOW/FEED FLOW MISMATCH WITH COINCIDENT LOW LEVEL TRIP AT UNIT 2. | | THE EVALUATION OF NSAL-96-004 HAS DETERMINED THAT THIS CONDITION IS NOT | | APPLICABLE TO BVPS UNIT 1 DUE TO A DIFFERENCE IN DESIGN. CORRECTIVE ACTIONS | | WILL BE TAKEN PRIOR TO UNIT STARTUP." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:54 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 18:35[EDT]| |NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR FLOODING OF RHR PUMPS DURING POSTULATED INTERNAL FLOODING | | EVENT. | | | | THE LICENSEE HAS DISCOVERED TWO CONDITIONS WHICH COULD PERMIT FLOODING OF | | THE RHR PUMPS DURING AN INTERNAL FLOODING EVENT. UNSEALED PIPE PENETRATIONS | | IN THE PRIMARY AUXILIARY BUILDING PROVIDE A DIRECT FLOOD PATH TO THE RHR | | PUMPS. ADDITIONALLY, LOUVERED DOORS, INSTALLED TO PERMIT WATER TO ESCAPE | | FROM THE PRIMARY AUXILIARY BUILDING, ARE LOCATED HIGHER THAN THEIR ORIGINAL | | DESIGN. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 20:45[CDT]| |NRC NOTIFIED BY: ALEXANDER |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSON 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 +------------------------------------------------------------------------------+ | THREE STEAM GENERATORS DECLARED CATEGORY C-3 DURING INSERVICE INSPECTION. | | | | "ON OCTOBER 24, 1996, A STEAM GENERATOR (SG) TUBE INSERVICE INSPECTION WAS | | INITIATED ON BRAIDWOOD UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENT (TSSR) 4.4.5.0. THE INITIAL SAMPLE SIZE OF 100% OF | | ALL AVAILABLE TOP-OF-TUBESHEET ROLL TRANSITIONS WAS SELECTED. | | | | TSSR 4.4.5.2.c REQUIRES THAT THE RESULTS OF EACH SAMPLE INSPECTION BE | | CLASSIFIED INTO ONE OF THREE CATEGORIES. A SG WILL BE CLASSIFIED IN | | CATEGORY C-3 IF MORE THAN 10% OF THE TOTAL TUBES INSPECTED ARE DEGRADED OR | | MORE THAN 1% OF THE INSPECTED TUBES ARE DEFECTIVE. A SG TUBE IS CONSIDERED | | DEFECTIVE IF IT HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 40% NOMINAL | | TUBE WALL. ON OCTOBER 24, 1996, AT 2045 HOURS, THE RESULTS OF THE SAMPLE | | INSPECTION RESULTED IN SG 1A, 1B AND 1D BEING CLASSIFIED INTO CATEGORY C-3 | | BASED ON GREATER THAN 1% OF THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER | | OF INSERVICE TUBES ARE 4029, 4450, AND 4181 FOR THE 1A, 1B AND 1D SGs, | | RESPECTIVELY. THESE TUBES ARE CONSIDERED DEFECTIVE MAINLY DUE TO | | CIRCUMFERENTIAL CRACK-LIKE INDICATION AT THE HOT LEG TOP-OF-TUBESHEET ROLL | | TRANSITION REGION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31210 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/25/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 01:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 01:06[EDT]| |NRC NOTIFIED BY: STEVE ALLISON |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ELINOR ADENSAM EO | | |AUSTIN FEMA | | |BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 79 POWER OPERATION | 79 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT - LOSS OF 25% OF THE CONTROL ROOM ANNUNCIATORS | | | | A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED ON UNIT 2 AT 0106 ON 10/25/96, | | DUE TO A LOSS OF SEVERAL ALARM PANELS; HOWEVER, ALL CONTROL BOARD | | INDICATIONS ARE AVAILABLE AND ARE BEING MONITORED FREQUENTLY. ADDITIONAL | | OPERATORS ARE IN THE CONTROL ROOM TO AID IN THIS TASK. | | | | THE ANNUNCIATOR PROBLEM OCCURRED AT 2310 ON 10/24/96, WHEN AN I&C | | TECHNICIAN ACCIDENTLY GROUNDED ONE OF THE ANNUNCIATOR ALARM LIGHT SOCKETS | | WHILE MAKING A REPAIR. THE SPECIFIC CAUSE FOR THE LOSS OF ANNUNCIATORS HAS | | NOT BEEN DETERMINED; TROUBLESHOOTING IS IN PROGRESS. ABOUT 25 OF THE | | CONTROL ROOM ALARMS INITIALLY LOCKED IN. HOWEVER, FURTHER INVESTIGATION | | REVEALED THAT SOME ALARMS WOULD NOT ACTUATE IF REQUIRED. A TOTAL OF ABOUT | | 25% OF THE CONTROL ROOM ANNUNCIATORS ARE INOPERABLE. | | | | ALL MAJOR SAFETY RELATED EQUIPMENT IS OPERABLE WITH THE FOLLOWING | | EXCEPTIONS, THE "A" TRAIN CONTAINMENT SPRAY PUMP AND ONE OF THREE "A" TRAIN | | COMPONENT COOLING WATER PUMPS. HOWEVER, THE "A" TRAIN CCW SYSTEM IS | | CONSIDERED OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL | | OFFICIALS. | | | | * * * UPDATE AT 0420 ON 10/25/96 BY ROBINSON TAKEN BY WEAVER * * * | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0420. ALL CONTROL ROOM | | ANNUNCIATORS HAVE BEEN RETURNED TO SERVICE. THE HOO NOTIFIED THE | | RDO(LANDIS); EO(ADENSAM); AEOD(BARRETT); FEMA(AUSTIN) | +------------------------------------------------------------------------------+