U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/08/97 - 07/09/97 ** EVENT NUMBERS ** 32469 32519 32531 32584 32599 32600 32601 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32469 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/12/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/12/97 | +------------------------------------------------+EVENT TIME: 13:13[CDT]| |NRC NOTIFIED BY: BRIAN GRANT |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF PROCESS COMPUTER | | | | THE LICENSEE REPORTED A LOSS OF THE PROCESS COMPUTER AS REQUIRED BY THE | | DRESDEN REPORTABILITY MANUAL. THE INITIAL ALARM WAS RECEIVED AT 1313 CDT, | | AND THE CAUSE OF THE LOSS IS CURRENTLY UNDER INVESTIGATION. | | | | THE PROCESS COMPUTER SUPPLIES INPUT TO THE SAFETY PARAMETER DISPLAY SYSTEM, | | MOST OF THE THERMAL CALCULATIONS, AND ALL COMPUTER POINTS. AT THIS TIME, | | ALL CONTROL ROOM INDICATIONS AND ALARMS ARE FUNCTIONAL. THE UNITS ARE NOT | | IN TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF | | THIS ISSUE. | | | | THE LICENSE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE ILLINOIS | | DEPARTMENT OF NUCLEAR SAFETY INSPECTOR. | | | | * * * UPDATE AT 1942 ON 7/8/97, FROM CARTER TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. AFTER ADDITIONAL | | REVIEW, DRESDEN HAS DETERMINED THAT LOSS OF THE PROCESS COMPUTER DOES NOT | | CONSTITUTE A MAJOR LOSS OF ASSESSMENT CAPABILITY. THE COMPUTER WAS | | RETURNED TO SERVICE IN JUST OVER ONE HOUR. GUIDANCE PROVIDED BY NUREG 1022 | | STATES THAT A LOSS OF THE SAFETY PARAMETER DISPLAY SYSTEM OR PLANT COMPUTER | | FOR LESS THAN EIGHT HOURS IS NOT CONSIDERED REPORTABLE. | | | | THE HOO NOTIFIED THE R3DO (WRIGHT). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32519 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/20/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 23:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/20/97 | +------------------------------------------------+EVENT TIME: 22:10[EDT]| |NRC NOTIFIED BY: MIKE WILLIAMS |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AHIN 50.72(b)(1)(vi) OTHER HIND TO SAFE OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | 60 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE SUPPRESSION WATER SYSTEM FLOW DID NOT MEET TEST ACCEPTANCE CRITERION. | | | | THE TEST CRITERION IS STATED IN TERMS OF RESISTANCE TO FLOW AND THE SYSTEM | | DEMONSTRATED TOO MUCH RESISTANCE (POTENTIALLY RESULTING IN TOO LOW OF A | | WATER FLOW TO MEET SYSTEM REQUIREMENTS). THE LICENSEE HAD 24 HOURS TO | | RESTORE THE SYSTEM TO OPERABILITY OR ESTABLISH A BACKUP FIRE SUPPRESSION | | WATER SYSTEM. NEITHER ONE OF THESE OPTIONS WAS MET, AND THE 24 HOUR CLOCK | | EXPIRED AT 1800 ON 6/20/97. THE LICENSEE HAS 12 HOURS TO PLACE BOTH UNITS | | IN HOT SHUTDOWN AND AN ADDITIONAL 24 HOURS TO PLACE BOTH UNITS IN COLD | | SHUTDOWN. THESE REQUIREMENTS ARE NOT CONTAINED IN TECHNICAL SPECIFICATIONS | | BUT RATHER IN PLANT PROCEDURES. | | | | ALL ON AND OFFSITE POWER SUPPLIES ARE OPERABLE AS IS ALL EMERGENCY CORE | | COOLING SYSTEM EQUIPMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0616 EDT ON 6/21/97, FROM MIKE WILLIAMS TO S.SANDIN * * * | | | | FURTHER TESTING IDENTIFIED WHICH AREAS WERE AFFECTED BY THE FLOW BLOCKAGES. | | THE AFFECTED AREAS ARE COMPENSATED FOR BY CONTINUOUS FIRE WATCHES AND | | BACKUP FIRE SUPPRESSION. THE LICENSEE TERMINATED THE SHUTDOWN AT 0530 EDT | | WITH BOTH UNITS AT 20% POWER. CURRENT INTENTIONS ARE TO INCREASE POWER | | LATER TODAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (LESSER). | | | | * * * UPDATE AT 1334 ON 7/8/97, FROM TURKAL TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FOLLOWING | | EXPLANATION. THE ORIGINAL CALCULATION WHICH INDICATED THAT THE FLOW | | RESISTANCE WAS TOO HIGH WAS IN ERROR. A SUBSEQUENT CALCULATION SHOWS THAT | | THE FLOW RESISTANCE IS WITHIN SPECIFICATIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R2D0 (URYC). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32531 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 06/23/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 20:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/23/97 | +------------------------------------------------+EVENT TIME: 19:02[EDT]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 2 ENTERED TS 3.0.3 AFTER DECLARING BOTH TRAINS OF EMERGENCY CORE | | COOLING SYSTEM (ECCS) INOPERABLE. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON 6/23/97, A PLANT REVIEW OF THE RESIDUAL HEAT REMOVAL SYSTEM WAS BEING | | CONDUCTED IN PREPARATION FOR AN UPCOMING SCHEDULED NRC SAFETY SYSTEM | | ENGINEERING INSPECTION (SSEI). AS A RESULT OF THIS REVIEW, IT WAS | | DISCOVERED THAT TWO CHECK VALVES, ONE IN THE SAFETY INJECTION SYSTEM AND | | ONE IN THE CHEMICAL AND VOLUME CONTROL SYSTEM, HAD NOT BEEN REVERSE FLOW | | TESTED IN ACCORDANCE WITH THE ASME SECTION XI TEST PROGRAM. | | | | THE AFFECTED VALVES ARE NI-342, WHICH IS A CHECK IN THE LINE BETWEEN | | RESIDUAL HEAT REMOVAL PUMP 'B' AND THE INTERMEDIATE-HEAD SAFETY INJECTION | | PUMPS, AND NV-813, WHICH IS A CHECK VALVE IN THE LINE BETWEEN RESIDUAL HEAT | | REMOVAL PUMP 'A' AND THE HIGH-HEAD CENTRIFUGAL CHARGING PUMPS. | | | | THE SUBJECT VALVES WERE DECLARED INOPERABLE AT 1902 HOURS ON 6/23/97. | | CURRENT PLANS ARE TO TEST THE VALVES WITHIN 24 HOURS PER THE ALLOWANCE FOR | | A MISSED SURVEILLANCE AS STATED IN TECHNICAL SPECIFICATION 4.0.3. | | | | THIS EVENT IS BEING REPORTED UNDER 10CFR50.72(b)(2)(iii)(EVENT OR CONDITION | | THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF SAFETY FUNCTION OF | | SYSTEMS OR STRUCTURES)." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1334 ON 7/8/97, FROM BRISSON TAKEN BY WEAVER * * * | | | | THE LICENSEE COMPLETED TESTING OF THE AFFECTED CHECK VALVES ON 6/24/97. THE | | CHECK VALVES TESTED SATISFACTORILY, AND THEREFORE, THE LICENSEE CONSIDERS | | THAT THE VALVES WERE ALWAYS OPERABLE. THEREFORE, THE LICENSEE IS | | RETRACTING THIS EVENT NOTIFICATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R2DO (URYC). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32584 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/03/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 09:49 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 08:22[CDT]| |NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 95 POWER OPERATION | 95 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF THE PROCESS COMPUTER AND SAFETY PARAMETER DISPLAY SYSTEM DISPLAYS | | DUE TO HIGH COMPUTER ROOM TEMPERATURES. | | | | THE LICENSEE RECEIVED INDICATION OF HIGH COMPUTER ROOM TEMPERATURES, AND A | | LOSS OF THE PROCESS COMPUTER AND SAFETY PARAMETER DISPLAY SYSTEM DISPLAYS | | OCCURRED APPROXIMATELY ONE MINUTE LATER. APPARENTLY, NEITHER THE NORMAL | | OR BACKUP HVAC SYSTEM WAS PROVIDING COOLING TO THE COMPUTER ROOM. THE | | LICENSEE'S INITIAL INVESTIGATION INDICATED THAT THIS WAS A MAJOR CONCERN. | | | | EFFORTS ARE CURRENTLY UNDERWAY TO PROVIDE ADDITIONAL COOLING TO THE | | COMPUTER ROOM FROM ALTERNATE SOURCES, AND THE LICENSEE'S ROOT CAUSE | | INVESTIGATION IS IN PROGRESS. THE LICENSEE ALSO PLANS TO PERFORM | | EVALUATIONS OF THE EFFECTS ON THE COMPUTERS WHEN TEMPERATURES RETURN TO | | NORMAL RANGE. | | | | AT THE TIME OF THIS NOTIFICATION, COMPUTER ROOM TEMPERATURE WAS AT 95øF | | AND DECREASING. THE TEMPERATURE HAD PEAKED AT APPROXIMATELY 98øF. | | | | AT THE PRESENT TIME, THE LICENSEE IS UTILIZING NUMEROUS OTHER METHODS TO | | MONITOR THE STATUS OF UNITS 2 AND 3. THE LICENSEE STATED THAT THERE WERE | | NO PROBLEMS WITH CONTROL ROOM ANNUNCIATORS AND THAT ALL OTHER SYSTEMS WERE | | PERFORMING AS EXPECTED. UNITS 2 AND 3 ARE NOT CURRENTLY IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS EVENT. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY | | STATE OFFICIALS. | | | | * * * UPDATE AT 1942 ON 7/8/97, FROM CARTER TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. AFTER ADDITIONAL | | REVIEW, DRESDEN HAD DETERMINED THAT LOSS OF THE PROCESS COMPUTER DOES NOT | | CONSTITUTE A MAJOR LOSS OF ASSESSMENT CAPABILITY. THE COMPUTER WAS | | RETURNED TO SERVICE IN JUST UNDER FOUR HOURS. GUIDANCE PROVIDED BY NUREG | | 1022 STATES THAT A LOSS OF THE SAFETY PARAMETER DISPLAY SYSTEM OR PLANT | | COMPUTER FOR LESS THAN EIGHT HOURS IS NOT CONSIDERED REPORTABLE. | | | | THE HOO NOTIFIED THE R3DO (WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32599 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/08/97 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/08/97 | +------------------------------------------------+EVENT TIME: 12:51[CDT]| |NRC NOTIFIED BY: JAMES PORTER |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - EMERGENCY FEEDWATER PUMP STARTED | | | | TESTING IN COMBINATION WITH A POWER FAILURE CAUSED AN EMERGENCY FEEDWATER | | PUMP TO START. THE ALPHA CHANNEL OF THE EMERGENCY FEEDWATER | | INSTRUMENTATION & CONTROL (EFIC) SYSTEM WAS BEING BYPASSED TO SUPPORT | | TESTING OF THE REACTOR PROTECTION SYSTEM. AT THE SAME TIME, A LOSS OF | | POWER TO THE DELTA CHANNEL OF EFIC OCCURRED GENERATING A TRIP SIGNAL ON THE | | DELTA CHANNEL. THE EFIC LOGIC SENSED THE LOSS OF POWER AND AUTOMATICALLY | | TOOK THE ALPHA CHANNEL OUT OF BYPASS. SINCE THE ALPHA CHANNEL WAS | | RECEIVING A TRIP SIGNAL FROM THE REACTOR PROTECTION SYSTEM, THE LOGIC WAS | | SATISFIED FOR AN EMERGENCY FEEDWATER ACTUATION. | | | | THE BRAVO EMERGENCY FEEDWATER (EFW) PUMP STARTED AS EXPECTED. THE ALPHA | | PUMP DID NOT START BECAUSE IT WAS OUT OF SERVICE FOR MAINTENANCE. THE | | LICENSEE ENTERED A SIX HOUR LCO FOR THE INOPERABILITY OF BOTH EFW PUMPS | | SHORTLY AFTER THIS EVENT OCCURRED. | | | | THE BRAVO EFW PUMP HAS BEEN SECURED. MAINTENANCE ACTIVITIES ON THE ALPHA | | PUMP HAVE BEEN TERMINATED, AND THE PUMP IS BEING RETESTED. THE LICENSEE | | BELIEVES THE LOSS OF POWER WAS CAUSED BY THE LIGHTNING STRIKES OF A PASSING | | THUNDERSTORM. | | | | THE LICENSEE PLANS TO PERFORM FURTHER TESTING ON THE DELTA CHANNEL OF EFIC | | BEFORE DECLARING IT OPERABLE; HOWEVER, THE LICENSEE EXPECTS TO EXIT THE | | LIMITING CONDITION FOR OPERATION PRIOR TO ITS EXPIRATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32600 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MALINKRODT |NOTIFICATION DATE: 07/08/97 | | CITY: PINEBROOK REGION: 1 |NOTIFICATION TIME: 16:28 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 07/08/97 | |LICENSE#: 29-28064-01 AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PETER ESELGROTH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JASON WILLMAN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PACKAGE RECEIVED WHICH EXCEEDED EXTERNAL RADIATION LIMITS | | | | MALINKRODT OF PINEBROOK, NJ, RECEIVED A PACKAGE FROM THEIR CORPORATE OFFICE | | NEAR ST. LOUIS, MO. THE PACKAGE CONTAINED A Tc-99 GENERATOR AND WAS | | CARRIED BY FEDERAL EXPRESS. THE MAXIMUM ON CONTACT READING OF THE PACKAGE | | WAS 250 mR/hr. THE MAXIMUM RADIATION READING AT 1 METER WAS 11 mR/hr. BOTH | | OF THESE NUMBERS EXCEED THE ALLOWABLE LIMITS OF 200 AND 10 mR/hr, | | RESPECTIVELY. THE ST. LOUIS OFFICE HAS SENT SOMEONE TO NJ TO INVESTIGATE | | THIS EVENT. | | | | THE LICENSEE REPORTED THIS EVENT TO THE OPERATIONS CENTER UNDER 10 CFR | | 20.1906 BECAUSE THE REGIONAL OFFICE WAS CLOSED AT THE TIME THE REPORT WAS | | MADE. (A CONTACT PHONE NUMBER IS AVAILABLE IN THE HOO LOG.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32601 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/08/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:25 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/08/97 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: STEPHEN BAKER |LAST UPDATE DATE: 07/08/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CALCULATED HIGH PRESSURE SAFETY INJECTION FLOW MAY BE NONCONSERVATIVE. | | | | THE UFSAR CHAPTER 14 ANALYSIS STATES THAT IF A COLD LEG LOCA OCCURS, 75% OF | | THE HIGH HEAD FLOW WILL STILL BE DIRECTED TO THE REACTOR VESSEL. NEW | | CALCULATIONS SHOW THAT THIS REMAINING FLOW COULD BE AS LOW AS 50% OF THE | | TOTAL FLOW. THE LICENSEE IS REVIEWING THIS EVENT TO SEE IF THE CHAPTER 14 | | ACCEPTANCE CRITERIA ARE STILL MET. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+