U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/23/98 - 04/24/98 ** EVENT NUMBERS ** 34101 34121 34122 34123 34124 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/19/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 15:55 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/19/98 | +------------------------------------------------+EVENT TIME: 14:04[CDT]| |NRC NOTIFIED BY: DAN RAGAN |LAST UPDATE DATE: 04/23/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO COMPUTER FUNCTIONS. | | | | THE LICENSEE DISCOVERED A SAFEGUARDS SYSTEM DEGRADATION TO COMPUTER | | FUNCTIONS AND HAS TAKEN IMMEDIATE COMPENSATORY MEASURES. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | | | | REFER TO HOO LOG FOR ADDITIONAL DETAILS. | | | | * * * 1239EDT 4/23/98 FROM CHARLES WILLIAMSON TO S. SANDIN * * * | | | | THE RESULTS OF A SECURITY INVESTIGATION CONCLUDED THAT THE SECURITY SYSTEM | | COMPUTER WAS IN OPERATION UNTIL 1425EDT AND THAT COMPENSATORY MEASURES WERE | | IMPLEMENTED BY 1431EDT WHICH IS WITHIN THE 10 MINUTES ALLOWED BY THE | | SECURITY PLAN. THE LICENSEE IS RETRACTING THIS REPORT AND WILL DOCUMENT | | THE RESULTS IN THE QUARTERLY SECURITY LOG. THE LICENSEE DISCUSSED THIS | | EVENT WITH REGION III AND WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R3DO(GAVULA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34121 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 04/23/98 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 20:09 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/23/98 | +------------------------------------------------+EVENT TIME: 18:40[CDT]| |NRC NOTIFIED BY: EDWARD RAY |LAST UPDATE DATE: 04/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION INVOLVING OPERABILITY OF THE | | ATMOSPHERIC RELIEF VALVES (ARV) WHERE THE UPDATED SAFETY ANALYSIS REPORT | | (USAR) IS MORE LIMITING THAN THE TECHNICAL SPECIFICATION (TS) REQUIREMENTS. | | | | THE FOLLOWING IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE LIMITING STEAM GENERATOR TUBE RUPTURE (SGTR) ANALYSIS ASSUMES THAT AT | | LEAST 2 ARVs ON INTACT STEAM GENERATORS WILL BE AVAILABLE TO PERFORM THE | | REQUIRED POST TRANSIENT COOLDOWN. THE LIMITING USAR ANALYSIS ASSUMES A | | SINGLE FAILURE IN THE AFW CONTROLLER SUCH THAT EXCESSIVE AFW IS FED TO THE | | FAULTED STEAM GENERATOR. THIS ANALYSIS RESULTS IN OVERFILL OF THE RUPTURED | | STEAM GENERATOR, WATER FLOW THROUGH A SAFETY VALVE, AND A CONSEQUENTIAL | | FAILURE OF THE SAFETY VALVE TO RECLOSE (ASSUMED TO STICK OPEN 5 PERCENT). | | FOR THIS CASE, 2 ARVs ON INTACT LOOPS WOULD BE AVAILABLE FOR COOLDOWN. | | | | "HOWEVER, WITH ONE ARV OUT-OF-SERVICE AS CURRENTLY ALLOWED BY TECHNICAL | | SPECIFICATION 3.7.1.6, AND ASSUMING THE ANALYSIS SINGLE FAILURE OF 1 ARV ON | | AN INTACT LOOP (IN PLACE OF THE FAILURE IN THE AFW CONTROLLER), ONLY 1 ARV | | IS LEFT ON AN INTACT LOOP TO PERFORM THE POST TRANSIENT COOLDOWN (i.e., THE | | 4th ARV IS ON THE RUPTURED SG). HAVING ONLY 1 ARV USED FOR THE COOLDOWN | | SIGNIFICANTLY LENGTHENS THE TIME TO REACH RHR CUT IN CONDITIONS AND TO | | TERMINATE THE TRANSIENT. THE RESULT OF THE DELAY BEFORE REACHING RHR | | CUT-IN CONDITIONS, AND THEREBY TERMINATING THE TRANSIENT, IS AN INCREASE IN | | RADIOLOGICAL DOSE. | | | | "FOR THIS SCENARIO, THE CURRENT USAR ANALYSIS OF RADIOLOGICAL DOSES MAY NOT | | BE BOUNDING. THIS CONDITION MUST BE EVALUATED. | | | | "THE CURRENT TECHNICAL SPECIFICATION 3.7.1.6 STATES, 'AT LEAST THREE STEAM | | GENERATOR ATMOSPHERIC RELIEF VALVE (ARV) SHALL BE OPERABLE.' THEREFORE, | | FOR 1 ARV OUT-OF-SERVICE, NO ACTION IS REQUIRED. FOR 2 ARVs | | OUT-OF-SERVICE, THE LCO REQUIRES THAT AT LEAST 1 OF THE 2 INOPERABLE VALVES | | BE RESTORED TO SERVICE WITHIN 7 DAYS. WITH 3 ARVs OUT-OF-SERVICE, THE LCO | | REQUIRES THAT 1 INOPERABLE ARV BE RESTORED TO SERVICE WITHIN 24 HOURS. | | | | "CURRENTLY, ALL 4 STEAM GENERATOR ARVs ARE OPERABLE. IN THIS CONDITION THE | | USAR ANALYSIS BOUNDS CURRENT PLANT OPERATING CONDITIONS SINCE AT LEAST 2 | | ARVs WOULD BE AVAILABLE ON INTACT STEAM GENERATORS TO PERFORM THE POST | | TRANSIENT COOLDOWN FOLLOWING A STEAM GENERATOR TUBE RUPTURE EVENT. | | | | "AS AN INTERIM MEASURE, OPERATIONS HAS IMPLEMENTED ADMINISTRATIVE CONTROLS | | THROUGH AN OPERATIONS ESSENTIAL READING TO INDICATE THAT TS LCO 3.7.1.6 BE | | MET BY HAVING 4 OPERABLE ARVs (VERSUS 3 REQUIRED BY THE TS) AND, THEREBY, | | THAT THE APPROPRIATE ACTIONS WOULD BE ENTERED FOR ANY ARV BEING | | INOPERABLE." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #34123 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34122 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/23/98 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 20:42 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/23/98 | +------------------------------------------------+EVENT TIME: 19:50[EDT]| |NRC NOTIFIED BY: THOMAS J. CHWALEK |LAST UPDATE DATE: 04/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 91 POWER OPERATION | 91 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 ENTERED AND EXITED TECHNICAL SPECIFICATION 3.0.3 AFTER IDENTIFYING | | THAT VARIOUS DIVISION 2 EQUIPMENT SWITCHGEAR CABINETS DID NOT HAVE SAFETY | | RELATED DOGGING MECHANISMS INSTALLED. | | | | "NON-SAFETY RELATED DOGGING MECHANISMS WERE FOUND TO BE INSTALLED IN | | VARIOUS EMERGENCY SWITCHGEAR DOORS DURING AN INSPECTION BY NIAGARA MOHAWK | | PERSONNEL. THE DOGGING MECHANISMS ARE DESIGNED TO ENSURE THE SWITCHGEAR | | DOORS ARE PROPERLY SEISMICALLY LATCHED AND ARE REQUIRED FOR SWITCHGEAR | | OPERABILITY. REPAIRS ARE BEING EFFECTED AS THE DEVIATIONS ARE IDENTIFIED | | THROUGH ON-GOING INSPECTIONS. EQUIPMENT AFFECTED THAT HAS BEEN IDENTIFIED | | TO DATE IS AS FOLLOWS: | | | | 2ENS*SWGR103-5, 2RHS*P1C SUPPLY BREAKER, 2ENS*SWGR103-11, 2SWP*P1B SUPPLY | | BREAKER, 2ENS*SWGR103-12, 2RHS*P1B SUPPLY BREAKER, 2ENS*SWGR103-14, | | DIVISION 2 EMERGENCY DIESEL GENERATOR OUTPUT BREAKER, 2ENS*SWGR103-13, | | 2NJS-OS3 SUPPLY BREAKER, 2ENS*SWGR103-15, SPARE AND METERING FOR THE | | DIVISION 2 SWITCHGEAR, 2ENS*SWGR103-3, METERING RELAYS FOR THE DIVISION 2 | | SWITCHGEAR | | | | "THIS CONDITION IS BEING IDENTIFIED AS BEING OUTSIDE THE DESIGN BASIS OF | | THE PLANT DUE TO THE APPARENT EXTENSIVE LENGTH OF TIME THE CONDITION IS | | BELIEVED TO HAVE EXISTED." | | | | THE LICENSEE ENTERED TS 3.0.3 AT 2010EDT AFTER DECLARING NUMEROUS DIVISION | | 2 EQUIPMENT INOPERABLE. INSPECTION AND REPAIR OF ALL AFFECTED DIVISION 2 | | DOGGING MECHANISMS WAS COMPLETED AT 2030EDT AT WHICH TIME TS 3.0.3 WAS | | EXITED. THE LICENSEE IS CONTINUING WITH INSPECTIONS OF DIVISION 1 AND 3 | | SWITCHGEAR WHICH THEY ANTICIPATE COMPLETING IN APPROXIMATELY 2 HOURS. THE | | LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34123 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 04/23/98 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 22:50 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/23/98 | +------------------------------------------------+EVENT TIME: 21:52[CDT]| |NRC NOTIFIED BY: ANTHONY HOLMES |LAST UPDATE DATE: 04/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION INVOLVING OPERABILITY OF THE | | ATMOSPHERIC STEAM DUMP (ASD) VALVES WHERE THE FINAL SAFETY ANALYSIS REPORT | | (FSAR) IS MORE LIMITING THAN THE TECHNICAL SPECIFICATION (TS) REQUIREMENTS. | | | | "CALLAWAY'S FSAR ASSUMES 2 STEAM GENERATOR ATMOSPHERIC DUMP VALVES (ASD) | | WILL BE AVAILABLE TO PERFORM THE REQUIRED POST TRANSIENT COOLDOWN. HOWEVER, | | WITH 1 ASD OUT-OF-SERVICE AS CURRENTLY ALLOWED BY THE TS 3.7.1.7 ON AN | | INTACT LOOP AND A SINGLE FAILURE OF ANOTHER ASD ON AN INTACT LOOP WITH A | | STEAM GENERATOR TUBE RUPTURE, THERE WOULD BE ONLY 1 ASD AVAILABLE FOR | | COOLDOWN. THIS WOULD BE OUTSIDE CALLAWAY'S DESIGN BASIS. ON THREE KNOWN | | OCCASIONS (3/21/93, 2/7/94, AND 2/20/94) AN ASD WAS OUT-OF SERVICE FOR | | GREATER THAN SEVEN DAYS. CALLAWAY IS SUBMITTING THIS NOTIFICATION PER | | 10CFR50.72(b)(1)(ii)(B) AS A CONDITION THAT WAS OUTSIDE THE DESIGN BASIS OF | | THE PLANT. A TS CHANGE REQUEST WAS SUBMITTED TO TS 3.7.1.7 LIMITING | | CONDITION OF OPERATION (LCO) AND OPERATING LICENSE (OL) AMENDMENT #1177 | | CONVERSION TO IMPROVED TS (ITS) TO CHANGE THE REQUIREMENT OF OPERABLE ASDs | | FROM 3 TO 4. WE ARE ADMINISTRATIVELY CONTROLLING 4 OPERABLE ASDs UNTIL TS | | 3.7.1.7 IS CHANGED. CALLAWAY IS CURRENTLY IN MODE 6 IN A REFUELING OUTAGE, | | AND THE APPLICABILITY OF TS 3.7.1.7 IS MODES 1 THROUGH 3." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #34121 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34124 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/24/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 05:40 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/24/98 | +------------------------------------------------+EVENT TIME: 04:25[EDT]| |NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 04/24/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 +------------------------------------------------------------------------------+ | PERIPHERAL FUEL BUNDLE CHANNEL FASTENER DISCOVERED IN INCORRECT POSITION. | | | | IN THE COURSE OF DOING CONTROL ROD BLADE CHANGE OUT, IT WAS NOTICED THAT A | | PERIPHERAL BUNDLE CHANNEL FASTENER (SINGLE BUNDLE ON THE OUTSIDE OF THE | | CORE AT LOCATION 29-04) WAS NOT POINTED OUT FROM THE CORE. THE FUEL BUNDLE | | HAD BEEN MOVED EARLIER IN THIS REFUELING OUTAGE. THE LICENSEE DISCOVERED | | THAT THE FUEL MOVEMENT SHEET, WHICH DIRECTS THE REFUELERS WHERE TO PLACE | | AND POSITION THE FUEL BUNDLE, WAS IN ERROR. REACTOR ENGINEERING HAD | | DEVELOPED AND REVIEWED THE FUEL MOVEMENT SHEET BEFORE IT WAS USED. | | | | ALL REFUEL BRIDGE ACTIVITIES HAVE BEEN STOPPED, AND AN INVESTIGATION INTO | | THIS PROBLEM IS BEING PERFORMED. THE LICENSEE SAID THAT PRIOR TO EXITING A | | REFUELING OUTAGE, ALL THE FUEL BUNDLES WOULD HAVE BEEN RECHECKED TO MAKE | | SURE THAT THEY WERE IN THEIR PROPER LOCATION AND PROPER ORIENTATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+