U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/13/1998 - 11/16/1998 ** EVENT NUMBERS ** 34208 35026 35027 35028 35029 35030 35031 35032 35033 35034 35035 35036 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 34208 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 05/11/1998| | UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 20:00[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/11/1998| +------------------------------------------------+EVENT TIME: 08:00[EDT]| | NRC NOTIFIED BY: BRISSON |LAST UPDATE DATE: 11/13/1998| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON RDO | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 85 Power Operation |85 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE BARRIER SEALING DEVICES HAVE BEEN DETERMINED TO BE INOPERABLE. | | | | THE SELECTED LICENSEE COMMITMENT(SLC) 16.9-5, "FIRE BARRIER PENETRATIONS" | | REQUIRES THAT ALL FIRE BARRIERS AND ALL SEALING DEVICES IN FIRE BARRIER | | PENETRATIONS SHALL BE OPERABLE WHEN THEY SEPARATE: | | 1. SAFETY FROM NON-SAFETY RELATED AREAS, | | 2. REDUNDANT ANALYZED POST FIRE SAFE SHUTDOWN EQUIPMENT, | | 3. THE CONTROL COMPLEX (CONTROL ROOM, CABLE ROOMS AND BATTERY ROOMS) FROM | | THE REMAINDER OF THE PLANT, OR | | 4. CONTAINMENT FROM NON-CONTAINMENT AREAS. | | | | DURING THE TRIENNIAL FIRE PROTECTION AUDIT, SEVERAL PROBLEMS WERE | | DISCOVERED WITH PENETRATION SEALS IN COMMITTED FIRE BARRIERS. A | | PENETRATION SEAL IN A WALL SEPARATING TWO TRAINS OF COMPONENT COOLING WATER | | PUMPS WAS FOUND TO HAVE A THROUGH-WALL GAP. SEPARATELY, SIXTY OF THE | | PENETRATION SEALS IN THE CONTROL ROOM FLOOR WERE FOUND TO HAVE AN | | INADEQUATE DEPTH OF FOAM. | | | | AS AN IMMEDIATE CORRECTIVE MEASURE, THE AFFECTED SEALS WERE PLACED UNDER A | | FIRE WATCH AS REQUIRED BY SLC 16.9-5. IN ADDITION, THEY ARE INSPECTING | | ADDITIONAL PENETRATION SEALS OF SIMILAR CONFIGURATION. A RANDOM SAMPLING | | IS BEING CONDUCTED FOR THOSE SEALS ASSOCIATED WITH THE COMPONENT COOLING | | WATER PUMPS. ALL FLOOR SEALS IN COMMITTED FLOOR BOUNDARIES ASSOCIATED WITH | | THE CONTROL ROOM ARE BEING INSPECTED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * UPDATE 1519 5/19/98 FROM ORR TAKEN BY STRANSKY * * * | | | | ON MAY 18, ADDITIONAL FOLLOW-UP INSPECTIONS OF FLOOR PENETRATION SEALS OF | | SIMILAR CONFIGURATIONS DISCOVERED DURING THE TRIENNIAL FIRE PROTECTION | | AUDIT WERE COMPLETED. ALL PENETRATIONS THAT CONSISTED OF EMBEDDED SLEEVES | | IN COMMITTED FIRE BARRIERS WERE INSPECTED. TWENTY-FOUR ADDITIONAL | | PENETRATIONS THROUGHOUT THE PLANT WERE DISCOVERED TO HAVE INADEQUATE DEPTH | | OF FOAM AND ARE THEREFORE INOPERABLE. FIRE WATCHES HAVE BEEN ESTABLISHED | | PER SELECTED LICENSEE COMMITMENT 16.9.5, FIRE BARRIER PENETRATIONS. | | ADDITIONAL INSPECTIONS OF COMMITTED FIRE BARRIER WALL PENETRATION SEALS ARE | | STILL IN PROGRESS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED | | R2DO (SHYMLOCK). | | | | * * * UPDATE 1732 11/13/98 FROM C. ORR TAKEN BY MACKINNON* * * | | | | FOLLOW-UP INSPECTIONS OF A SAMPLE OF WALL PENETRATIONS HAS REVEALED | | ADDITIONAL EXAMPLES OF THROUGH WALL GAPS IN SIX PENETRATIONS INSPECTED. AS | | A CONSERVATIVE MEASURE, ALL PENETRATIONS OF THIS TYPE WERE DECLARED | | INOPERABLE AND FIRE WATCHES ESTABLISHED. THESE PENETRATIONS WILL BE | | INSPECTED AND REPAIRED, AS NECESSARY. R2DO (CAUDLE JULIAN) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35026 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 11/12/1998| | UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 19:00[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/12/1998| +------------------------------------------------+EVENT TIME: 17:00[EST]| | NRC NOTIFIED BY: Julius Bryant |LAST UPDATE DATE: 11/13/1998| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 24 hour report required by Facility Operating Licenses - voids discovered in | | the foam sealant used in penetrations. | | | | McGuire Nuclear Station determined that provisions of their fire protection | | program had not been maintained as required by conditions C. (4) [Unit 1] | | and C. (7) [Unit 2] of the Facility Operating Licenses. | | | | Selected Licensee Commitment 16.9-5 requires that all fire rated assemblies | | and sealing devices separating (1) Safety from non-safety related areas, | | (2) Redundant analyzed post fire safe shutdown equipment or, (3) The Control | | Complex (Control Rooms, and Battery Rooms) from the remainder of the plant | | or, (4) Containment from non-containment areas shall be operable. Contrary | | to this, numerous fire barrier penetrations designed to satisfy the above | | separation criteria were determined to be inoperable when inspections | | identified voids in the foam sealant used in the penetrations. Remedial | | actions required by Selected Licensee Commitment 16.9-5 have been | | implemented (fire watches). The Standby Shutdown System was not affected by | | this alignment, therefore McGuire did not operate outside the design basis | | of the plant. | | | | A follow-up written report will be issued within 14 days. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | * * *Update on 11/13/98 at 1448ET by Tim Heafner taken by John MacKinnon* * | | * | | | | It was discovered at 1300 hours on 11/13/98 that two of the affected | | penetrations did not have fire watches in place as required by the Fire | | Protection Program. | | | | Firewatches are now in place on these two penetrations. The written report | | for this notification will address the failure to properly establish fire | | watches on those two penetrations. The plant Safe Shutdown Facility remains | | unaffected, therefore the plant has not operated outside its design basis. | | R2DO (Caudle Julian) notified. | | | | The NRC Senior Resident Inspector was notified of this event update. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35027 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/13/1998| | UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 09:00[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 11/13/1998| +------------------------------------------------+EVENT TIME: 09:00[EST]| | NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 11/13/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 | |10 CFR SECTION: | | |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 N 0 Hot Standby |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Plant shutdown required by Technical Specifications. | | | | At 0915 on 11/12/98, the unit entered Technical Specification (TS) 3.8.1.1, | | due to overheating of an offsite electrical supply bus (the main | | transformer). TS 3.8.1.1 requires that two offsite electrical supplies be | | available. The unit reduced power and subsequently entered Hot Standby at | | 2007 on 11/12/98. The licensee determined that repairs to the main | | transformer could not be completed within the time of the TS Action | | Statement. Due to the inability to restore a second source of offsite | | power, TS 3.8.1.1 requires the unit to be in Cold Shutdown within 30 hours | | (from 0915 11/13/98). | | | | The licensee stated that the reportability of this event was determined | | after a review of examples contained in NUREG-1022, Revision 1, since the | | unit had been voluntarily placed into Hot Standby. The NRC resident | | inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35028 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 11/13/1998| | UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 10:00[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/13/1998| +------------------------------------------------+EVENT TIME: 09:00[EST]| | NRC NOTIFIED BY: KELLEY |LAST UPDATE DATE: 11/13/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A contract supervisor tested positive for marijuana use during a random test | | performed on 11/09/98. The results were received and reviewed by the Medical | | Review Officer at 0915 on 11/13/98. The licensee is reviewing work | | supervised by this individual, and plans to search the individual's work | | area. The NRC resident inspector will be informed of this event by the | | licensee. Refer to the HOO logbook for additional details. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35029 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | LICENSEE: H. C. NUTTING |NOTIFICATION DATE: 11/13/1998| | CITY: Cincinnati REGION: 3 |NOTIFICATION TIME: 13:00[EST]| | COUNTY: Hamilton STATE: OH |EVENT DATE: 11/13/1998| |LICENSE#: 34-18882-01 AGREEMENT: N |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/13/1998| | +-----------------------------+ | |PERSON ORGANIZATION | | |GEOFFREY WRIGHT R3 | | |Don Cool, NMSS EO | +------------------------------------------------+ | | NRC NOTIFIED BY: Harold Widener | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A Troxler Moisture Density gauge was run over by a Sheepfoot Compactor at a | | work site outside of Cincinnati, OH. , Radiation surveys of the damaged | | gauge indicate that the sources were not damaged. | | | | The Acting Radiation Safety Officer for H. C. Nutting company relayed the | | following information. | | | | | | On 11/13/98 around 0900 hours a Sheepfoot Compactor accidentally ran over a | | Troxler Moisture Density gauge (Model # 3411B & Serial # 10792). The gauge | | contained one 8.8mCi Cs-137 source and one 40.0 mCi Am-Be source. | | The guide rod was broken from the gauge and its yellow casing was scuffed | | when it was run over by the Compactor. A radiation level of 1.8Rem/hr at | | 12" from the gauge was measured (within expected levels). After the initial | | survey was completed the source rod for the Troxler Moisture gauge was | | returned to its safe position and the gauge was again surveyed. The | | radiation level of the gauge from 18" was less than 1 mRem/hr. The Troxler | | Moisture Density gauge was returned to its transfer case and locked in the | | back of a vehicle. The gauge will be taken back to the licensee's main | | office and a leak test and a wipe test will be performed on the gauge. The | | data from the leak test and the wipe test will be sent to Troxler later | | today, (11/13/98), for evaluation. | | | | NRC Region 3 (Kevin Null) was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35030 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | LICENSEE: COLTEC INDUSTRIES |NOTIFICATION DATE: 11/13/1998| | CITY: Beloit REGION: 3 |NOTIFICATION TIME: 15:00[CST]| | COUNTY: STATE: WI |EVENT DATE: 11/13/1998| |LICENSE#: AGREEMENT: N |EVENT TIME: 14:00[CST]| | DOCKET: |LAST UPDATE DATE: 11/13/1998| | +-----------------------------+ | |PERSON ORGANIZATION | | |GEOFFREY WRIGHT R3 | | |VERN HODGE NRR | +------------------------------------------------+ | | NRC NOTIFIED BY: James Golding | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Coltec Industries, Fairbanks Engine Division (FMED) became aware of a | | potential safety hazard associated with the wrist pin assemblies of FM-Alco | | 251 engines. Only affects Palisades Nuclear Power Plant. | | | | 10 CFR PART 21 REPORT | | | | On November 11, 1998, Coltec Industries, Fairbanks Engine Division (FMED), | | became aware of a potential safety hazard associated with the wrist pin | | assemblies for FM-Alco 251 engines. The wrist pin assembly consists of a | | wrist pin and a sleeve fitted in the bore of the wrist pin and held in place | | by rolling each end which causes a tight friction fit. The sleeves of the | | subject wrist pin assemblies were supplied with an incorrect material, | | which is not suitable for rolling - expansion. Therefore, the friction fit | | between the pin and the sleeve may not be sufficient, which could cause the | | sleeve to become loose and possibly contact the liner. | | | | Corrective actions have been taken to prevent recurrence, which includes no | | longer using the supplier of the defective wrist pin, and retraining the | | Receipt Inspectors and the Quality Assurance Supervisor to perform proper | | inspections and reviews of certifications. | | | | Consumers Power - Palisades is the only utility, which received a total of | | 36 wrist pin assemblies between 1995 and 1996. It should be noted that no | | failures have occurred to date and the problems with the wrist pin | | assemblies occurred in commercial applications after many thousands of hours | | of cyclic operation. FM-Alco 251 engines in nuclear applications are not | | typically subjected to this type of operation. However, it is recommended | | that the subject pins be replaced with pin assemblies made with the correct | | sleeve material. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35031 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 11/13/1998| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 15:00[CST]| | RXTYPE: [1] W-2-LP |EVENT DATE: 11/13/1998| +------------------------------------------------+EVENT TIME: 14:00[CST]| | NRC NOTIFIED BY: G Harrington |LAST UPDATE DATE: 11/13/1998| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 | |10 CFR SECTION: | | |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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Leak rate test could not be quantified. | | | | During the leak test of the containment sump recirculation piping the | | leakage past one of the isolation valves (SI-5B, RWST to SI pump B) could | | not be quantified. The leakage past the valve exceeded the capacity of the | | hydro pumps used to perform the test. As a result the test volume could not | | be pressurized. The combined capacity of the pumps is approximately 1 gpm. | | The total allowed leakage through all of the valves per the procedure is 3 | | gpm. The 3 gpm limit is based on ensuring control room doses stay within | | USAR assumptions. The cause of the failure will be determined during the | | corrective maintenance activities. | | | | The NRC Resident Inspector was notified of this event by the Licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35032 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/13/1998| | UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:00[CST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/13/1998| +------------------------------------------------+EVENT TIME: 17:00[CST]| | NRC NOTIFIED BY: W CUMBEE |LAST UPDATE DATE: 11/16/1998| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Planned removal of power from the Emergency Operations Facility (EOF). | | | | Farley Nuclear Plant's Emergency Operations Facility has been declared | | inoperable due to a planned maintenance activity that removes all electrical | | power from the facility. As a compensatory measure the on-call staff from | | the EOF has been directed to proceed to and use the Alternate EOF if a | | plant emergency requires activation of the EOF. All functions of emergency | | assessment, communications and off site response will be maintained operable | | during the entire outage. It is anticipated that power and full EOF | | function will be restored within 24 to 60 hours. | | | | The NRC Resident Inspector was notified of this event by the Licensee. | | | | * * * Update 0139EST on 11/16/98 from Doug Hawkins to S.Sandin * * * | | | | The EOF was declared operable at 2239CST on 11/15/98 after completion of the | | planned maintenance. Notified R2DO (Julian). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35033 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/14/1998| | UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 12:00[CST]| | RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/14/1998| +------------------------------------------------+EVENT TIME: 09:00[CST]| | NRC NOTIFIED BY: SAULSBERRY |LAST UPDATE DATE: 11/14/1998| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ELMO COLLINS R4 | |10 CFR SECTION: | | |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 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Offsite notification made to Arkansas Department of Health informing them | | that a non-employee fishing in their discharge canal suffered an apparent | | heart attack. | | | | | | A courtesy notification was made to the Arkansas Department of Health at | | 1042 CST on 11/14/98 to report a potentially newsworthy event involving a | | medical emergency at Arkansas Nuclear One. A non-employee fishing at the | | discharge canal suffered an apparent heart attack and was transported | | offsite by a local ambulance to Saint Mary's Hospital. First aid was | | rendered by trained site personnel. | | | | The NRC Resident Inspector will be notified by the licensee of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35034 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | LICENSEE: MAXIM TECHNOLOGY, AZ |NOTIFICATION DATE: 11/14/1998| | CITY: Phoenix REGION: 4 |NOTIFICATION TIME: 14:00[MST]| | COUNTY: STATE: AZ |EVENT DATE: 11/14/1998| |LICENSE#: AGREEMENT: Y |EVENT TIME: 09:00[MST]| | DOCKET: |LAST UPDATE DATE: 11/14/1998| | +-----------------------------+ | |PERSON ORGANIZATION | | |ELMO COLLINS R4 | | |JOHN GREEVES NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: Linda Collins | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Troxler Moisture Density Gauge (Model # 3411B) in the open bed of the truck | | was stolen. | | | | An employee of Maxim Technology arrived home last night around 0200 MST in | | her truck and parked the truck. This morning (11/14/98) between the hours | | of 0900 & 1000 MST she discovered that her truck had been stolen from the | | front of her house. The gauge had been locked and a chain lock had been | | locked around the handle of the case to the bed of the truck. The serial | | number of the Troxler moisture density gauge is 16225. The Maxim Technology | | employee reported the theft to the Phoenix Police Department. The Radiation | | Safety Officer for Maxim Technology was notified, around 1300 MST, of this | | event and he will notify the state of Arizona of the stolen moisture density | | gauge. | | | | See HOO log book for names and phone numbers. | | | | * * * Update by the Phoenix Police Department taken by MacKinnon* * * | | | | An officer from the Phoenix Police Department called and stated that the | | Troxler moisture density gauge was stolen from the back of the truck and | | that the truck had not been stolen. The Phoenix Police Department was | | provided the 24- hour phone number for the Arizona Radiation Regulatory | | Agency. R4DO (Elmo Collins), NMSS EO (John Greeves) and NMSS EO (Fred Combs) | | notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35035 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/15/1998| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 11:00[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 11/15/1998| +------------------------------------------------+EVENT TIME: 09:00[EST]| | NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 11/15/1998| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 95 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Reactor scram caused by a main turbine trip due to an apparent high level on | | the moisture separator drain tanks. | | | | While performing a tagging evolution on the "A" feedwater heater string, the | | main turbine tripped due to an apparent high level on the moisture separator | | drain tanks. The main turbine trip signal at greater than 30% power | | provides a trip input to the reactor protection system and a full reactor | | scram ensued. The scram was successful and all rods fully inserted in. The | | low-low set function of the safety relief valves was activated due to the | | subsequent high pressure spike. The logic was reset following the turbine | | trip and bypass valves were controlling pressure at this time. All three | | feedwater strings and # 1 & # 2 feedwater heaters isolated which led to a | | feedpump trip during recovery. These heaters were reset and the feedpumps | | were reset for normal level control. No emergency core cooling systems were | | initiated or challenged during this evolution. Two safety relief valves | | momentarily lifted and then reseated. Suppression pool temperature is | | currently 92 degrees F. | | | | The following major equipment was cleared and tagged out of service at the | | time of the trip but did not contribute to the scram. | | 1. The "A" reactor feedpump | | 2. The "BK111" turbine building chiller | | 3. The "A" feedwater heater string #3, 4, 5 & 6 heaters. | | 4. 1-5 500KV breaker | | | | The NRC resident inspector and Lower ALLOWAYS Creek Township were notified | | of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35036 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/16/1998| | UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 04:00[CST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/16/1998| +------------------------------------------------+EVENT TIME: 02:00[CST]| | NRC NOTIFIED BY: DOUG HAWKINS |LAST UPDATE DATE: 11/16/1998| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 88 Power Operation |88 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN UNEXPECTED RUNNING OF ITS LOAD SEQUENCER DURING | | SURVEILLANCE TESTING OF THE STATION SWING EMERGENCY DIESEL GENERATOR (D/G). | | | | "DURING 1-2A D/G 1000KW LOAD REJECTION, THE B2F SEQUENCER RAN AND STARTED | | ENGINEERED SAFEGUARDS FEATURES LOADS. THERE WAS NO VALID SAFETY INJECTION | | (SI) SIGNAL PRESENT AND NO DISCHARGE INTO THE REACTOR COOLANT SYSTEM. THIS | | OCCURRED WHEN A SIMULATED SI SIGNAL WAS INJECTED INTO THE SEQUENCER. AN | | ELECTRICAL JUMPER INSTALLED IN THE SEQUENCER FAILED TO PREVENT THE | | SEQUENCER FROM RUNNING. | | | | "THE 2A RESIDUAL HEAT REMOVAL PUMP STARTED, THE 2A MOTOR DRIVEN AUXILIARY | | FEEDWATER PUMP STARTED, STEAM GENERATOR BLOWDOWN (SGBD) TRIPPED, AND THE 2A | | REACTOR CAVITY HYDROGEN DILUTION FAN STARTED. | | | | "ALL COMPONENTS WERE SECURED AND SGBD RESTARTED. COMPLETED STP-80.2 AND | | RETURNED B2F SEQUENCER TO SERVICE." | | | | THE 1-2A EMERGENCY DIESEL GENERATOR (D/G) IS THE STATION SWING D/G SHARED BY | | BOTH UNITS. IN THE PAST THIS SURVEILLANCE HAD BEEN PERFORMED WITH A | | SIMULATED SI SIGNAL FROM UNIT 1. DUE TO A CONCERN THAT A UNIT 2 SI SIGNAL | | HAD NOT BEEN TESTED, THE SURVEILLANCE TEST PROCEDURE WAS REVISED FOR THIS | | TEST. THE LICENSEE IS INVESTIGATING WHETHER THE ELECTRICAL JUMPER | | LOCATION FOR THE UNIT 2 BASED TEST WAS PROPERLY IDENTIFIED BASED ON AN | | EXAMINATION OF THE D/G CONTROL CIRCUITRY. ALTHOUGH THE RUNNING OF THE LOAD | | SEQUENCER WAS UNEXPECTED, ALL FUNCTIONS AND EQUIPMENT OPERATED PROPERLY. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+