Event Notification Report for October 25, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/24/2001 - 10/25/2001
** EVENT NUMBERS **
38414 38416 38421 38422 38423 38424 38425
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|General Information or Other |Event Number: 38414 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 10/22/2001|
|LICENSEE: QTE GROUP, INC. |NOTIFICATION TIME: 12:00[EDT]|
| CITY: GARLAND REGION: 4 |EVENT DATE: 09/29/2001|
| COUNTY: STATE: TX |EVENT TIME: 08:30[CDT]|
|LICENSE#: L05222 AGREEMENT: Y |LAST UPDATE DATE: 10/22/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS (via fax) | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE |
| |
| The following is a portion of a fax received from the Texas Department of |
| Health: |
| |
| "On the morning of September 29, 2001, [a] QTE technician picked up Troxler |
| Gauge [Model 3440] SN:30229 from office to perform test on a project in |
| Garland at 8:30 a.m. On his way to project he realized that he forgot his |
| wallet and returned home to pick it up. After returning to his pickup (1998 |
| Chevy S-10 - Silver), he noticed that the lock was cut and the gauge had |
| been stolen (approximately 8:00 a.m.). Source numbers are (CS-137: |
| 750-4377) and (AM-241: 47-27208)." |
| |
| The licensee notified the City of Garland Police Department (Report Number |
| R028859) and the Texas Department of Health (Texas Incident Number I-7816). |
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|Power Reactor |Event Number: 38416 |
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| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 10/22/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 18:48[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 10/22/2001|
+------------------------------------------------+EVENT TIME: 13:57[EDT]|
| NRC NOTIFIED BY: MILLER |LAST UPDATE DATE: 10/24/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: |WILLIAM BECKNER NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| DISCOVERY OF A THROUGH-WALL LEAK AROUND 3 (THREE) CONTROL ROD DRIVE
|
| MECHANISM NOZZLES (REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK)
|
| |
| On October 11 and 12, 2001, following shutdown for a scheduled refueling |
| outage, Three Mile Island Unit 1 (TMI-1) performed a visual inspection of |
| the Reactor Vessel (RV) Control Rod Drive Mechanism (CRDM) nozzles per NRC |
| Bulletin 2001-01. The inspection revealed evidence of boric acid buildup |
| around 12 CRDM nozzles. No other CRDM nozzles showed similar boron buildup. |
| After the RV head was removed and placed on the storage stand, additional |
| inspections were performed. At approximately 1357 on October 22, 2001, |
| Engineering evaluation of the visual inspection, Liquid Penetrant Test (PT) |
| data and Ultrasonic Test (UT) data identified through-wall indications on |
| three CRDM nozzles. This engineering evaluation concluded that the visual |
| indications around CRDMs 44, 35, and 37 indicate a Reactor Coolant System |
| (RCS) pressure boundary leak. The inspection is not yet completed, thus |
| additional CRDM through-wall indications may be identified. This condition |
| is consistent with industry experience with Primary Water Stress Corrosion |
| Cracking (PWSCC) in similar components that have been evaluated as part of |
| the NRC Generic Letter 97-01 and NRC Bulletin 2001-01. Additional nozzles |
| may be examined by UT in accordance with TMl-1's response to NRC Bulletin |
| 2001-01. This condition did not pose a significant safety risk during plant |
| operation. TMl-1 plans to perform CRDM nozzle repairs during the current |
| refueling outage. Since the condition resulted in leakage through the RCS |
| pressure boundary, it is being reported as a non-emergency [8-hour] report |
| in accordance with 10 CFR 50.72(b)(3) (ii)(A) and 50.73(a)(2)(ii) (A). |
| |
| The NRC resident inspector has been notified. |
| |
| * * * UPDATED AT 1015 EDT ON 10/24/01 BY ADAM MILLER TO FANGIE JONES * * * |
| |
| Two additional CRDMs (29 and 64) indicate a RCS pressure boundary leak. |
| This brings the total to 5 CRDM nozzles showing through-wall leaks. The |
| licensee notified the NRC Resident Inspector. |
| |
| The R1DO (John Kinneman) and the NRR EO (William Beckner) have been |
| informed. |
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|General Information or Other |Event Number: 38421 |
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| REP ORG: DRESSER-RAND |NOTIFICATION DATE: 10/24/2001|
|LICENSEE: GIMPEL |NOTIFICATION TIME: 05:05[EDT]|
| CITY: WELLSVILLE REGION: 1 |EVENT DATE: 10/22/2001|
| COUNTY: STATE: NY |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/24/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE DOERFLEIN R1 |
| |EDWARD MCALPINE R2 |
+------------------------------------------------+BRENT CLAYTON R3 |
| NRC NOTIFIED BY: GEORGE HERMANN |WILLIAM JOHNSON R4 |
| HQ OPS OFFICER: FANGIE JONES |VERN HODGE (FAX) NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
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| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT CONCERNING TERRY TURBINE TRIP & THROTTLE VALVE
SCREW |
| SPINDLE |
| |
| The following is from a facsimile report: |
| |
| DESCRIPTION OF DEFECT: |
| |
| Material substitution of grade 1212 Steel in place of grade 1018 carbon |
| steel specified by design. |
| |
| ENGINEERING EVALUATION & RECOMMENDATIONS: |
| |
| Following the failure of an installed Trip/Throttle valve screw spindle on |
| the Catawba unit #2 AFW Pump Turbine (Terry Turbine S/N 40096A or B) on May |
| 25, 2000, the material of the failed screw was analyzed and found to be |
| Grade 1212 steel. Gimpel gave verbal confirmation that the screw material |
| was incorrect (Grade 1213 and 1215 steel) at the Terry Turbine Users Group |
| meeting on July 18, 2001 Gimpel has traced the supplied material to a single |
| lot of approximately 50 original screw spindles manufactured in 1974, and |
| has identified the originally affected Trip & Throttle valve serial numbers |
| as 74-12201-01 to 74-12244-02, 78-13136-01, 78-13215-01, and 78-13091-01. |
| Written confirmation of this defect and a listing of affected valves was |
| received by Dresser-Rand 10/11/01. |
| |
| Following this incident, additional information was received indicating that |
| a screw spindle installed in Palo Verde Unit 1 was found cracked In 1992, |
| and was determined to be grade 1213 steel. |
| |
| Dresser-Rand tested the material of a functional screw spindle removed from |
| an in-house test valve (Gimpel serial number 74-12243) and determined the |
| material was grade 1212. |
| |
| It is unknown whether the material substitution was a contributing factor in |
| the failures of the screw spindles at these sites. The trip valves in |
| question have been in operation for many years, and although the material |
| used is less desirable in this application than the design specified |
| material, the limited number of failures indicates that the immediate risk |
| of continued operation is minimal. It is acknowledged however, that a |
| substantial safety hazard may exist due to this defect in that failure of |
| this component can result in steam isolation preventing the emergency |
| feedwater turbine from performing its safety-related function. |
| |
| Recommendations: |
| 1) Units using Gimpel T&T valves in the serial number series listed above |
| which may have the original Screw spindle installed should replace their |
| screw spindles at the next maintenance opportunity. The original spindles |
| should be destroyed. |
| 2) It is additionally recommended that any Gimpel screw spindles in-stock or |
| in-service which may have been manufactured in the 1974-75 timeframe be |
| treated as suspect and be tested to confirm that the material is correct |
| (Grade 1018 carbon steel). |
| |
| A written Final Report will be submitted no later than 11/21/01. |
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|Power Reactor |Event Number: 38422 |
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/24/2001|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 13:41[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/24/2001|
+------------------------------------------------+EVENT TIME: 10:00[EDT]|
| NRC NOTIFIED BY: RAWLS |LAST UPDATE DATE: 10/24/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R2 IRC TEAM MANAGER R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| ACTUATION OF THE EMERGENCY FEEDWATER SYSTEM |
| |
| At 1000 on October 24, 2001, Crystal River Unit 3 (CR-3) was in MODE 3 |
| withdrawing Safety Rod Group 2 in preparation for Reactor Startup following |
| a refueling outage. In-plant Auxiliary Steam loads were being supplied from |
| Crystal River Unit 1 (CR-1). Auxiliary Steam (AS) loads are normally |
| supplied from CR-1 or Crystal River Unit 2 (CR-2) (sister fossil units) when |
| Unit 3 is not operating at high power. CR-2 was off-line at the time and |
| CR-1 tripped, resulting in a complete loss of Auxiliary Steam (AS) to Unit |
| 3. Motive steam was lost for the running Main Feed Pump and Main Condenser |
| vacuum lowered. Both Once Thru Steam Generator (OTSG) levels lowered |
| resulting in an Emergency Feedwater System (EFW) actuation on low OTSG |
| level. The OTSG levels were restored to normal by EFW. OTSG levels |
| remained on scale throughout the transient. Safety Rod Group 2 was fully |
| inserted and Reactor Startup preparations were suspended. The AS header was |
| repressurized from the Main Steam System and Main Condenser vacuum was |
| restored. Reactor Coolant System (RCS) temperature and pressure are stable |
| at normal hot standby values and plant startup will continue once AS is |
| restored from CR-1. This event was an event or condition that resulted in a |
| valid actuation of the Emergency Feedwater System and is thus reportable as |
| an eight hour report. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 38423 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/24/2001|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:41[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/24/2001|
+------------------------------------------------+EVENT TIME: 17:40[CDT]|
| NRC NOTIFIED BY: MATHEWS |LAST UPDATE DATE: 10/24/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
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+------------------------------------------------------------------------------+
EVENT TEXT
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| GREATER THAN 25% OF THE OFFSITE EMERGENCY SIRENS WERE OUT OF SERVICE
|
| |
| At 1523 on 10/24/01 16 of 44 emergency sirens were determined to be |
| inoperable for greater than one hour due to a storm causing power outages. |
| At 1620 six of the original non-functioning sirens were returned to service, |
| leaving a total of ten sirens out of service which is less than 25% being |
| out of service The remaining out of service sirens are expected to be |
| returned to service on 10/25/01 as power is restored to these areas. |
| |
| The NRC Resident Inspector and local agencies were notified. |
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|Power Reactor |Event Number: 38424 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/24/2001|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 19:09[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/24/2001|
+------------------------------------------------+EVENT TIME: 16:25[CDT]|
| NRC NOTIFIED BY: RODE |LAST UPDATE DATE: 10/24/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 63 Power Operation |63 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| PROCEDURE USED FOR INSTALLATION OF TEMPORARY FIRE SEALS WAS NOT IN
|
| COMPLIANCE WITH THE CALCULATION QUALIFYING THE TEMPORARY FIRE SEALS
|
| |
| During an internal review of the fire protection program at Point Beach |
| Nuclear Power Plant, it was determined that the procedure used for the |
| installation of temporary fire seals was not in compliance with the |
| calculation qualifying the temporary fire seals. The procedure called for 4 |
| inches of Kaowool while the calculation demonstrated the 5 inches would |
| ensure adequate fire protection. |
| |
| Out of the 9 barriers that were identified, 4 of them are required to |
| provide train separation for safe shut down equipment. Due to the identified |
| condition, these penetrations may not have adequately provided such |
| separation as required by our safe shutdown analysis. |
| |
| Immediate actions taken included: 1) Affected penetrations were identified |
| and declared out of service. 2) Appropriate fire rounds were commenced. 3) |
| Installed the required 5 inches of Kaowool in the identified barriers and |
| returned the barriers back to service. |
| |
| Pending corrective actions: Although the calculation determined 5 inches of |
| Kaowool provides an adequate fire barrier, engineering will perform an |
| additional evaluation to determine if 4 inches of Kaowool would suffice. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 38425 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 10/25/2001|
| UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 02:07[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/25/2001|
+------------------------------------------------+EVENT TIME: 00:25[CDT]|
| NRC NOTIFIED BY: FUCICH |LAST UPDATE DATE: 10/25/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN MONNINGER R2 |
|10 CFR SECTION: | |
|AMED 50.72(b)(3)(xii) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| WORKER OVERCOME BY HEAT TAKEN TO LOCAL MEDICAL FACILITY |
| |
| The licensee evacuated a worker who was working in containment and was |
| overcome by the heat. The worker was transported using the utility's |
| emergency vehicle. There was a small area of contamination on the worker's |
| neck which was decontaminated during the trip to the hospital. The worker |
| was not contaminated when admitted to the hospital. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021