The NRC is modernizing nrc.gov with an updated design and improved navigation to enhance usability. We are committed to a smooth transition and will work to minimize any disruption. The site may be briefly unavailable at times during launch. Thank you for your patience.
Event Notification Report for October 24, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/23/2001 - 10/24/2001
** EVENT NUMBERS **
38414 38417 38418 38419 38420 38421
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38414 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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). |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38417 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 10/23/2001|
|LICENSEE: CITY OF COLORADO SPRINGS |NOTIFICATION TIME: 12:59[EDT]|
| CITY: COLORADO SPRINGS REGION: 4 |EVENT DATE: 10/23/2001|
| COUNTY: STATE: CO |EVENT TIME: [MDT]|
|LICENSE#: 48-01 AGREEMENT: Y |LAST UPDATE DATE: 10/23/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JACOBI by FAX | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE CITY OF COLORADO SPRINGS REPORTED A MISSING Ni-63 RADIATION SOURCE
|
| |
| The wastewater treatment plant has gas chromatography equipment that uses |
| electron capture detectors containing 8-15 mCi Ni-63. For as long as anyone |
| now present can remember, the instruments in use there have been made by |
| Hewlett Packard. There have been 4 detectors made by Varian in a box in |
| storage on a shelf in a cabinet in the lab. Those detector cells did not |
| fit on the HP GCs. The lab manager discovered another laboratory that |
| wanted the detectors that were in storage. They solicited and received a |
| copy of that laboratories license to possess radioactive material (as well |
| as the license for CJ Bruyn, a detector maintenance facility). The 4 |
| detectors were sent to C.J. Bruyn of Bellingham Washington, who upon |
| receiving the detectors and opening the cases for cleaning reported that one |
| of them did not contain the radioactive source. |
| |
| An exhaustive search of the lab, concentrating on the cabinet area where the |
| sources were stored revealed no hint of the source. The emissions or Ni-63 |
| are of such energy that external readings with a survey instrument would |
| never indicate the presence of such a source. Areas of the laboratory have |
| been wipe tested for contamination from the time that sources have been in |
| use there, and no lost source has been so revealed. |
| |
| The source housings for the Varian sources have not been opened at the |
| Laboratory, to the best of anyone's knowledge. In the past, the HP sources |
| were opened for cleaning and maintenance, but never the Varian sources. No |
| one now at the lab can remember using Varian GCs and so cannot remember that |
| one of those detectors did not work (possibly indicating a missing source). |
| |
| The only scenarios that make any sense is that either |
| 1. The detector cell was received without the radioactive source from the |
| original vendor or a facility that cleaned it. |
| 2. The source inadvertently fell out of the detector cell when it was opened |
| at CJ Bruyn and was not detected. The individual involved at CJ Bruyn denies |
| this possibility. |
| |
| Ni-63 is a beta emitter with 67 keV electron energy and approximately 100y |
| half-life. The range of the emissions in air is ~10 inches, if the source |
| was in contact with an individuals skin the electrons would penetrate |
| ~0.35mm. A significant radiological hazard is hard to imagine unless the |
| source was ingested, inhaled, or held against the skin for a protracted |
| period. It has been discussed with the department that ingesting Ni-63 is |
| not even a hazard of significance. Nickel is not absorbed by the body and |
| the beta particles are absorbed by the fecal matter. |
| |
| Modifying the procedures to avoid a future occurrence of a similar instance |
| is not indicated due to the extremely unlikely probability. We no longer |
| have EC detectors that are in long-term storage and use the ones that we |
| have on a regular rotation, so we will know if the source is not present. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38418 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 10/23/2001|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 14:54[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/23/2001|
+------------------------------------------------+EVENT TIME: [CDT]|
| NRC NOTIFIED BY: HAWKINS |LAST UPDATE DATE: 10/23/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R2 IRC TEAM MANAGER R2 |
|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 N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE EMERGENCY NOTIFICATION NETWORK WAS INOPERABLE |
| |
| The licensee reported that their Emergency Notification Network(ENN) was |
| declared inoperable due to an on site switching problem. Three channel |
| banks went down and did not automatically transfer to backup source. The |
| problem has been identified and was restored(test satisfactory) at 1324 CDT. |
| The problem with the automatic transfer is still being investigated. The |
| licensee uses the Southern Line System as a backup for the ENN. |
| |
| The NRC Resident inspector was notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38419 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/23/2001|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 14:57[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/23/2001|
+------------------------------------------------+EVENT TIME: 11:02[EDT]|
| NRC NOTIFIED BY: CAMPBELL |LAST UPDATE DATE: 10/23/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: |GENE IMBRO NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|RICHARD WESSMAN IRO |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAMMED FROM 100% POWER DUE TO TURBINE VALVE FAST CLOSURE
SIGNAL |
| |
| Unit 2 was operating at 100% power when a Main Generator Lockout resulted in |
| a Reactor SCRAM from a Turbine Control Valve Fast Closure Signal. Reactor |
| Pressure peaked at 1125 psig causing 5 Safety Relief Valves to open, and an |
| automatic ARI (Alternate Rod Insertion) initiation on high reactor pressure. |
| The SCRAM transient also caused an expected reactor low level condition of |
| minus seven inches (-7 inches) resulting in PCIS (Primary Containment |
| Isolation System) Group II and III Isolations and SBGTS (Standby Gas |
| Treatment System) initiation. All plant systems operated as expected with |
| all rods being fully inserted and all relief valves fully reseating. |
| |
| The Unit 2 Reactor is shutdown, and cause of the Generator Lockout is being |
| investigated. Reactor level is 23 inches, and a controlled reactor cool |
| down is in progress. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38420 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 10/23/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 19:40[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 10/23/2001|
+------------------------------------------------+EVENT TIME: 17:12[CDT]|
| NRC NOTIFIED BY: STOCKHAM |LAST UPDATE DATE: 10/23/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 98 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR SCRAM FROM 98% POWER DUE TO A GROUP 1
ISOLATION |
| |
| The group 1 MSIV isolation instrumentation was bumped in the plant causing |
| an inadvertent group 1 isolation which resulted in a reactor scram. Group 2 |
| and 3 isolations also occurred on low reactor level (+9") during the reactor |
| scram. The low-low set controlled reactor pressure while the MSIV's were |
| closed. The "H" SRV cycled approximately 6 times and fully reseated. All |
| rods fully inserted and no ECCS actuation occurred. |
| |
| The NRC Resident Inspector, the state, and local agencies were notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38421 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
.
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021