Event Notification Report for September 25, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/22/2000 - 09/25/2000
** EVENT NUMBERS **
37313 37360 37361 37364 37365 37366 37367 37368 37369 37370 37371 37372
37373
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37313 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/13/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 07:58[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/13/2000|
+------------------------------------------------+EVENT TIME: 04:33[EDT]|
| NRC NOTIFIED BY: MATT WALDECKER |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|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 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC START OF THE HIGH PRESSURE CORE SPRAY PUMP |
| |
| The licensee reported that the high pressure core spray (HPCS) pump |
| automatically started when the pump control switch was taken out of the |
| "pull-to-lock" position. The HPCS system was out of service for maintenance |
| at the time of the event and had been declared inoperable on 09/12/00 at |
| 0520 EDT. The HPCS spray injection valve did not open, as it was |
| deenergized closed. The divisional diesel generator did not start as it was |
| configured in the maintenance mode. |
| |
| There was no impact on the plant. The plant is in cold shutdown with the |
| mode switch in the refuel position. The cause of the actuation is unknown |
| and an investigation is in progress. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * RETRACTED AT 1650 EDT ON 9/22/00 BY THOMAS CHWALEK TO FANGIE JONES * * |
| * |
| |
| "Subsequent evaluation of the system condition at the time concluded that |
| the system was appropriately removed from service with the injection valve |
| de-energized closed (it was known at the time that the initiation signal was |
| invalid). In addition, removal of the system from service as part of a |
| planned evolution for maintenance or surveillance testing is generally not |
| reportable (NUREG 1022). |
| |
| "In summary, the system was properly removed from service with the injection |
| valve de-energized closed. The event is not reportable and this retraction |
| is notification thereof." |
| |
| The licensee intends to notify the NRC Resident Inspector. The R1DO (Bruce |
| Barkley) has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37360 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MARYLAND DEPT OF THE ENVIRONMENT |NOTIFICATION DATE: 09/21/2000|
|LICENSEE: D W KOZERA INC |NOTIFICATION TIME: 09:48[EDT]|
| CITY: BALTIMORE REGION: 1 |EVENT DATE: 09/20/2000|
| COUNTY: STATE: MD |EVENT TIME: 14:30[EDT]|
|LICENSE#: MD0514901 AGREEMENT: Y |LAST UPDATE DATE: 09/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM RULAND R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MANLEY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST TROXLER MOISTURE DENSITY GAUGE REPORTED TO THE MARYLAND DEPARTMENT OF |
| THE ENVIRONMENT (MDE) |
| |
| Maryland licensee, D W Kozera Inc. of Baltimore, Md. lost a Troxler moisture |
| density gauge model 3430 serial # 25607 in Adamstown, Md. The gauge was |
| missing from the back of a flat bed truck , which had its tailgate down, |
| that was being driven around the Greenhill Manor Residential subdivision(New |
| Design Rd & Union Ridge Rd in Fredrick City). The gauge, which apparently |
| fell out of the back of the truck, was not in its case and the source rod |
| was not padlocked. The source (7.2 millicuries of cesium 137 and 39.7 |
| millicuries of americium 241), as far as they know, was in the shielded |
| position and has not been found. MDE has conducted an initial investigation |
| and it appears that they may issue a press release. |
| |
| * * * UPDATE ON 09/22/00 AT 0842 ET BY R. MANLEY TAKEN BY MACKINNON * * * |
| |
| The Troxler gauge was picked up from the middle of road (New Design Rd & |
| Union Ridge Rd) by a sub contractor shortly after it fell from the back of |
| the flat bed truck. The casing of the Troxler gauge had minor damage and |
| the source never left its shielded position. After reading the article in |
| the newspaper about the missing Troxler gauge the Sub Contractor contacted |
| the licensee, D W Kozera Inc. The Troxler gauge case had a phone number and |
| address on it but the Sub Contractor was unable to contact the licensee |
| until reading the newspaper article which gave where the licensee could be |
| contacted. The Troxler gauge will be checked over today by Troxler. |
| |
| NRC R1DO (Bill Ruland) and NMSS EO (Brian Smith) notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37361 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/21/2000|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 16:07[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/21/2000|
+------------------------------------------------+EVENT TIME: 15:30[EDT]|
| NRC NOTIFIED BY: JOHN POPIELARSKI |LAST UPDATE DATE: 09/23/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE EMERGENCY SIRENS IN DEGRADED CONDITION |
| |
| "On September 21, 2000 at 1530, it was identified that at least 17 of Peach |
| Bottom's 97 Emergency Offsite Sirens were in a degraded condition. The exact |
| cause of the degraded sirens is not known at this time, but the ability of |
| the licensee to detect the degraded sirens has been compromised due to poor |
| maintenance practices. A plan is being developed and implemented to repair |
| the degraded sirens and appropriate interim compensatory measures are being |
| put in place to compensate for the degraded condition." |
| |
| An investigation is underway into this matter. The contractor responsible |
| for the siren maintenance has no other responsibilities on site. |
| |
| The licensee has notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 2253 EDT ON 9/23/00 BY JIM VASH TO FANGIE JONES * * * |
| |
| The licensee reported that 15 of the 17 sirens that were in degraded |
| conditions have been restored to service. The remaining 2 sirens are |
| expected to be restored to service early next weeks. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R1DO |
| (Richard Barkley) has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 04:26[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 04:00[EDT]|
| NRC NOTIFIED BY: HAMM/SCHALL |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |THOMAS DECKER R2 |
|10 CFR SECTION: |BILL BATEMAN NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOSEPH GIITTER IRO |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |LUIS REYES R2 |
| |HEYMAN FEMA |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| FIRE IN THE PROTECTED AREA LASTING GREATER THAN 10 MINUTES RESULTING IN A |
| REACTOR SCRAM. |
| |
| AN UNUSUAL EVENT WAS DECLARED @ 0400 DUE TO A FIRE IN THE MAIN TRANSFORMER |
| THAT LASTED >10 MINUTES. OFF SITE FIRE DEPARTMENT WAS CALLED IN TO RESPOND |
| AND THE FIRE WAS EXTINGUISHED WITHIN 14 MINUTES, HOWEVER THE PLANT STILL |
| REMAINS IN THE UNUSUAL EVENT. A REACTOR SCRAM FROM 100% POWER OCCURRED |
| FOLLOWING A MAIN TURBINE GENERATOR LOCKOUT WHICH RESULTED FROM THE |
| TRANSFORMER FAILURE. THERE WERE SOME ERRONEOUS INDICATIONS OF CONTROL ROD |
| POSITION, BUT ALL RODS APPEAR TO BE FULLY INSERTED. THERE WAS NO ECCS |
| ACTUATION AND NO SAFETY RELIEF VALVES LIFTED DURING THIS EVENT. THE PLANT |
| DID NOT LOSE OFFSITE POWER DUE TO THE AUTO TRANSFER FROM THE MAIN |
| TRANSFORMER TO THE STARTUP AUXILIARY TRANSFORMER. THE DIESELS AUTOMATICALLY |
| STARTED AND WERE STILL RUNNING AT THE TIME OF THIS REPORT. GROUP 2,6 AND 8 |
| ISOLATIONS WERE ALSO RECEIVED. THERE WAS A PROBLEM WITH THE STARTUP LEVEL |
| CONTROL VALVE WHEN THEY REESTABLISHED REACTOR FEED PUMP, VALVE DID NOT OPEN |
| PROPERLY SO THEY HAD TO USE THE BACKUP PATH IN THE FEED SYSTEM. AS A |
| RESULT OF THIS THE LEVEL WENT LOW ENOUGH TO RECEIVE A SECOND REACTOR SCRAM |
| SIGNAL. THE CONDENSER IS BEING USED AS THE HEAT SINK AND THE PLANT IS |
| STABLE. THE CAUSES FOR THE TRANSFORMER FIRE AND THE ERRONEOUS CONTROL ROD |
| INDICATIONS ARE BEING INVESTIGATED. THERE HAVE BEEN NO INJURIES REPORTED |
| AND IT IS NOT KNOWN AT THIS TIME IF A PRESS RELEASE WILL BE ISSUED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| * * * UPDATE ON 9/22/00 @ 0528 BY HAMM TO GOULD * * * |
| |
| THE NOUE WAS TERMINATED AT 0512 DUE TO THE FIRE BEING COMPLETELY |
| EXTINGUISHED. |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. |
| THE EO(BATEMAN), RDO(DECKER), FEMA (HEYMAN) AND IRO(GIITTER) WERE |
| NOTIFIED. |
| |
| SEE EVENT # 37365. |
| |
| * * * UPDATE AT 1313 EDT ON 9/22/00 BY KEN CHISM TO FANGIE JONES * * * |
| |
| The licensee, after further review, has determined that the fire was |
| extinguished in 16 minutes versus the 14 minutes originally reported. |
| |
| The licensee has issued a press release concerning the declaration of |
| Unusual Event. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R2DO (Thomas |
| Decker), NRR (Ed Goodwin), IRO (Joseph Giitter) have been notified. |
| |
| * * * UPDATE AT 1653 EDT ON 9/22/00 BY KEITH REQUARD TO FANGIE JONES * * * |
| |
| The licensee notified the State of North Carolina due to an oil spill |
| resulting from the event. On September 22, 2000, at approximately 1350 |
| hours, a notification was made to Mr. Jim Bushard, of the North Carolina |
| Division of Water Quality, Wilmington Regional Office. |
| |
| The incident began when a transformer overheated. The overheated transformer |
| developed a leak at an oil flange, and caught fire. The transformer deluge |
| system activated and, as a result, a mixture of water and transformer oil |
| escaped the concrete containment structure surrounding the transformer. It |
| is estimated that greater than 25 gallons and less than 100 gallons of |
| transformer oil is outside of the containment structure. The oil is |
| contained onsite and poses no environmental hazard. The oil is a mineral oil |
| and contains no PCBs. Clark Environmental Services Inc. is performing the |
| cleanup. |
| |
| The licensee notified the NRC Resident. The R2DO (Thomas Decker), IRO |
| (Joseph Giitter), and NRR EO (Bill Bateman) have been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37365 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 06:37[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 03:40[EDT]|
| NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER 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 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT HAD ESF ACTUATIONS DURING A REACTOR SCRAM |
| |
| A main turbine trip resulted in a reactor scram. As expected following the |
| scram, reactor water level dropped to the actuation setpoint for Groups 2, 6 |
| and 8 isolations. The main turbine trip apparently resulted from a fire in B |
| main power transformer. The fire was reported to the control room at 0346. |
| The site fire brigade responded and the fire was extinguished at 0402 using |
| the automatic deluge system and fire hoses. Offsite fire department |
| assistance was requested but was not needed to extinguish the fire. An |
| Unusual Event was declared at 0400 in accordance with the plant's emergency |
| procedures. The Unusual Event was terminated at 0512 based on the plant |
| being in a stable condition. During the transient the startup level |
| control did not control level in the automatic mode. Reactor level was |
| controlled using a feedwater bypass valve. A second reactor scram signal |
| was generated due a low reactor water level signal received while manual |
| level control was being established, however all rods were already fully |
| inserted. The plant emergency diesels started but did not load. Offsite |
| power remained available throughout the event. The NRC Resident Inspector |
| was notified. |
| |
| HOO Note: see event # 37364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37366 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 11:49[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 11:10[EDT]|
| NRC NOTIFIED BY: A. DALL'AU |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 88 Power Operation |88 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SEVERAL PIECES OF SCAFFOLDING KNUCKLES AND ELBOWS RECEIVED FROM VENDOR FOUND |
| TO HAVE LOW LEVELS OF RADIOACTIVITY. OFFSITE NOTIFICATION MADE TO THE STATE |
| OF FLORIDA |
| |
| While performing routine surveys, Turkey Point Health Physics personnel |
| discovered low levels of radioactivity on several pieces of scaffolding |
| knuckles and elbows received from a vendor. The knuckles never entered the |
| site's radiation controlled area. These items were counted in a Small |
| Articles Monitor (SAM) and indicated low level contamination was present. |
| In total 3 out of approximately 700 item's surveyed indicted the presence of |
| low level fixed activity. The highest level measured was 15,000 |
| disintegration's per minute (dpm) using a standard HP-210 (pancake GM) |
| probe. Isotope analysis indicated Cobalt-60 and Cesium-137. No loose |
| surface contamination was found. The items identified with low level fixed |
| contamination are now being held inside the Turkey Point radiation |
| controlled area. The state of Florida was notified of this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37367 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 12:17[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 09:40[EDT]|
| NRC NOTIFIED BY: DAVID FRYE |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|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
+------------------------------------------------------------------------------+
| LICENSEE TECHNICAL REQUIREMENTS 24 HOUR REPORT |
| |
| The licensee, in accordance with their technical requirements, reported that |
| the diesel fire pump was removed from service for approximately 2 hours. |
| The pump was removed from service as part of ongoing maintenance of the |
| pretreatment water storage tank. The pump being out-of-service and having |
| one of two sources of water out-of-service prompted the 24 hour report. The |
| pump has been restored to service. |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37368 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 09/22/2000|
|LICENSEE: CONSTRUCTION TESTING ENGINEERING |NOTIFICATION TIME: 13:07[EDT]|
| CITY: CONCORD REGION: 4 |EVENT DATE: 09/22/2000|
| COUNTY: STATE: CA |EVENT TIME: 06:00[PDT]|
|LICENSE#: 2952-07 AGREEMENT: Y |LAST UPDATE DATE: 09/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARK M. GOTTLIEB | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE STOLEN FROM THE BACK OF A PICKUP TRUCK |
| |
| AGREEMENT STATE REPORT |
| |
| A Troxler Moisture Density gauge, Model # 3411-B (serial (12622) was stolen |
| from the back of a pickup truck in Concord, California this morning around |
| 0600 PT. The gauge was locked in the back of the licensee's pickup truck |
| with a hasp lock going through the handle of the Troxler gauge case. The |
| hasp lock cable was cut with a chain cutter. The person driving the pickup |
| truck drove the truck home and was away from the truck approximately 15 |
| minutes. The Concord police department was notified of the theft. |
| |
| Troxler Model # 3411-B: 9 mCi of Cs-137 and 44 mCi of Americium-241. State |
| of California report number is 092200. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 37369 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SIBLEY MEMORIAL HOSPITAL |NOTIFICATION DATE: 09/22/2000|
|LICENSEE: SIBLEY MEMORIAL HOSPITAL |NOTIFICATION TIME: 16:15[EDT]|
| CITY: WASHINGTON REGION: 1 |EVENT DATE: 09/22/2000|
| COUNTY: STATE: DC |EVENT TIME: 13:00[EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RICHARD BARKLEY R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GREGORY SIBLEY | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 2 PATIENTS RECEIVED MEDICAL MISADMINISTRATION DUE TO CALCULATION ERROR |
| |
| The hospital discovered today that a mistake was made in ordering sources |
| for medical procedures, a change had been made to order sources in 'air |
| kerma strength' instead of millicuries (mCi). The conversion is suppose to |
| be mCi divided by 1.2 instead they multiplied by 1.2. Two patients received |
| I-125 plaques to the eye for melanoma and were suppose to receive 7000 rads, |
| instead received 10,866 and 11,470 rads. There is not expected to be any |
| consequences beyond what was expected with the prescribed dose. The |
| procedure was a try at preserving the eye as it would have been removed |
| otherwise. The prescribing physician has been contacted and the patient |
| will be counseled. |
| |
| The hospital has determined that no other sources were ordered with the |
| wrong calculation and is taking steps to insure this mistake is not |
| repeated. |
| |
| The hospital has contacted NRC Region 1 (Teresa Darden). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37370 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/22/2000|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 20:04[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/22/2000|
+------------------------------------------------+EVENT TIME: 19:15[EDT]|
| NRC NOTIFIED BY: THOMAS DOUGHERTY |LAST UPDATE DATE: 09/22/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| TESTING FOUND 20 OF 165 OFFSITE EMERGENCY SIRENS DETERMINED TO BE |
| INOPERABLE |
| |
| "On September 22, 2000 at 19:15, it was determined that 20 of Limerick |
| Generating Station's 165 Emergency Offsite Sirens were inoperable. The exact |
| cause of the inoperable sirens is not known at this time, but the ability of |
| the licensee and counties to detect the inoperable sirens has been |
| compromised. A plan is being developed to repair the degraded sirens, and |
| appropriate interim compensatory measures are being implemented to |
| compensate for the degraded condition." |
| |
| This was the result of routine testing, there was no cluster of inoperable |
| sirens, the inoperable sirens reported appeared operable from remote testing |
| at the county, and an investigation will continue. These sirens have been |
| maintained by the same contractor as mentioned in NRC report #37361 of |
| 9/21/00. |
| |
| The licensee has notified the NRC Resident Inspector and contacted the local |
| authorities as part of the interim compensatory measures. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37371 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 09/23/2000|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 03:02[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/23/2000|
+------------------------------------------------+EVENT TIME: 00:37[EDT]|
| NRC NOTIFIED BY: TOM COTTER |LAST UPDATE DATE: 09/23/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|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 7 Power Operation |7 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC FEEDWATER ISOLATION DURING PLANT SHUTDOWN |
| |
| "Beaver Valley Unit 2 experienced an Automatic Feedwater Isolation on high |
| steam generator water level from the 21 B steam generator. The main turbine |
| valves were closed and the unit was off line. This occurred during plant |
| shutdown for refueling at 00:37. Unit 2 was at 7% reactor power at the time |
| of the feedwater isolation. The steam generators were being fed using normal |
| feedwater through the bypass feedwater regulating valves. Steam removal was |
| via the condenser steam dump system. The feedwater isolation occurred |
| shortly after the planned main turbine overspeed trip test was completed. |
| The feedwater isolation resulted in the closure of feed water isolation |
| valves 2FWS-HYV157A, B, and C and the trip of the running main feedwater |
| pump 2FWS-P21A. The motor driven auxiliary feedwater pumps started as |
| designed upon the trip of the running main feedwater pump. All ESF |
| equipment was verified to respond as expected. New positioners were |
| installed on the bypass feedwater regulating valves prior to the Unit 2 |
| shutdown for refueling and may have changed the control response. |
| |
| "Plant shutdown continued and at 00:39 Unit 2 entered Mode 2. After the |
| steam generator water level returned to below the ESF setpoint, normal |
| feedwater flow was re-established via 2FWS-P21A and the bypass feedwater |
| regulating valves at 00:42. Heat removal was maintained at all times via |
| the condenser steam dump removal system. The auxiliary feedwater pumps were |
| manually secured at 00:46. Unit 2 entered Mode 3 at 01:12 and preparations |
| are being made for cooldown to Mode 5. A root cause analysis is being |
| performed to investigate the ESF actuation." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37372 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 09/23/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 05:09[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/23/2000|
+------------------------------------------------+EVENT TIME: 01:20[EDT]|
| NRC NOTIFIED BY: FRANK SOENS |LAST UPDATE DATE: 09/23/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |RICHARD BARKLEY R1 |
|10 CFR SECTION: |FEMA, DOE, DOA (fax) |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |HHS, EPA, DOT (fax) |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 40 Power Operation |18 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE OF NEW JERSEY INVOLVING RELEASE OF SECONDARY |
| CONDENSATE CONTAINING HYDRAZINE TO THE DELAWARE RIVER |
| |
| "During a planned downpower, a flange leak developed on the 15C feedwater |
| heater condensate line. The leakage rate was approximately 100 gpm. This |
| resulted in water containing hydrazine entering a storm drain which leads to |
| the Delaware River. A 15 minute notification was made to the State of New |
| Jersey at 0135. Sample results indicated 30 ppb hydrazine with the limit |
| being 10 ppb. The 15C feedwater heater is being isolated and cooled down |
| with leakage at approximately 25 gpm. The plant is stable with power at 18% |
| and the turbine offline in accordance with the scheduled downpower. [The] |
| 15 SW pump is INOPERABLE but available due to planned maintenance. [The] 13 |
| Charging Pump is INOPERABLE due to a preexisting condition." |
| |
| The licensee estimates that 8-12 hours will be required to cooldown and |
| isolate the affected feedwater heater condensate line. Meanwhile, efforts |
| are underway to contain the leakage for reprocessing. There were no |
| injuries associated with the 250 degree condensate leakage. The licensee |
| informed the state of New Jersey, the Lower Alloways Creek Township and will |
| inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37373 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/23/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:29[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/23/2000|
+------------------------------------------------+EVENT TIME: 16:15[EDT]|
| NRC NOTIFIED BY: BRIAN CRAIG |LAST UPDATE DATE: 09/23/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SUPPORT CENTER LOST POWER UNEXPECTEDLY DURING MAINTENANCE |
| |
| It was determined at 1615 EDT on 9/23/00 that the unexpected loss of power |
| to the Technical Support Center (TSC) during a planned maintenance procedure |
| on 9/18/00 at 2000 EDT constituted a reportable event as a major loss of |
| assessment capability. Power was restored at 2107 on 9/18/00 and all |
| functions restored. It has been determined that the loss of power should |
| have been expected as part of the maintenance and a review of the event is |
| ongoing. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021