Event Notification Report for July 21, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/20/1999 - 07/21/1999 ** EVENT NUMBERS ** 35931 35936 35937 35938 35939 35940 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35931 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 07/18/1999| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 20:41[EDT]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 07/18/1999| +------------------------------------------------+EVENT TIME: 18:07[EDT]| | NRC NOTIFIED BY: BOB BOYER |LAST UPDATE DATE: 07/20/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN WHITE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO OF THREE OPERATING REACTOR CONTAINMENT BUILDING (RCB) FANS UNEXPECTEDLY | | TRIPPED DURING TROUBLESHOOTING OF ENGINEERED SAFEGUARDS ACTUATION SIGNAL | | (ESAS) RELAYS BY A CONTROL ROOM OPERATOR (CRO). | | | | "A CRO was checking the ESAS relays for noise, humming or signs of | | overheating after the relays had been exercised as a result of de-energizing | | VBB for 1B Inverter restoration. While trying to identify a humming relay | | the CRO touched what he thought was the frame of relay 1X1A RCB, but what he | | touched actuated the relay contacts. This caused AH-E-1B and AH-E-1C to | | trip. | | | | "The crew restarted AH-E-1B and AH-E-1C and followed Alarm response B-1-5 | | '480V ES Motor Trip.' Electrical prints (209-570 and 209-592) were referred | | to and showed that the relay is a normally de-energized relay. It sends a | | signal to the 1S and 1T 480V under voltage circuit, DH-V-4B to open and | | AH-E-1B/C to trip. The UV relays were verified to have not actuated and | | they were manually reset as a precautionary measure. DH-V-4B was verified | | still closed. | | | | "It is believed since the CRO only slightly moved the relay and AH-E-1B/C | | contacts are normally closed when the relay is de-energized and the other | | three relays are normally open, that the movement was enough to break the | | closed contacts but not enough to make up the open contacts." | | | | The licensee will inform the NRC resident inspector. | | | | * * * UPDATE AT 1337 ON 7/20/99 BY SCHORK RECEIVED BY WEAVER * * * | | | | The event that occurred on July 18, 1999, was an invalid actuation that only | | involved the AH-E-1B and AH-E-1C fans that are part of the reactor building | | ventilation system. Therefore, the requirement for reporting this as an ESF | | actuation is exempted in accordance with 10CFR50.72(b)(2)(ii)(B)(3)(iii). | | Thus, GPU Nuclear is withdrawing the 4 hour report | | | | A review of the reporting criteria of 10CFR50.73 found that the event is | | similarly not required to be reported and therefore GPU Nuclear will not be | | submitting a 30 day licensee event report regarding this issue. | | | | Nonetheless, the event has been entered into the GPU Nuclear 10CFR50, | | Appendix B Corrective Action Program and the cause and corrective action | | taken in response to this event will be documented in accordance with that | | program. | | | | The retraction of the 4 hour report has been discussed with W. Schmidt, the | | NRC Senior Resident Inspector. | | | | The NRC Operations Officer notified the R1DO Jim Noggle. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35936 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TN DIV OF RADIOLOGICAL HEALTH |NOTIFICATION DATE: 07/20/1999| |LICENSEE: GE INSPECTION SERVICES |NOTIFICATION TIME: 08:39[EDT]| | CITY: REGION: 2 |EVENT DATE: 07/15/1999| | COUNTY: STATE: TN |EVENT TIME: 12:00[EDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 07/20/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ANN BOLAND R2 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: DEBRA SHULTS (fax) | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - PERSONNEL OVEREXPOSURE | | | | On 07/19/99, the TN Division of Radiological Health (TN DRH) was notified by | | the Corporate Radiation Safety Officer for GE Inspection Services of an | | overexposure to an Assistant Radiographer. The overexposure occurred on | | 07/15/99 and was not reported to the TN DRH within the 24-hour requirement. | | | | A radiographer and an assistant were conducting radiography when they noted | | that the pocket dosimeter was off scale. They ceased operations and sent | | the dosimeter badges to Landauer for analysis on 07/16/99. According to | | Landauer, the assistant radiographer received a 17-rem whole body dose. It | | appears that the operator did not follow proper procedures for use of the | | device since the source was not returned fully into the camera. TN DRH | | staff is on site on 07/20/99 conducting an investigation. | | | | This is report #TN-99-095. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35937 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: PROFESSIONAL SERVICE INDUSTRIES |NOTIFICATION DATE: 07/20/1999| |LICENSEE: PROFESSIONAL SERVICE INDUSTRIES |NOTIFICATION TIME: 09:58[EDT]| | CITY: LIMA REGION: 3 |EVENT DATE: 07/20/1999| | COUNTY: STATE: OH |EVENT TIME: 01:00[EDT]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/20/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PATRICK HILAND R3 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CHRIS SMITH | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STOLEN TROXLER MOISTURE/DENSITY GAUGE | | | | A Troxler Model 3430 Moisture/Density Gauge (S/N 27891) was stolen from the | | back of a pickup truck in Lima, Ohio. The licensee reported that both the | | gauge and its transport carrier were missing from the truck. The local | | police were contacted and responded to the scene. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35938 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: OREGON RAD PROTECTION SERVICES |NOTIFICATION DATE: 07/20/1999| |LICENSEE: MERLE WEST MEDICAL CENTER |NOTIFICATION TIME: 13:06[EDT]| | CITY: KLAMATH FALLS REGION: 4 |EVENT DATE: 05/06/1999| | COUNTY: STATE: OR |EVENT TIME: 12:00[PDT]| |LICENSE#: ORE-90442 AGREEMENT: Y |LAST UPDATE DATE: 07/20/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ELMO COLLINS R4 | | |JOSIE PICCONE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TERRY LINDSEY | | | HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION | | | | A patient received 97 mCi of Sm-153 instead of 62 mCi based on a dosage of 1 | | mCi per Kg of body weight. | | This event occurred at the Merle West Medical Center in Klamath Falls, OR. | | Sm-153 is used to alleviate bone pain in cancer patients. The error was | | discovered by the chief technician. No other information was immediately | | available. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35939 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 07/20/1999| | UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 14:44[EDT]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/20/1999| +------------------------------------------------+EVENT TIME: 13:09[CDT]| | NRC NOTIFIED BY: PHILLIP SHORT |LAST UPDATE DATE: 07/20/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND R3 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASES - CONDITION OUTSIDE OF APPENDIX R REQUIREMENTS | | | | During an Appendix R baseline project review, a condition has been found | | that is considered to be outside the Appendix R Safe Shutdown design basis. | | During a postulated fire on the 26 foot level of the primary auxiliary | | building, fire related cable damage could lead to spurious opening of a | | single power operated relief valve (PORV) along with the inability to close | | its associated block valve. Presently, plant procedures direct operators to | | isolate air to the containment and vent the instrument air header locally in | | order to shut the PORV. The local valve operations that are required, | | however, are in the same area as the postulated fire. Failure to get the | | PORVs closed in adequate time would place the plant outside of the | | performance goals of 10CFR50, Appendix R, Paragraph III.L. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35940 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 07/20/1999| | UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 16:50[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/20/1999| +------------------------------------------------+EVENT TIME: 15:05[CDT]| | NRC NOTIFIED BY: D.W. MCGAUGHEY |LAST UPDATE DATE: 07/20/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ELMO COLLINS R4 | |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 +------------------------------------------------------------------------------+ | EMERGENCY SIRENS | | | | All Comanche Peak Emergency Warning Sirens are inoperable. The cause of | | the failure is unknown, but personnel are working to effect repairs. Hood | | and Somervell counties have been notified. The licensee notified the NRC | | Resident Inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021