Home
> NRC Library
> Document Collections
> Reports Associated With Events
> Event Notification Reports > 1999
Event Notification Report for April 7, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/06/1999 - 04/07/1999 ** EVENT NUMBERS ** 35507 35547 35548 35549 35550 35551 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35507 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/25/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:36[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/24/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/06/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND R3 | | DOCKET: 0707002 |ROBERT PIERSON NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ERIC SPAETH | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TSR allowed one of two smoke detectors to be inoperable during withdrawal | | operations when both smoke detectors have to be operable during withdrawal | | operations. | | | | On March 10, 1999, Operations personnel identified a deficiency in a TSR | | requirement for the Pigtail line Isolation System at ERP (extended range | | product), LAW (low assay withdrawal), and TAILS, (TSR 2.5.3.4). The TSR | | required action allowed continued withdrawal operations if one (1) smoke | | detector was inoperable. The Pigtail Line Isolation System requires two (2) | | Pyrotronics Smoke Detectors to actuate for the isolation valve to close. | | Operation personnel initiated a Compensatory Action (CA-99-009) for this | | anomaly to isolate the withdrawal cylinder and manifold per TSR 2.5.3.4b if | | one smoke detector is declared inoperable. | | | | Initially there was no evidence that the Pigtail Line Isolation System had | | been allowed to operate any applicable mode (modes II or III) with one or | | more inoperable smoke head. As a follow up investigation to this | | deficiency, a search of the BPS system (problem report database) was | | conducted. This search identified that on July 8, 1998, a Pyrotronic smoke | | head at the Law IA withdrawal position had been declared inoperable and | | cylinder filling operations had been allowed to continue. | | | | This event is reportable due to a Safety System required by the TSR not | | being available or operable and no redundant equipment was available to | | perform the required safety function. | | | | The NRC Resident Inspector was notified of this event by the certificate | | holder. | | | | * * * UPDATE at 1645EDT on 4/6/99 from Keith Williamson to S.Sandin * * * | | | | "On April 6, 1999 at 0850, the Plant Shift Superintendent retracted the | | above event. Based on completion of Engineering Evaluation | | EVAL-OS-1999_0202 Rev. 0, the plant has determined that the system would | | have performed its designed safety function in this particular instance." | | | | The certificatee informed the NRC Resident Inspector and the DOE Site | | Representative. Notified R3DO(Burgess) and NMSS EO(Camper). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35547 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/06/1999| | UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 06:01[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 04/06/1999| +------------------------------------------------+EVENT TIME: 01:50[CDT]| | NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 04/06/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |TOM STETKA R4 | |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 N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT INITIATION OF DIVISION 1 STANDBY SERVICE WATER DURING | | PERFORMANCE OF COLD SHUTDOWN VALVE STROKE TESTING | | | | The following text is a portion of a facsimile received from the licensee: | | | | "At 0150 [CDT], on April 6, 1999, with the plant in Mode 5 (Refueling), | | Division One Standby Service Water initiated due to Reactor Component | | Cooling Water low pressure." | | | | "The low-pressure condition was inadvertently created during the performance | | of cold shutdown valve stroke testing." | | | | "The Division One Standby Service Water System is not required to be | | OPERABLE in the current plant MODE; however, the system was in standby and | | responded as expected. Operators returned the system to a standby line | | up." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35548 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/06/1999| | UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 08:00[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/06/1999| +------------------------------------------------+EVENT TIME: 07:00[EDT]| | NRC NOTIFIED BY: DON KOSLOFF |LAST UPDATE DATE: 04/06/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRUCE BURGESS R3 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Cold Shutdown |0 Cold Shutdown | |2 N N 0 Cold Shutdown |0 Cold Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL COMPROMISE OF SAFEGUARDS INFORMATION. | | | | At 0700 EDT on 04/06/99, a potential compromise of safeguards information | | was discovered. Immediate compensatory actions were taken upon discovery. | | (Contact the NRC operations officer for additional details and for licensee | | contact information.) | | | | This issue was reported as a 1-hour event notification in accordance with 10 | | CFR 73.71(b)(1), Appendix G. | | | | The licensee plans to notify the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35549 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 04/06/1999| | UNIT: [] [3] [] STATE: PA |NOTIFICATION TIME: 10:27[EDT]| | RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 04/06/1999| +------------------------------------------------+EVENT TIME: 09:50[EDT]| | NRC NOTIFIED BY: JIM KOVALCHICK |LAST UPDATE DATE: 04/06/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |FRANK COSTELLO R1 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A VULNERABILITY THAT COULD HAVE ALLOWED UNDETECTED ACCESS TO A | | VITAL AREA | | | | The licensee discovered a safeguards system degradation related to a vital | | area door. Compensatory actions were taken upon discovery. (Contact the | | NRC operations officer for additional details.) | | | | This issue was reported as a 1-hour report event notification in accordance | | with 10 CFR 73.71(b)(1). | | | | The licensee plans to notify the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35550 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/06/1999| | UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 11:46[EDT]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/06/1999| +------------------------------------------------+EVENT TIME: 11:00[EDT]| | NRC NOTIFIED BY: ALAN HALL |LAST UPDATE DATE: 04/06/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |WALTER RODGERS R2 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |97 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VERY SMALL THROUGH WALL LEAKS ON ECCS SUCTION LINES REQUIRE PLANT SHUTDOWN | | | | While the mechanical people were making a normal plant walkdown, they | | discovered very small through wall leaks on both emergency core cooling | | system (ECCS) suction lines. The leaks are downstream of the motor operated | | isolation valves just after the splitter for the connection to the refueling | | water tank. Both leaks were discovered due to boric acid buildup on the | | '2A' and '2B' ECCS suction lines. The plant has entered Technical | | Specifications 3.5.2, 3.5.3, and 3.0.3 which requires plant shutdown to cold | | shutdown. The plant is in the process of shutting down and expects to be | | shutdown until the problems are corrected. | | | | The licensee notified the NRC Resident Inspector. | | | | * * * UPDATE at 1729EDT on 4/6/99 from Alan Hall to S. Sandin * * * | | | | "Following discussion with NRR and Region II if the as-found condition of | | the low pressure piping, FPL has performed an OPERABILITY evaluation of the | | flawed piping in accordance with Generic Letters 91-18 and 90-05 and | | concluded that the ECCS piping is OPERABLE. FPL exited the LCOs and secured | | the downpower of unit 2 as of 1640 on 4/6/99 following Facility Review Group | | and management review of the OPERABILITY evaluation. As discussed with the | | NRC, FPL will submit a relief request in a timely manner." | | | | Unit 2 is currently at 28% power. The licensee intends to increase and hold | | power at 50% for grid stabilization. The licensee informed the NRC | | Resident Inspector. Notified R2DO(Rodgers). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35551 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/06/1999| | UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 14:32[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/06/1999| +------------------------------------------------+EVENT TIME: 11:00[CDT]| | NRC NOTIFIED BY: BOB PELL |LAST UPDATE DATE: 04/06/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID GRAVES | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 CONTAINMENT AIRLOCK DETERMINED INOPERABLE DURING LAST REFUELING | | OUTAGE | | | | "On 10/7/98 during the 2RE06 Refueling outage in Unit 2, The Temporary | | Modification used to return power to the Reactor Containment Building (RCB) | | personnel airlock did not adequately cover all components necessary to | | enable the Instrument Air (IA) Supply Solenoids to be OPENED (IA is a | | required support system used to pressurize the airlock door seals). | | Therefore, instrument air could not be supplied to the airlock seals within | | 30 minutes as required by Technical Specification (TS) 3.9.4.b. TS 3.9.4 | | required one airlock door capable of being closed within 30 minutes. During | | this time period, when the airlock door was inoperable core alterations were | | performed. This ACTION was in violation of TS 3.9.4.b. | | | | "This condition is being reported under Section 2G of the Operating License | | (NPF-80)." | | | | This condition was discovered while implementing the same Temporary | | Modification on Unit 1. The licensee is conducting a root cause | | investigation following which appropriate corrective actions will be | | identified. | | | | The licensee informed the NRC Resident Inspector. | +------------------------------------------------------------------------------+