Event Notification Report for November 24, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/23/1999 - 11/24/1999 ** EVENT NUMBERS ** 35790 36342 36374 36427 36458 36459 +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35790 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/03/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:44[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/02/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/23/1999| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |DAVID HILLS R3 | | DOCKET: 0707001 |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: THOMAS WHITE | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour | | report) | | | | "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified | | that numerous sprinkler heads were corroded, affecting 16 sprinkler systems | | in C-337 and one system in C-333, such that the ability of the sprinklers to | | flow sufficient water was called into question. Subsequently, these | | sprinkler systems were declared inoperable, and TSR-required actions | | establishing roving fire patrols were initiated. This deficiency was | | detected during scheduled system inspections conducted by Fire Protection | | personnel. Currently, functionality of the sprinkler heads has not been | | fully evaluated by Fire Protection personnel, and the remaining cascade | | buildings are currently being inspected, and if necessary, this report will | | be updated to identify any additional areas. It has been determined that | | this event is reportable under 10CFR76.120(c)(2) as an event in which | | equipment is disabled or fails to function as designed." The NRC resident | | inspector has been notified of this event. | | | | * * * UPDATE AT 1022 EDT ON 06/04/99 FROM CAGE TO TROCINE * * * | | | | "Two sprinkler heads on system D-1 in C-337 and two sprinkler heads on | | system 27 in C-335 were identified to also be corroded. These were | | identified to the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, | | and determined to require an update to this report by the PSS. It has been | | determined that this event is reportable under 10CFR76.120(c)(2) as an event | | in which equipment is disabled or fails to function as designed." Paducah | | personnel notified the NRC resident inspector of this update. The NRC | | operations officer notified the R3DO (Hills) and NMSS EO (Combs). | | | | * * * UPDATE AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER * * * | | | | "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 | | in C-333 were identified to also be corroded. The PSS was notified of this | | condition at 1300 CDT on 06/17/99 and determined that an update to this | | report was required. It has been determined that this event is reportable | | under 10CFR76.120(c)(2) as an event in which equipment is disabled or fails | | to function as designed." Paducah personnel notified the NRC resident | | inspector of this update. The NRC operations officer notified the R3DO | | (Madera). | | | | * * * UPDATE 1440 EDT 6/18/1999 FROM UNDERWOOD TAKEN BY STRANSKY * * * | | | | "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in | | C-333 were identified to have corrosion. The PSS was notified of this | | condition at 1350 CDT on 06/18/99. The area of the fire patrol for system | | C-15 was expanded to include the two heads identified as corroded. The one | | head on system B-8 was in the area already being patrolled. The PSS | | determined that an update to this report was required." The NRC resident | | inspector has been informed of this update. Notified R3DO (Madera). | | | | * * * UPDATE 1315 EDT 6/25/1999 FROM WALKER TAKEN BY STRANSKY * * * | | | | "Two sprinkler heads on system D-8 and three sprinkler heads on system D-7 | | in C-337 were identified to have corrosion. The PSS was notified of the | | condition on system D-8 at 0125 CDT on 06/25/99 and at 1019 CDT on 06/25/99 | | for system D-7. Both systems were immediately declared inoperable and LCO | | fire patrol actions were implemented. It was determined that an update to | | this report was required." The NRC resident inspector has been informed of | | this update. Notified R3DO (Jordan). | | | | * * * UPDATE 2119 EDT 7/30/1999 FROM CAGE TAKEN BY STRANSKY * * * | | | | "Five sprinkler heads and one sprinkler piping tee on C-337 system D-7 were | | identified to have corrosion. The PSS was notified of these corroded system | | parts and declared the system inoperable at 0931 CDT on 07/30/99. LCO | | required fire patrols of the affected area were initiated. The PSS | | determined that an update to this event report was required." The NRC | | resident inspector has been informed of this update. Notified R3DO | | (Wright). | | | | * * * UPDATE AT 1655 EDT ON 07/31/99 FROM WHITE TAKEN BY STRANSKY * * * | | | | "Two sprinkler heads on C-337 System D-1 were identified to have corrosion. | | The PSS was notified of these corroded system parts and declared the system | | inoperable at 1155 CDT on 7/31/99. LCO required fire patrols of the | | affected area were initiated. The PSS determined that an update to this | | report was required." The NRC resident inspector has been informed of this | | update. Notified R3DO (Wright). | | | | * * * UPDATE AT 1546 EDT ON 08/10/99 FROM WHITE TAKEN BY STRANSKY * * * | | | | "Two sprinkler heads on C-337 system C-15 were identified to have corrosion. | | The PSS was notified of these corroded system parts and declared the system | | inoperable at 1130 CDT on 8/10/99. LCO required fire patrols of the | | affected area were initiated. The PSS determined that an update to this | | report was required." The NRC resident inspector has been informed of this | | update. Notified R3DO (Burgess). | | | | * * * UPDATE AT 1154 EDT ON 08/22/99 FROM WALKER TO POERTNER * * * | | | | Four adjacent sprinkler heads on the C-333 building System B-1 were | | identified to have corrosion. The PSS was notified of the corroded system | | parts and declared the system inoperable at 0918 CDT on 08/22/99. LCO | | required fire patrols were initiated. The NRC Resident Inspector will be | | notified. The NRC Operations Officer notified the R3DO (Clayton). | | | | * * * UPDATE 2015 EDT ON 08/28/99 FROM W. F. GAGE TO S. SANDIN * * * | | | | Two adjacent sprinkler heads on the C-337 building System D-11 were | | identified to have corrosion. The PSS was notified of these corroded system | | parts and declared the system inoperable at 1420 CDT on 08/28/99. LCO | | required fire patrols of the affected area were initiated. Paducah | | personnel informed the NRC Resident Inspector. The NRC Operations Officer | | notified the R3DO (Leach) and NMSS EO (Piccone). | | | | * * * UPDATE 2037 EDT ON 08/29/99 FROM KEVIN BEASLEY TO S. SANDIN * * * | | | | Two adjacent sprinkler heads on the C-337 building System D-15 were | | identified to have corrosion and the PSS declared the system inoperable at | | 0925 CDT on 08/29/99. Also two adjacent heads on the C-337 building System | | D-10 were identified to have corrosion and the PSS declared the system | | inoperable at 1450 CDT. LCO required fire patrols for both of the affected | | areas were initiated in the time frame required by TSR. Paducah personnel | | informed the NRC Resident Inspector. The NRC Operations Officer notified | | the R3DO (Leach) and NMSS EO (Piccone). | | | | * * * UPDATE AT 0930 EDT ON 09/01/99 BY ERIC WALKER TO FANGIE JONES * * * | | | | Add two adjacent sprinkler heads on the C-337 building System D-14 were | | declared inoperable. Paducah personnel informed the NRC Resident Inspector. | | The NRC Operations Officer notified the R3DO (David Hills) and NMSS (Robert | | Pierson). | | | | * * * UPDATE AT 1133 EDT ON 09/08/99 BY TOM WHITE TO FANGIE JONES * * * | | | | Add two adjacent sprinkler heads on the C-331 building System 26 were | | declared inoperable at 2155 CDT on 09/07/99. An LCO required fire patrol | | for the affected area was initiated in the time frame required by the TSR. | | Paducah personnel informed the NRC Resident Inspector. The NRC Operations | | Officer notified the R3DO (Monte Phillips) and NMSS (Josie Piccone). | | | | * * * UPDATE AT 0948 ON 09/30/99 BY ERIC WALKER TO DOUG WEAVER * * * | | | | Add two adjacent sprinkler heads on the C-333 building System B-15 were | | identified to have corrosion and the PSS declared the system inoperable at | | 0815 CDT on 9/30/99. An LCO required fire patrol for the affected area was | | initiated in the time frame required by the TSR. Paducah personnel informed | | the NRC Resident Inspector. The NRC operations officer notified the R3DO | | (Vegel) and NMSS (Cool). | | | | * * * UPDATE AT 1600 ON 10/13/99 BY WALKER TO GOULD * * * | | | | Two adjacent sprinkler heads on the C-333 building System A-11 were | | Identified to have corrosion and the PSS declared the system inoperable at | | 1307 CDT on 10/13/99. An LCO required fire patrol for the affected area was | | initiated in the time frame required by the TSR. Paducah personnel informed | | the NRC Resident Inspector. The NRC operations officer notified the R3DO | | (Madera) and NMSS (Moore). | | | | * * * UPDATE AT 1520 ON 10/19/99 FROM UNDERWOOD TAKEN BY STRANSKY * * * | | | | Six sprinkler heads on the C-337 building System D-16 were identified to | | have corrosion and the PSS declared the system inoperable at 1052 CDT on | | 10/19/99. An LCO required fire patrol for the affected area was initiated | | in the time frame required by the TSR. The NRC Resident Inspector has been | | informed of this update. The NRC Operations Officer notified R3DO | | (Jorgensen). | | | | * * * UPDATE AT 2140 ON 10/19/99 FROM WALKER TAKEN BY STRANSKY * * * | | | | Seven sprinkler heads on the C-337 building System A-7 were identified to | | have corrosion, and another four had been painted over. In addition, three | | adjacent sprinkler heads on the C-337 building System A-8 were identified to | | have corrosion. The PSS declared the systems inoperable at 1900 CDT on | | 10/19/99. An LCO required fire patrols for the affected areas were | | initiated in the time frame required by the TSR. The NRC Resident Inspector | | has been informed of this update. The NRC Operations Officer notified R3DO | | (Wright). | | | | * * * UPDATE AT 1713 ON 10/21/99 FROM CAGE TAKEN BY JOLLIFFE * * * | | | | Four sprinkler heads on the C-337 building System A-5, twelve sprinkler | | heads on the C-337 building System A-8, three sprinkler heads on the C-337 | | building System A-9, and six sprinkler heads on the C-337 building System | | B-8 were identified to have corrosion. On 10/21/99, the PSS declared | | Systems A-5 and A-9 inoperable at 1028 CDT, System A-8 inoperable at 1227 | | CDT and System B-8 inoperable at 1406 CDT. An LCO required fire patrol for | | the affected areas was initiated in the time frame required by the TSR.. | | The NRC Resident Inspector has been informed of this update. The NRC | | Operations Officer notified the R3DO Bruce Jorgensen. | | | | * * * UPDATE AT 2128 ON 10/22/99 FROM ERIC WALKER TAKEN BY JOLLIFFE * * * | | | | At 1400 CDT on 10/22/99, the PSS was notified that numerous corroded | | sprinkler heads were discovered in the C-337 building on sprinkler systems | | B-1, B-3, B-5, B-6, B-7, B-11 and D-17. Due to the number of systems called | | into question, the PSS declared all of the sprinkler systems in C-337 on the | | cell floor (a total of 66 systems) inoperable and TSR required actions | | establishing roving fire patrols were initiated within the required time | | frame. The NRC Resident Inspector has been informed of this update. The | | NRC Operations Officer notified the R3DO Bruce Jorgensen. | | | | * * * UPDATE AT 1239 ON 10/24/99 FROM TOM WHITE TAKEN BY JOLLIFFE * * * | | | | At 1200 CDT on 10/23/99, the PSS was notified that numerous corroded | | sprinkler heads were discovered in the C-337 building on sprinkler systems | | B-13 and B-14 on the ground floor, The PSS declared these systems | | inoperable and TSR required actions establishing roving fire patrols were | | initiated within the required time frame. At 1600 CDT on 10/23/99, the PSS | | was notified that numerous corroded sprinkler heads were discovered in the | | C-337 building on sprinkler systems A-16, B-12, C-8, C-12, C-15, D-5 and D-8 | | on the cell floor, These systems have already been declared inoperable and | | fire patrols are already being performed. The NRC Resident Inspector has | | been notified of this update. The NRC Operations Officer notified the R3DO | | Bruce Jorgensen. | | | | * * * UPDATE AT 1117 ON 10/25/99 FROM W. F. CAGE TAKEN BY SANDIN * * * | | | | At 1940 CDT on 10/24/99, the PSS was notified that numerous corroded | | sprinkler heads had been discovered on High Pressure Fire Water Systems C-4, | | C-5, C-6 and C-8, located in the C-337 building. These systems had | | previously been declared inoperable and fire patrols were already being | | performed at the time of discovery. The NRC Resident Inspector has been | | notified of this update. The NRC Operations Officer notified R3DO | | (Lanksbury) and NMSS (Brain Smith). | | | | * * * UPDATE AT 2235 ON 10/27/99 BY WHITE TAKEN BY MACKINNON * * * | | | | At 1517 CDT on 10/27/99, the PSS was notified that nine corroded sprinkler | | heads had been discovered on High Pressure Fire Water System A-12 located in | | the C-333 building. This system has been declared inoperable and fire | | patrols have been initiated. The NRC Resident Inspector has been notified | | of this update. The NRC Operations Officer notified R3DO (Jordan) and NMSS | | EO (Hickey). | | | | * * * UPDATE AT 2150 ON 10/30/99 BY UNDERWOOD TAKEN BY WEAVER * * * | | | | At 1950 CDT on 10/30/99, the PSS was notified that numerous corroded | | sprinkler heads had been discovered on High Pressure Fire Water Systems A-5, | | A-9, A-11, C-5, and C-7 in the C-333 building. Reference ATR-1 1999-6699 | | and 6702. These systems have been declared inoperable and fire patrols have | | been initiated. Also, due to the number of inoperable sprinkler heads, the | | remaining systems on the cell floor of C-333 were called into question and | | declared inoperable. Fire patrols for the entire cell floor have been | | initialed. The PSS determined that an update to this report was required. | | The NRC Resident Inspector has been notified of this update. The NRC | | Operations Officer notified R3DO (Jordan) and NMSS EO (Hickey). | | | | * * * UPDATE AT 2111 ON 10/31/99 BY UNDERWOOD TAKEN BY WEAVER * * * | | | | At 1412 CDT on 10/31/99, the PSS was notified that five corroded sprinkler | | heads had been discovered on High Pressure Fire Water System 9 in the C-335 | | building. There were two adjacent corroded heads discovered in two separate | | locations and a third individual head at a different location. The system | | was declared inoperable and fire patrols were initiated. The corroded heads | | have since been replaced and the system returned to operable status. The | | NRC Resident Inspector was notified of this update. The NRC Operations | | Officer notified R3DO (Jordan) and NMSS EO (Hickey). | | | | * * * UPDATE AT 2121 ON 11/01/99 BY KEVIN BEASLEY TAKEN BY JOLLIFFE * * * | | | | At 0930 CST on 11/01/99, the PSS was notified that three corroded sprinkler | | heads had been discovered on the High Pressure Fire Water System B-4 in the | | C-337 building. Two of these sprinkler heads are adjacent. Two adjacent | | corroded sprinkler heads were also discovered on the High Pressure Fire | | Water System B-5 in the C-337 building. These systems were declared | | inoperable and fire patrols were initiated. Work has been initiated to | | replace the corroded heads. The NRC Resident Inspector has been notified of | | this update. The NRC Operations Officer notified the R3DO Jim Creed. | | | | * * * UPDATE AT 2143 ON 11/02/99 BY KEVIN BEASLEY TAKEN BY JOLLIFFE * * * | | | | At 1400 CST on 11/02/99, the PSS was notified that numerous corroded | | sprinkler heads had been discovered on High Pressure Fire Water Systems C-8 | | and D-7 in the C-333 building. These systems had been previously declared | | inoperable and fire patrols were being performed at the time of discovery. | | Work has been initiated to replace the corroded heads. The NRC Resident | | Inspector has been notified of this update. The NRC Operations Officer | | notified the R3DO Jim Creed. | | | | * * * UPDATE AT 2110EST ON 11/4/99 FROM ERIC WALKER TO S. SANDIN * * * | | | | "At 1700 on 11/4/99, the Plant Shift Superintendent (PSS) was notified that | | numerous corroded sprinkler heads had been discovered on High Pressure Fire | | Water systems A-16, C-17, D-12, and D-16 in the C-333 building. These | | systems had been previously declared inoperable, and fire patrols were being | | performed at the time of discovery. Work his been initiated to replace the | | corroded heads. The PSS determined that an update to this report was | | required. | | | | "It has been determined that this event is reportable under | | 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to | | function as designed." | | | | The NRC Senior Resident Inspector has been notified of this event. Notified | | R3DO (Creed) and NMSS EO (Hodges). | | | | * * * UPDATE AT 2328 EST ON 11/23/99 FROM WHITE TAKEN BY MACKINNON * * * | | | | At 2240 on 11/22/99, the PSS was notified that numerous corroded sprinkler | | heads had been discovered on High Pressure Fire Water System B-7 and B-8 in | | the C-337 building. These systems were declared inoperable, and fire | | patrols were initiated at the time of discovery. The PSS determined that an | | update to this report was required. | | | | The NRC Resident Inspector was notified of this update by the certificate | | holder. The R3DO (Ron Gardner) was notified by the NRC operations officer. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36342 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/25/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:17[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/24/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/23/1999| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY | | DOCKET: 0707001 |JOSIE PICCONE | +------------------------------------------------+ | | NRC NOTIFIED BY: W. F. CAGE | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADEQUATE HIGH PRESSURE FIRE WATER SYSTEM INSTALLATION IN THE C-337 | | BUILDING | | | | "On 10/24/99, at 2250 CDT, the Plant Shift Superintendent was notified that | | High Pressure Fire Water system D5 in the C-337 building, does not meet | | NFPA Code 13. During a walkdown of the system, two non-conformances were | | noted. The spacing between two of the branch lines exceeds the NFPA 13 | | maximum spacing criteria of 15 feet. It was also noted that the spacing of | | the sprinkler heads on these two branch lines is between 5 to 6 feet. NFPA | | 13 requires the heads to be spaced a minimum of 6 feet apart unless baffles | | have been installed. These heads do not have baffles installed on them. | | This system was inoperable at the time of discovery, and LCO required fire | | patrols were being performed. | | | | "It has been determined that this event is reportable under | | 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to | | function as designed. | | | | "The NRC Resident Inspector has been notified of this event." | | | | | | ***RETRACTION ON 11/23/99 AT 2328 EST FROM WHITE TAKEN BY MACKINNON**** | | | | PGDP Engineering has evaluated this condition and concluded that the spacing | | of the branch lines on this system (C-337 HPFWS D-5) is such that the | | sprinkler spray pattern and coverage area is maintained without the need for | | the center branch line, and the sprinkler can meet its intended safety | | function. The subject non-conformance did not impact the systems ability to | | perform its intended function, and therefore, the 10CFR76.120(c)(2) | | reporting criteria was not met. | | | | The NRC Resident was notified of this retraction by the certificate holder. | | The R3DO (Ron Gardner) and NMSS EO (Joe Holonich) were notified by the NRC | | operations officer. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36374 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: SCIENTECH, INC. |NOTIFICATION DATE: 10/29/1999| |LICENSEE: NUSI |NOTIFICATION TIME: 16:05[EDT]| | CITY: GAITHERSBURG REGION: 1 |EVENT DATE: 10/22/1999| | COUNTY: MONTGOMERY STATE: MD |EVENT TIME: 12:00[EDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/23/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK LESSER R2 | | |VERN HODGE NRR | +------------------------------------------------+ | | NRC NOTIFIED BY: PAUL LOCH | | | HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 REPORT | | | | SCIENTECH, Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined | | that a Basic Component, supplied to Carolina Power & Light Robinson Nuclear | | Plant under CP&L purchase orders 8Q3800CM and 9D3530CJ, contains a deviation | | that is reportable under 10 CFR Part 21. NUSI became aware of this | | potential deviation on October 22, 1999. SCIENTECH, Inc's. President was | | informed October 28, 1999. CP&L is aware of this problem and the components | | have been removed from service. A formal written report will be provided | | within 30 days of this notification. The components, Low Level Amplifier | | M/N:RTL850, P/N:NUS-A002PA-1/3, Rev. 1 (1 ea.) and P/N:NUS-A002PA-1, Rev. 0 | | (12 ea.), were manufactured by NUSI. These components have been supplied to | | no other utility for use in Safety Related Systems. NUSI has opened a 10 | | CFR Part 21 file concerning this component and has numbered it as 21-99-01. | | | | ***UPDATE ON 11/23/99 AT 1431 ET FROM PAUL LOCH TAKEN BY MACKINNON*** | | | | SCIENTECH, Inc.'s subsidiary NUS Instruments, Inc. (NUSI) formal report as a | | follow up to the above preliminary notice which was reported to the NRC on | | October 29, 1999. | | | | AFFECTED FACILITY AND PRODUCT WHICH IS NON-COMPLIANT | | | | The facility is Carolina Power & Light, Robinson Plant. The Basic Component | | is Low Level Amplifier used to process signals from resistance temperature | | detectors (RTD). Then module is NUS Instruments Model No. RTL850. | | | | SUPPLYING FIRM IDENTIFICATION | | | | NUS Instruments, Inc., a wholly owned subsidiary of SCIENTECH, Inc. | | 440 W. Broadway | | Idaho Falls, ID 83402 | | | | DESCRIPTION OF DEFECT AND ASSOCIATED SAFETY HAZARD (INCLUDES THE DATE THAT | | INFORMATION WAS OBTAINED) | | | | NUS Instruments Model RTL850 Low Level Amplifiers were installed in the | | Robinson Plant at Carolina Power & Light as replacement modules for Hagan | | Model 118 modules and NUS Instruments Model RTD850 modules due to the RTL's | | better temperature coefficients. The modules were being used to monitor | | primary plant temperatures of the cold and hot logs to provide Tave and | | DeltaT indications for operators. The lead length compensation circuitry on | | the RTL converter PC board has its polarity inverted. This results in the | | output of the RTL, when configured in three wire mode, to read higher than | | it actually should. The magnitude is dependent upon the range configured, | | the RTD type, the lead resistance and other factors. This error can result | | in actions being taken to control the reactor based upon incorrect | | information. NUS Instruments became aware of this problem on October 2, | | 1999 and a 10 CFR PART 21 log entry was made with the number 21-99-01 | | assigned to it. | | | | CORRECTIVE ACTION THAT HAS BEEN OR IS BEING TAKEN | | | | Corrective action for the basic component is to replace the internal RTL, | | Personality Module (RPM, P/N: NUS-B003PA-3) in all RTL modules with a new | | RPM built to a revised schematic to correct for the inverted polarity in the | | PC board. | | | | NUS Instruments has verified through testing that the units equipped with | | revision 3 RPMs properly compensated for lead length resistance and is | | confident no recurrence of this problem will occur. All affected utilities | | have been notified of this problem and all affected components have been | | recalled (including modules in Non-Safety Related applications) | | | | ESTIMATE OF WHEN CORRECTIVE ACTION WILL BE COMPLETE: | | | | 14 January 2000 | | | | The R2DO (Len Wert) and NRR (Vern Hodge) were notified by the NRC operations | | officer. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36427 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/11/1999| | UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 17:53[EST]| | RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/11/1999| +------------------------------------------------+EVENT TIME: 16:45[CST]| | NRC NOTIFIED BY: SCOTT |LAST UPDATE DATE: 11/23/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LINDA SMITH R4 | |10 CFR SECTION: | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE OF INSIDE AND OUTSIDE CCW CONTAINMENT ISOLATION VALVES. | | | | ON 11/09/99, WHILE IN MODE 5, COLD SHUTDOWN, FOR MID-CYCLE OUTAGE, THE | | OUTSIDE CONTAINMENT ISOLATION VALVE FOR COMPONENT COOLING WATER (CCW) RETURN | | (2CV-5255-1) FAILED TO FULLY CLOSE BASED ON FLOW NOISE DURING THE INITIAL | | STROKE. THE VALVE WAS STROKED 10 TIMES AND APPEARED TO CLOSE ON ALL STROKES | | FOLLOWING THE INITIAL ATTEMPT. ON 11/10/99, THE INSIDE CONTAINMENT | | ISOLATION VALVE FOR CCW RETURN (2CV-5254-2) FAILED TO REACH THE TRAVEL LIMIT | | ON ITS FIRST STROKE. AN IMPROMPTU LEAK TEST USING WATER WITH 2CV-5254-2 IN | | ITS INITIAL POSITION INDICATED 300-500 ML/MIN LEAKAGE VIA THE VALVE SEAT. | | BOTH VALVES WERE OVERHAULED DURING THE REFUELING OUTAGE IN EARLY 1999 AND | | SUCCESSFULLY PASSED POST-MAINTENANCE TESTING. DETERMINATION OF THE CAUSE(S) | | AND RESTORATION OF BOTH VALVES TO AN OPERABLE STATUS WILL BE COMPLETED | | BEFORE PLANT STARTUP. THERE DOES NOT APPEAR TO BE FIRM EVIDENCE CONCERNING | | A TIME OF FAILURE BEFORE THE CONDITIONS WERE DISCOVERED. ON NOVEMBER 11, | | 1999, DURING A REVIEW OF THESE CONDITIONS AFFECTING THE SAME CONTAINMENT | | PENETRATION, IT WAS DETERMINED THAT THEY MET THE REPORTING CRITERION OF 10 | | CFR 5O.72(b)(2)(I) AS A SERIOUS DEGRADATION OF A PRINCIPAL SAFETY BARRIER | | (REACTOR CONTAINMENT) FOUND WHILE SHUTDOWN. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * RETRACTED AT 1030 EST ON 11/23/99 BY TOM SCOTT TO FANGIE JONES * * * | | | | "ARKANSAS NUCLEAR ONE UNIT 2 IS RETRACTING THE REPORT IDENTIFIED AS EVENT # | | 36427 MADE PER 10 CFR 50.72(b)(2)(i) ON NOVEMBER 11, 1999. AFTER COMPLETING | | INSPECTION, TESTING, AND ENGINEERING ANALYSIS OF THE TWO COMPONENT COOLING | | WATER (CCW) SYSTEM CONTAINMENT ISOLATION VALVES, IT HAS BEEN CONCLUDED THAT | | THE OUTSIDE ISOLATION VALVE (2CV-5255-1) WAS OPERABLE IN ITS AS-FOUND STATE | | AND WOULD HAVE BEEN CAPABLE OF ISOLATING THE AFFECTED CONTAINMENT | | PENETRATION DURING THE CURRENT OPERATING CYCLE. THE LEAKAGE THAT CAUSED THE | | INITIAL REPORT OCCURRED DURING A SPECIAL DIFFERENTIAL PRESSURE TEST AFTER | | CCW SYSTEM WATER TEMPERATURE HAD BEEN REDUCED TO LESS THAN THE NORMAL | | OPERATING VALUE. THE LOWER TEMPERATURE CAUSED THE VALVE SEATING MATERIAL TO | | BECOME LESS PLIABLE. NORMAL CCW SERVICE TEMPERATURE RESULTS IN A SOFTER | | VALVE SEAT ALLOWING THE VALVE TO CLOSE FULLY AND SEAL THE PENETRATION. THE | | INSIDE CCW ISOLATION FOR THE SAME PENETRATION (2CV-5254-2) WAS DETERMINED TO | | HAVE BEEN INOPERABLE DUE TO A BINDING OF THE LIMIT DECK GEAR. IT WAS | | RESTORED TO AN OPERABLE STATUS PRIOR TO STARTING PLANT HEATUP. SINCE THERE | | IS NO CREDIBLE DESIGN BASIS ACCIDENT THAT WOULD RESULT IN CCW BEING COOLED | | TO THE POINT WHERE THE PENETRATION WOULD NOT HAVE BEEN ISOLATED. THERE IS | | NO REPORTING CRITERION | | APPLICABLE TO THIS CONDITION." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R4DO (BLAIR SPITZBERG). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36458 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MISSISSIPPI DEPARTMENT OF HEALTH |NOTIFICATION DATE: 11/23/1999| |LICENSEE: MISSISSPPI DEPARTMET OF TRANSPORTATIO|NOTIFICATION TIME: 09:55[EST]| | CITY: REGION: 2 |EVENT DATE: 11/19/1999| | COUNTY: STATE: MS |EVENT TIME: 07:00[CST]| |LICENSE#: MS26101 AGREEMENT: Y |LAST UPDATE DATE: 11/23/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |EDWARD MCALPINE R2 | | |BRIAN SMITH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ROBERT NELSON | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - POSSIBLE DAMAGED TROXLER GAUGE | | | | On 11/19/99 at about 0700 CST, a Mississippi Department of Transportation | | (DOT) truck was involved in an accident. The truck was carrying a Troxler | | Model 4640B Moisture Density Gauge in a locked and chained Type-2 container. | | The container broke free of the chain but remained in the truck during the | | accident. There was no apparent damage to the gauge. The Mississippi | | Department of Health was contacted at about 0800 CST about the accident. | | They recommended that the gauge be leak tested, and DOT is sending the gauge | | to Troxler for testing. | | | | The Mississippi Department of Health contacted NRC Region 2 (Richard | | Woodruff) and discussed this incident with them. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36459 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/23/1999| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 11:07[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/23/1999| +------------------------------------------------+EVENT TIME: 10:30[EST]| | NRC NOTIFIED BY: ARDIE KISINGER |LAST UPDATE DATE: 11/23/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CURTIS COWGILL R1 | |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 +------------------------------------------------------------------------------+ | TRAVERSING INCORE PROBE GUIDE TUBE PRIMARY CONTAINMENT ISOLATION CONTROLS DO | | NOT MEET GENERAL DESIGN CRITERION 56. | | | | The design of the Traversing Incore Probe (TIP) guide tube primary | | containment isolation controls does not meet General Design Criterion 56 for | | lines penetrating primary containment that communicate directly with the | | drywell atmosphere. A failure at the TIP Guide Tube Isolation Ball Valve | | could result in a direct pathway from the Drywell atmosphere to the Reactor | | Building secondary containment. This constitutes a condition that is | | outside the design basis of the plant. | | | | The TIP Ball Valve controls are not designed or qualified for nuclear | | safety-related service and do not meet the requirements of IEEE 279-1971 | | Criteria for Protection Systems. As a result, there can be no assurance | | that multiple failures, resulting in undesired opening of any or all of the | | five guide tube penetrations, would not occur under design basis accident | | conditions. However, the TIP Ball Valve and TIP Shear Valve actuation | | circuits remain operable and continue to be capable of operating as | | containment boundary devices. There remains a high degree of confidence | | that the TIP Ball Valves will remain isolated, when required, and that the | | Shear Valves will be capable of isolating when necessary. | | | | The TIP Ball Valve control is powered through the TIP Drive Mechanism. The | | TIP Drive Mechanism is in the de-energized state (i.e., OFF) during normal | | operating conditions. The TIP Ball Valve will be further disabled by | | removing the power source from the Drive Mechanism when the TIP system is | | not actively in use per Technical Specification Surveillance Requirement | | (SR) 3.3.1.1.8. The Drive Mechanism power will be restored, under | | administrative control, when the TIP system is required for use per SR | | 3.3.1.1.8, and as system maintenance and testing dictate. | | | | This report is applicable to Susquehanna Units 1 and 2. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021