Event Notification Report for November 5, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/04/1999 - 11/05/1999
** EVENT NUMBERS **
35790 36263 36394 36395 36396 36397 36398 36399 36400 36401
+------------------------------------------------------------------------------+
|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: 11/04/1999|
| 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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36263 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SWAGELOK COMPANY |NOTIFICATION DATE: 10/06/1999|
|LICENSEE: SWAGELOK COMPANY |NOTIFICATION TIME: 09:48[EDT]|
| CITY: Solon REGION: 3 |EVENT DATE: 10/04/1999|
| COUNTY: STATE: OH |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 11/04/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN KINNEMAN R1 |
| |BRIAN BONSER R2 |
+------------------------------------------------+JOHN JACOBSON R3 |
| NRC NOTIFIED BY: BRUCE FLUSCHE (Fax) |KRISS KENNEDY R4 |
| HQ OPS OFFICER: LEIGH TROCINE |VERN HODGE NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSSIBLE 10-CFR-PART-21 REPORT REGARDING A POSSIBLE DEFECT IN A SWAGELOK |
| TUBE FITTING |
| |
| The following text is a portion of a facsimile submitted by Swagelok |
| Company: |
| |
| "This is a preliminary notification of a possible defect in a Swagelok tube |
| fitting, part number SS-400-3-4TTM, male branch tee. A drawing of the part |
| is included with this notification. We are also notifying each of the |
| involved utilities." |
| |
| "We became aware of this on October 4, 1999." |
| |
| "The defect is a crack in the seat of the fitting. We are continuing our |
| analysis of the part and will provide further details in accordance with NRC |
| timetables." |
| |
| "[The] following are the six utilities to whom we have sold these parts: |
| |
| Georgia Power [Company], Plant Vogtle, ... , 10 pcs. ... [;] |
| Duke Power Company, Oconee Nuclear Station, ... ,100 pcs. ... [;] |
| Arizona Public Service Co., Palo Verde Nuclear Generating Station, ... , 15 |
| pcs. ... [;] |
| North Atlantic Energy Service Co., ... , Seabrook Station, ... ,10 pcs. ... |
| [;] |
| Virginia Power, Surry Power Station, ... , 3 pcs. ... [; and] |
| Omaha Public Power District, Ft. Calhoun Nuclear Station, ... , 10 Pcs. ... |
| ." |
| |
| (Call the NRC operations officer for Swagelok contact information.) |
| |
| * * * UPDATE 1553 EST ON 11/4/99 FROM BRUCE FLUSCHE TO S. SANDIN * * * |
| |
| The following information was received via fax: |
| |
| "We are writing further to our preliminary notification on October 6,1999 |
| about a possible defect in a Swagelok tube fitting, part number |
| SS-400-3-4TTM, male branch tee. |
| |
| "The utilities to whom we have sold this are repeated in the appendix to |
| this letter. |
| |
| "As we reported earlier, the defect is a crack in the seat of the fitting. |
| This crank resulted from overheating during the resistive type heated |
| forging process; it was not a defect in the raw material. The estimated per |
| cent of forgings that have this condition is less than 0.03%. |
| |
| "This forging was processed in December of 1996. Since the middle of 1998 |
| we have required liquid penetrant testing on all resistive type heated |
| forgings. |
| |
| "If there are any questions, please do not hesitate to contact us." |
| |
| Notified the R1DO (Mohamed Shanbaky), R2DO (Pierce Skinner), R3DO (James |
| Creed), and R4DO (Claude Johnson). Faxed to NRR part 21 (Vern Hodges). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36394 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/04/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:56[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/03/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:45[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/04/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: McCLEERY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LEGACY ITEM - TWO ERRORS OCCURRED ON A U235 MASS LOG |
| |
| NRC BULLETIN 91-01 24 HOUR NOTIFICATION |
| |
| On 1/3/99 at 1645 hrs the Plant Shift Superintendent (PSS) was notified that |
| a Nuclear Criticality Safety Approval |
| (NCSA) requirement was not being performed in the X-710 ES&H Analytical |
| Labs. Building personnel identified that two errors had occurred on the U235 |
| mass log which is used for NCSA compliance verification. The first error was |
| a [non-conservative] mathematical addition error causing an incorrect total |
| to be reported on the Mass log. The second error was that a sample container |
| was inadvertently not logged in on the mass log. This NCS anomaly is a |
| legacy item in that this error was entered into the log on March of 1998. |
| |
| Requirement 1 of NCSA-0710_25.AOO states in part; Samples in any room |
| enriched to 1% or greater U235, will be limited to one group of (30g U235) |
| per room. This will be ensured by maintaining a room inventory log of U235 |
| mass in labeled containers. Each log entry will consist of the U235 mass |
| value plus analytical uncertainty and will be: |
| |
| a. made by a knowledgeable person "PRIOR" to bring the samples into the |
| room, and |
| b. verified by a second knowledgeable person "PRIOR" to bringing the samples |
| into the room. |
| |
| Both errors were in the non-conservative direction, but the total mass limit |
| for the room 30g U235 was never exceeded [actual amount was 28.851g]. These |
| errors show that both the first and second contingency control were |
| violated. |
| |
| At the direction of the Plant Shift Superintendent the requirements for an |
| NCS anomalous condition were initiated and the area boundaried off |
| |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL. CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| SAFETY SIGNIFICANCE OF THE EVENT: |
| |
| The safety significance of the event is low. The U235 mass in the group was |
| never above the NCSA requirement. However, both controls on the mass |
| requirement were violated. |
| |
| POTENTIAL CRITICALITY PATHWAY INVOLVED (BRIEF SCENARIOs OF HOW CRITICALITY |
| COULD OCCUR): |
| |
| Repeated mass violations could result in a greater than safe mass being in |
| the room. Since moderation is not controlled, a spacing violation could have |
| allowed the uranium to reach a critical configuration. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.); |
| |
| Mass, volume, and interaction (spacing) was controlled. By incorrectly |
| logging the mass of one sample and neglecting to log the mass of a separate |
| sample, both the first and second contingency controls was violated. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDED PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| The highest mass of U235 in the group was 28.851 grams. Enrichment of this |
| operation is not controlled, but it is not expected to be 10% assay due to |
| plant production limitations. The form of the uranium varies based on the |
| specific samples involve, although uranyl fluoride, uranyl nitrate, uranium |
| tetra fluoride and other forms would be expected. This represents less than |
| 4% of critical mass. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(s) OR CONTROL SYSTEM(s) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| The control on this process included a first and second check to ensures the |
| U235 mass of each sample is recorded and a running total maintained to |
| prevent exceeding a limit of 30 grams U235. Both the first and second check |
| were violated in two separate cases. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| At the direction of the Plant Shift Superintendent the requirements for an |
| NCS anomalous condition were initiated and the are boundaried off. Lab |
| personnel made corrections to log error and mass was verified at 1700 |
| hours. |
| |
| The NRC Resident Inspector was notified of this legacy event by the |
| certificate holder. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36395 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 11/04/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 14:09[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/04/1999|
+------------------------------------------------+EVENT TIME: 11:36[CST]|
| NRC NOTIFIED BY: TODD STRAIN |LAST UPDATE DATE: 11/04/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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
+------------------------------------------------------------------------------+
| INADVERTENT SAFEGUARDS ACTUATIONS DURING PLANNED ELECTRICAL MAINTENANCE |
| |
| "AT 1136CST ON 11/4/99, SAFEGUARDS 4.16KV BUS '16' DE-ENERGIZED UNEXPECTEDLY |
| WHEN THE OFFSITE SOURCE SUPPLYING THE BUS TRIPPED. THE BUS WAS |
| AUTOMATICALLY REPOWERED WITH THE AUTOMATIC CLOSURE OF ANOTHER OFFSITE SOURCE |
| BREAKER. [THE] CAUSE OF THE DE-ENERGIZATION WAS AN INADVERTENT 'CT11' |
| (NORMAL OFFSITE SUPPLY TO SAFEGUARDS BUS '16') LOCKOUT, DUE TO A BUMPED |
| RELAY WHILE RE-INSTALLING A 4KV BREAKER INTO ITS CUBICLE. |
| |
| "AUTO ACTUATIONS AS A RESULT OF THE MOMENTARY DE-ENERGIZATION WERE: |
| |
| 1. AUTOSTART OF THE OPPOSITE TRAIN COMPONENT COOLING WATER PUMP, AND |
| 2. AUTO SEQUENCING OF BUS '16' TO AN ALTERNATE SOURCE." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36396 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: PRINCETON MEDICAL CENTER |NOTIFICATION DATE: 11/04/1999|
|LICENSEE: PRINCETON MEDICAL CENTER |NOTIFICATION TIME: 14:30[EST]|
| CITY: PRINCETON REGION: 1 |EVENT DATE: 11/04/1999|
| COUNTY: STATE: NJ |EVENT TIME: 09:15[EST]|
|LICENSE#: 29-06750-01 AGREEMENT: N |LAST UPDATE DATE: 11/04/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EDWARD BACZA | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL MISADMINISTRATION INVOLVING DISLODGED BRACHYTHERAPY SOURCE |
| |
| AT APPROXIMATELY 0915EST AN ELDERLY FEMALE PATIENT NOTIFIED HOSPITAL STAFF |
| THAT A BRACYTHERAPY SOURCE (Cs-137 - 21.8 MILLIGRAM RADIUM EQUIVALENT) HAD |
| BECOME DISLODGED. HOSPITAL STAFF CONTACTED THE PHYSICIAN THAT HAD INSERTED |
| THE SOURCE AND WAS INSTRUCTED TO RELOCATE THE APPLICATOR TO THE FOOT OF THE |
| BED. THE HOSPITAL PHYSICIST ESTIMATES THAT THE SOURCE WAS IN THE VICINITY |
| OF THE PATIENT'S THIGH FOR APPROXIMATELY 15 MINUTES AND AT THE FOOT THE BED |
| FOR ANOTHER 18 MINUTES BEFORE BEING PLACED IN A LEAD PIG. THE ATTENDING |
| PHYSICIAN DOES NOT INTEND ANY ADDITIONAL EXPOSURE SINCE THE SOURCE REMAINED |
| IN PLACE FOR 18.45 OF THE 22.79 HOURS PRESCRIBED. NO ADVERSE HEALTH |
| CONSEQUENCES ARE EXPECTED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36397 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 11/04/1999|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 15:06[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 11/04/1999|
+------------------------------------------------+EVENT TIME: 10:00[EST]|
| NRC NOTIFIED BY: BRIAN STETSON |LAST UPDATE DATE: 11/04/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL ROD WITHDRAWAL LIMITER DISCOVERED INOPERABLE DURING ROD TESTING |
| |
| "It has been discovered that following the insertion of a control rod, the |
| Rod Withdrawal Limiter is inoperable until that control rod is deselected |
| and reselected from the Rod Control & Information System control panel. |
| |
| "We have reasonable knowledge that we have withdrawn control rods in the |
| past, while the Rod Withdrawal Limiter has been inoperable. We have specific |
| knowledge that on 10/31/99, a control rod was withdrawn with the Rod |
| Withdrawal Limiter inoperable. This is a violation of Technical |
| Specification 3.3.2.1 Action A.1. |
| |
| "This report is required due to the requirements of the Operating License |
| for a violation of Technical Specifications." |
| |
| This condition was discovered by operators during performance of control rod |
| speed adjustment of a single rod. Control rod motion continued past the |
| withdrawal notch limit of 4. The operator immediately let go of the |
| withdraw push button causing the rod to stop at the notch 6 position. The |
| licensee suspects this condition has existed since initial construction and |
| has imposed administrative controls specifically referencing Technical |
| Specifications requirements. |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36398 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/04/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:04[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/04/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:25[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/04/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE DURING AUTOCLAVE HEATUP |
| |
| "ON 11/4/99 AT 0825 [HOURS] OPERATORS IN THE X-344 NOTICED CONDENSATE |
| LEAKING FROM THE AUTOCLAVE #2 LOCKING RING AREA WHILE IN MODE II (HEATING). |
| THE AUTOCLAVE WAS PLACED IN MODE VII (SHUTDOWN) 15 MINUTES AFTER THE |
| DISCOVERY OF THE LEAK. INITIAL INVESTIGATION SHOWS A PIECE OF COPPER TUBING |
| MAY HAVE BEEN LODGED ON THE SEALING SURFACE OF THE LOCKING RING. THE |
| AUTOCLAVE WAS MADE INOPERABLE IMMEDIATELY. THERE WAS NO ACTUATION OF A |
| SAFETY SYSTEM DURING THIS OPERATION. THIS IS REPORTABLE UNDER CONDITION |
| 76.120 (C)(2)(i), AN EVENT IN WHICH EQUIPMENT IS DISABLED OR FAILS TO |
| FUNCTION AS DESIGNED WHEN THE EQUIPMENT IS REQUIRED BY A TSR [TECHNICAL |
| SAFETY REQUIREMENT] TO PREVENT RELEASES. |
| |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." |
| |
| OPERATION'S STAFF NOTIFIED THE NRC RESIDENT INSPECTOR AND DOE SITE |
| REPRESENTATIVE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36399 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/04/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 18:29[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/04/1999|
+------------------------------------------------+EVENT TIME: 14:00[CST]|
| NRC NOTIFIED BY: JOHN SELL |LAST UPDATE DATE: 11/04/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TWO MAIN STEAM SAFETY VALVES (MSSVs) EXCEEDED ACCEPTANCE CRITERIA DURING |
| SETPOINT TESTING |
| |
| "DURING THE POINT BEACH NUCLEAR PLANT (PBNP) UNIT 1 R25 OUTAGE, TWO (2) MAIN |
| STEAM SAFETY VALVES WERE SENT TO WYLE LABS FOR SETPOINT TESTING. MS-02013 |
| LIFTED AT 2.4% ABOVE NAMEPLATE SETPOINT OF 1125 PSIG. THE OWNER ACCEPTANCE |
| CRITERIA IS 1.93%. THIS VALVE DID NOT EXCEED THE ASME ACCEPTANCE CRITERIA |
| OF 3%. |
| |
| "MS-02012 LIFTED AT 3.7% ABOVE THE NAMEPLATE SETPOINT OF 1125 PSIG. THIS |
| EXCEEDS BOTH THE OWNER ESTABLISHED ACCEPTANCE CRITERIA AND THE ASME XI |
| CRITERIA. |
| |
| "PBNP TECH SPECS REQUIRE AN ADDITIONAL NUMBER OF VALVES TO BE TESTED EQUAL |
| TO THE NUMBER ORIGINALLY TESTED. SINCE FOUR (4) MSSVs WERE SENT FOR TESTING |
| THIS OUTAGE, THE REMAINING FOUR (4) MSSVs WILL NEED TO BE TESTED. |
| |
| "BOTH MS-02012 AND MS-02013 MAY HAVE HAD THEIR SETPOINTS ADJUSTED |
| INCORRECTLY IN 1995." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36400 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:07[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/04/1999|
+------------------------------------------------+EVENT TIME: 20:30[CST]|
| NRC NOTIFIED BY: RICK ROBBINS |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 0.25 INCH LONG CRACK WAS FOUND ON "1A" STEAM GENERATOR HEAD DRAIN VALVE. |
| |
| During a liquid penetrant examination of a weld on the top side of valve |
| 1R-526A, "1A" Steam Generator head drain, a 0.25" long crack was found. |
| Appears o be a crack in the weld metal only, through wall of the Reactor |
| Coolant System pressure boundary. |
| |
| During initial screening of this condition at 2030 hours on 11/04/99 it was |
| not considered seriously degraded as no leak was detected while at power |
| (boric acid crystals were found in the vicinity of the valve). Upon further |
| review at 0200 hours on 11/05/99 this 4 hour non-emergency report was made. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36401 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 05:21[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 02:32[CST]|
| NRC NOTIFIED BY: TIM SMITH |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STEAM GENERATOR BLOWDOWN ISOLATION VALVE CLOSED |
| |
| At 0232 on 11/05/99 Radiation Monitor R-19 Steam Generator liquid failed. |
| This failure caused the Steam Generator blowdown isolation valves; |
| BT-2A/MV-32077 Steam Generator blowdown isolation valve A1, BT-2B/MV-32079 |
| Steam Generator blowdown isolation valve B1, BT-3A/MV-32078 Steam Generator |
| blowdown isolation valve A2, and BT-3B/MV-32080 Steam Generator blowdown |
| isolation valve B2, to close. These valves have a containment isolation |
| function for a Main Steam Line Rupture within containment. Their Post - |
| Loss of Coolant Accident function is to provide Steam Generator isolation. |
| |
| |
| The monitor failure will not allow the re-establishment of Steam Generator |
| blowdown flow. Plant Chemistry and Instrument and Control personnel have |
| been contacted to determine corrective actions and to repair the radiation |
| monitor. Radiation Monitor R-15, Air Ejector Exhaust, is indicating normal |
| readings and is being monitored by operations. Local indication of |
| Radiation Monitor R-19 are the normal count rate. Actual problem appears to |
| be the Control Room indication of R-19 failed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021