Event Notification Report for September 11, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/08/2000 - 09/11/2000
** EVENT NUMBERS **
37266 37268 37299 37300 37301 37302 37303
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37266 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/28/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 20:17[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/28/2000|
+------------------------------------------------+EVENT TIME: 16:30[EDT]|
| NRC NOTIFIED BY: RICHARD LANGE |LAST UPDATE DATE: 09/08/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETE ESELGROTH R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INOPERABILITY OF THE PASS AND BOTH DIVISION I/II H2O2 MONITORING SYSTEMS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 8/28/2000, at 1630, [the Division] I and [II] Hydrogen/Oxygen (H2O2) |
| Containment Monitoring Systems were declared inoperable. The Division I |
| system was declared inoperable on 8/28/2000, at 0818, for planned |
| maintenance. Subsequently, the Division II system was declared inoperable |
| due to a failed channel check." |
| |
| "In addition, the Post Accident Sampling System (PASS) was previously |
| declared inoperable. With the PASS and both Division I/II H2O2 Monitoring |
| Systems inoperable, this event is reportable in accordance with 10 CFR |
| 50.72(b)(2)(iii)(D)." |
| |
| "Also, on 8/28/2000, at 1905, the Division I H2O2 Monitor was restored to |
| operable [status] following completion of planned maintenance." |
| |
| The licensee stated that the unit remained in a 30-day limiting condition |
| for operation (LCO) and that a 7-day shutdown LCO was exited when the |
| Division I H2O2 Monitor was restored to operable status. |
| |
| The licensee notified the NRC resident inspector. |
| |
| ***** UPDATE/RETRACTION AT 0024 ON 09/08/00 FROM ANTHONY PETRELLI TO LEIGH |
| TROCINE ***** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "On 08/28/00, 1630 EDT, Nine Mile Point Unit 2 reported that Divisions 1 and |
| 2 of the Hydrogen/Oxygen (H2/02) Containment Monitoring Systems were |
| declared inoperable under Event Number 37266." |
| |
| "[The licensee is] retracting that notification based on the fact that the |
| Division 1 H2/O2 monitoring system was removed from service as part of |
| planned maintenance in accordance with approved procedures and plant |
| Technical [Specifications]. During planned maintenance, a discrepancy was |
| found in the Division 1 H2/O2 system. Subsequent evaluation indicated that |
| the condition discovered would not have prevented the system from performing |
| its safety function if called upon. Therefore, this event is not |
| reportable." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Dimitriadis). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37268 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/29/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:36[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/28/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:29[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/09/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH R3 |
| DOCKET: 0707002 |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT |
| |
| "On 8/28/00 at 1529, during implementation of NCSA 0705_076 (Inadvertent |
| Containers) a concern was raised about the maximum distance of spray from a |
| leak from a pressurized pipe. Calculations were reevaluated and the |
| corrected spray distance for the system in question resulted in a distance |
| of 106 feet. This new distance for the system in question is greater than |
| the original implementation distance of 15 feet, which the NCSA had |
| previously predicted for the entire X-705. This is considered a loss of one |
| control. The control considered lost is control #2 which states in part, |
| 'When unattended all potential inadvertent containers shall be: |
| -modified to prevent unsafe accumulation |
| -covered to prevent the in-leakage of spilled materials |
| -oriented to prevent an unsafe accumulation |
| |
| "The PSS(Plant Shift Superintendent) directed the facility custodian to |
| enter an anomalous condition. The system in question was previously shut |
| down prior to recalculation of the spray distance. The same equipment |
| remains shutdown until compliance with NCSA 0705_076 can be determined. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "Safety significance is low. The resulting situation is conservatively being |
| identified as a violation of one control contained in NCSA 0705_076 which |
| requires that all potential inadvertent containers utilized in the X-705 be |
| modified, covered, or oriented to prevent an unsafe accumulation. However, |
| since the system in question maintained its physical integrity and thus no |
| uranium bearing material was involved the safety significance of this event |
| is low. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): |
| |
| "If a sufficient amount of uranium bearing material had leaked, spilled, |
| splashed from the micro filtration system and the resuming material |
| accumulated on/in an inadvertent container, an unsafe geometry could have |
| resulted. If the leaking solution had contained a sufficient amount of |
| uranium, the resulting configuration could have been sufficient for a |
| criticality to occur. it should be noted that the allowed safe geometry and |
| volume limits established in NCSA 0705-076 are based on optimally moderated |
| solution which contains uranium enriched to 100 wt% U235. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC): |
| |
| "The parameter which was violated during this upset was maintaining |
| geometry/volume controls regarding potential accumulation points available |
| on/in nearby inadvertent containers. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| "No uranium-bearing material was actually involved in the upset. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| |
| "NCSA 0705_076 takes credit for the physical integrity of systems which |
| contain uranium bearing materials. NCSA 0705_076 also takes Credit that |
| unsafe volume/geometry containers are either modified, covered or oriented |
| while in areas where uranium bearing material can leak, spill or spray to |
| prevent an unsafe configuration from resulting in the event of a leak. The |
| administrative control #2 was not being followed for the new area identified |
| where uranium bearing materials can leak, spill or spray. The resulting |
| situation is conservatively being identified as a violation of the |
| administrative control in NCSA 0705_076. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| "The PSS (Plant Shift Superintendent) directed the facility custodian to |
| enter an anomalous condition. The system in question was previously shut |
| down prior to recalculation of the spray distance. The same equipment will |
| remain shutdown until NCS (Nuclear Criticality Safety) can assist in |
| determination of operability of that system and compliance with NCSA |
| 0705_076." |
| |
| The NRC resident inspector has been informed of this event. |
| |
| * * * UPDATE 1021EDT ON 9/9/00 FROM JEFF CASTLE TO S. SANDIN * * * |
| |
| "9/9/00 - Update #1 - An engineering evaluation (EVAL-PS-2000-0415) of the |
| system and pumps associated with implementation of NCSA_0705_076 identified |
| that the spray distances used to originally determine the reportability of |
| this event were excessive. The original distance (15 feet) used to implement |
| this NCSA has since been identified to adequately bound the credible |
| scenarios for solutions spraying from various systems in the X-705. This |
| issue would not have been reportable based on the newly acquired information |
| as a result of the recent technical review." |
| |
| The NRC resident inspector and DOE site representative have been informed. |
| Notified R3DO(Shear). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37299 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/08/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 15:39[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/08/2000|
+------------------------------------------------+EVENT TIME: 13:30[EDT]|
| NRC NOTIFIED BY: PAUL UNDERWOOD |LAST UPDATE DATE: 09/08/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE |
| |
| "At 1330 on 09/08/00, HPCI Flow Controller, 1E41-R612, was observed to be |
| exhibiting erratic indication of flow. Flow indication was oscillating from |
| 0 to >500 gpm with HPCI in its standby condition. Investigation is |
| continuing." |
| |
| The NRC resident inspector will be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37300 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/09/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:21[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/08/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/09/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING SAFETY SYSTEM ACTUATION |
| |
| "On 9/8/2000 at 2000 hours a safety system actuation occurred in the X344 |
| building. Autoclave #4 was in Mode II 'Heating' when the High Condensate |
| Level Shutoff safety system actuated. Per TSR 2.1.3.7, the autoclave was |
| placed in Mode VII 'Shutdown', a mode in which the High Condensate level |
| Shutoff system is not required, and declared inoperable. This is being |
| reported as a valid safety system actuation. An engineering evaluation has |
| been initiated to review the system conditions that surrounded the actuation |
| of the safety system." |
| |
| Operations notified both the NRC resident inspector and DOE site |
| representative. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37301 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CROW BUTTE RESOURCES |NOTIFICATION DATE: 09/10/2000|
|LICENSEE: CROW BUTTE RESOURCES |NOTIFICATION TIME: 09:52[EDT]|
| CITY: CRAWFORD REGION: 4 |EVENT DATE: 09/09/2000|
| COUNTY: STATE: NE |EVENT TIME: 18:30[CDT]|
|LICENSE#: SUA1534 AGREEMENT: Y |LAST UPDATE DATE: 09/10/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |DANIEL GILLEN NMSS |
+------------------------------------------------+E. WILLIAM BRACH NMSS |
| NRC NOTIFIED BY: MIKE GRIFFIN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONDITION OF LICENSEE REPORT INVOLVING A MONITOR WELL EXCURSION |
| |
| RESULTS OF SAMPLES REPORTED AT 1830MDT ON 9/9/00 CONFIRMED THAT FOUR |
| PARAMETER SINGLE UPPER CONTROL LIMITS (UCLs) AND THE FIFTH MULTIPLE UCL |
| WERE EXCEEDED IN SHALLOW MONITOR WELL SM6-12. |
| |
| PARAMETERS /UCLs/ MEASURED VALUES[UNITS] ARE: |
| |
| SODIUM /36/ 43 |
| [milligrams/liter] |
| SULFATE /19/ 85 |
| [milligrams/liter] |
| CHLORIDES /7/ 55 |
| [milligrams/liter] |
| CONDUCTIVITY /736/ 910 |
| [microMHOs/cm] |
| ALKALINITY /290/ 294 |
| [milligrams/liter] |
| |
| THE LICENSEE WILL DISCUSS POSSIBLE CORRECTIVE ACTIONS WITH THEIR HYDROLOGIST |
| AND GEOLOGISTS IN THE MORNING. THIS COULD INCLUDE DRILLING SAMPLE TEST |
| WELLS. |
| |
| THE LICENSEE WILL NOTIFY THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY |
| AND THE NRC PROJECT MANAGER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37302 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 09/10/2000|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 19:55[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/2000|
+------------------------------------------------+EVENT TIME: 16:28[EDT]|
| NRC NOTIFIED BY: BENJAMIN HUNT |LAST UPDATE DATE: 09/10/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC START OF TURBINE DRIVEN AUXILIARY FEEDWATER PUMP |
| |
| "At 1628 hours on 9/10/2000, with the reactor in Mode 5 for a refueling |
| outage; Watts Bar engineering reported preliminary results of an |
| investigation into the inadvertent start of the turbine driven auxiliary |
| feedwater pump. At approximately 0200 hours on 9/10/2000, operators found |
| the auxiliary feedwater pump operating without the presence of start signal. |
| Steam generator level was being provided by previously started motor driven |
| AFW pumps and operations secured the turbine driven pump. There was no |
| impact from the event on plant refueling preparations and no safety |
| consequence. |
| |
| "There was no valid AFW start signal in place at the time and plant |
| conditions were not such that a signal was required. Engineering was |
| requested to investigate the event and identified that at about the time of |
| the pump start, maintenance technicians were working in an adjacent part of |
| this rack where the relay believed to have been involved in the actuation is |
| located. A review of the circuit determined that an inadvertent bump of the |
| relay could result in the start of the pump and the independent actuation of |
| turbine driven AFW steam generator level control valves. Based on this |
| information, Operations concluded that based on the preliminary engineering |
| information an invalid start of an ESF train had occurred and declared the |
| event reportable under 10 CFR 50.72(b)(2)(ii) and 50.73(a)(2)(iv). |
| |
| "At the time the pump was found in operation it was known that there was no |
| valid start signal, but it was thought that the issue involved only a single |
| component. Because other S/G level maneuvers were in process independent of |
| the AFW start, it was not recognized at the time that the level control |
| valves were involved in the event. After the preliminary engineering review, |
| it was concluded that although it was an invalid actuation, the event |
| involved a train level actuation and was, therefore, reportable." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37303 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 09/10/2000|
| UNIT: [1] [] [] STATE: MD |NOTIFICATION TIME: 23:02[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/10/2000|
+------------------------------------------------+EVENT TIME: 21:23[EDT]|
| NRC NOTIFIED BY: ROBERT PACE |LAST UPDATE DATE: 09/11/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANTHONY DIMITRIADIS R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO CLOSURE OF MAIN STEAM ISOLATION VALVES |
| |
| An automatic reactor trip/turbine trip occurred due to the spurious closure |
| of both main steam isolation valves (MSIVs). The spurious MSIV closure was |
| the result of a failed logic module in the engineered safety features |
| actuation system (ESFAS). All control rods inserted following the trip, and |
| all systems functioned as expected. The auxiliary feedwater (AFW) system |
| automatically started as designed following the trip. The unit is currently |
| stable in Hot Standby with decay heat being removed through steam released |
| via the steam generator atmospheric dump valves. Steam generator water |
| levels are being maintained by the AFW system. |
| |
| The licensee anticipates that replacement of the logic module and |
| establishment of decay heat removal via the main condenser will occur within |
| the next few hours. The NRC resident inspector has been informed of this |
| event by the licensee. The licensee reported that nearby residents have |
| contacted emergency services regarding the noises caused by the steam |
| release through the atmospheric dump valves. The licensee plans to make a |
| press release regarding this event. |
| |
| * * * UPDATE 0428EDT ON 9/11/00 FROM ROBERT PACE TO S. SANDIN * * * |
| |
| The MSIVs were reopened and the main condenser placed back in service at |
| 0420EDT for decay heat removal. Preparations are underway to restore one |
| main feedwater pump and secure the AFW system. Notified R1DO(Dimitriadis). |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Wednesday, March 24, 2021