Event Notification Report for May 21, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/20/1999 - 05/21/1999
** EVENT NUMBERS **
35720 35726 35739 35744 35745 35746 35747 35748
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35720 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 05/15/1999|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 18:25[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 05/15/1999|
+------------------------------------------------+EVENT TIME: 14:56[CDT]|
| NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 05/20/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP/REACTOR SCRAM DURING MAIN TURBINE MECHANICAL OVERSPEED TESTING |
| |
| While the licensee was resetting the mechanical overspeed trip during main |
| turbine mechanical overspeed testing, the main turbine tripped which |
| generated an automatic reactor scram. All control rods fully inserted into |
| the core. The resulting scram caused reactor vessel water level to lower to |
| below the primary containment isolation system group 2 (drywell), group 3 |
| (reactor water cleanup), group 6 (ventilation), and group 8 (traversing |
| incore probes) isolation setpoint resulting in those isolations along with |
| control room emergency ventilation system and the standby gas treatment |
| system initiations. Reactor feedwater is maintaining reactor vessel water |
| level, and the turbine bypass valves are maintaining reactor vessel |
| pressure. All emergency core cooling systems and the emergency diesel |
| generators are fully operable if needed. None of the safety-relief valves |
| opened, and the offsite electrical grid is stable. |
| |
| The licensee is investigating what caused the turbine trip/reactor scram. A |
| Licensee Event Report will be filed with the NRC within 30 days concerning |
| this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 1207 ON 05/20/99 BY JOE BENNETT TO JOLLIFFE * * * |
| |
| During an investigation of the above event, the licensee determined that |
| five main steam relief valves had opened automatically due to high reactor |
| pressure and immediately closed completely following the reactor scram. The |
| licensee plans to include this additional information in their Licensee |
| Event Report on this event. |
| |
| The licensee plans to inform the NRC Resident Inspector of this update. The |
| NRC Operations Officer notified the R2DO Ann Boland. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35726 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. ARMY |NOTIFICATION DATE: 05/17/1999|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 12:03[EDT]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 05/16/1999|
| COUNTY: STATE: IL |EVENT TIME: [CDT]|
|LICENSE#: 12-00722-13 AGREEMENT: Y |LAST UPDATE DATE: 05/20/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRENT CLAYTON R3 |
| |PETER ESELGROTH R1 |
+------------------------------------------------+JOE HOLONICH NMSS |
| NRC NOTIFIED BY: JEFF HAVENER |FEMA, DOE, USDA, HHS FAX |
| HQ OPS OFFICER: FANGIE JONES |EPA, DOT (VIA NRC) FAX |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST OR STOLEN 3-CURIE TRITIUM SOURCE FROM AN M140 ALIGNMENT DEVICE |
| |
| Sometime on 05/16/99 near Watervliet Arsenal (about 35 miles from Albany, |
| NY) at a contractor's facility (Wright Malta Corporation at Wright Malta |
| Station), a break-in occurred. In the facility was a howitzer with an M1A1 |
| collimator (10 curies tritium) and an M140 alignment device (3 curies |
| tritium). The two devices were taken but were recovered on site when the |
| thieves were interrupted on the way out and dropped them. However, the |
| source was missing from the M140 alignment device, and it is unknown whether |
| the source was missing previously or removed and taken by the thieves. The |
| local police are following up on the break-in and theft. The Watervliet |
| Arsenal contacted the State of New York, who in turn notified NRC Region 1. |
| |
| (Call the NRC Operations Officer for additional information.) |
| |
| * * * UPDATE AT 1730 EDT ON 05/19/99 FROM JEFF HAVENNER TO S. SANDIN * * * |
| |
| Additional information received by the licensee on 05/19/99 indicates that |
| an M58 and an M59 aiming post light may also be missing. These are 5 and 4 |
| curies of tritium for a total of 9 curies. The NRC Operations Officer |
| notified R1DO (Eselgroth), R3DO (Clayton), NMSS EO (Haughney) and FEMA, DOE, |
| USDA, HHS, EPA, and DOT (via NRC) by fax. |
| |
| * * * UPDATE AT 1329 EDT ON 05/20/99 FROM JEFF HAVENNER TO MACKINNON * * * |
| |
| Mr Havenner reported that the M58 and M59 aiming post lights containing |
| tritium were not missing but two aiming post lights which do not container |
| radioactive material were missing. The two missing aiming post lights are |
| battery operated. The NRC Operations Officer notified the R1DO (Peter |
| Eselgroth), R3DO (Brent Clayton), NMSS EO (Scott Moore) and FEMA, DOE, USDA, |
| HHS, EPA, and DOT (via NRC) by fax. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35739 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/19/1999|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 13:38[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/1999|
+------------------------------------------------+EVENT TIME: 10:30[EDT]|
| NRC NOTIFIED BY: TIM HEAFNER |LAST UPDATE DATE: 05/20/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-hour Condition of License report involving fire protection barriers. |
| |
| "On May 19,1999 at 1030 hours. McGuire Nuclear Station determined that |
| provisions of the McGuire fire protection program had not been maintained as |
| required by conditions C.(4) (Unit I) and C.(7) (Unit 2) of the McGuire |
| Facility Operating License. |
| |
| "Selected Licensee Commitment 16.9-5 requires that all fire rated assemblies |
| and sealing devices separating |
| 1. Safety from non-safety related areas or, |
| 2. Redundant analyzed post fire safe shutdown equipment or, |
| 3. The Control Complex (Control Room, Cable Rooms, and Battery Rooms) from |
| the remainder of the plant or, |
| 4. Containment from Non-containment areas shall be operable. |
| |
| "Contrary to this, numerous fire barrier penetrations designed to satisfy |
| the above separation criteria for certain containment to non-containment |
| penetrations have been determined to be inoperable. This discovery was made |
| as part of routine surveillance testing. A particular penetration design |
| has been identified to have been installed in non-conformance with the |
| design. The design specifies the incorporation of a fire resistive block |
| material surrounded by a metal frame as the physical penetration which is |
| installed in the wall as a unit. Necessary cables then penetrate through the |
| fire resistive block. Physical penetrations were installed in excess of |
| those actually necessary for transporting cables to accommodate future |
| modifications or other contingencies. Penetrations in these 'blank |
| locations' incorporated a welded steel plate as opposed to the design |
| described above. This configuration has not been qualified as a 3 hour fire |
| rated assembly. |
| |
| "Remedial actions required by Selected Licensee Commitment 16.9-5 have been |
| implemented (fire watches). The ability of the facility to achieve safe |
| shutdown conditions under a postulated design bases fire has not been |
| compromised by the discovered condition. Therefore, McGuire did not operate |
| outside the design basis of the plant. |
| |
| "The resident Inspector has been notified. A follow-up written report will |
| be issued within 14 days. Note that this event is not reportable under the |
| requirements of 10CFR50.72 or 10CFR50.73." |
| |
| * * * UPDATE AT 2101 ON 05/20/99 BY LARRY TUMBLESON AND JULIUS BRYANT TO |
| JOLLIFFE * * * |
| |
| The following is an update to this event: |
| |
| ". . . A particular penetration design was thought to have been installed in |
| non-conformance with design requirements. Specifically, penetrations in |
| 'blank' locations incorporated a welded steel plate as a barrier rather than |
| a fire resistive block material surrounded by a metal frame. Station |
| personnel concluded that this welded steel plate design did not satisfy the |
| requirements of Selected Licensee Commitment 16.9-5. Consequently, these |
| penetrations were declared inoperable and the May 19, 1999 NRC Notification |
| was made. |
| |
| Subsequent to the May 19,1999 notification, further evaluation of the welded |
| steel plate fire barrier penetration design determined that these |
| penetrations do satisfy the requirements of Selected Licensee Commitment |
| 16.9-5. Consequently, these penetrations were operable and the May 19, 1999 |
| NRC notification is retracted. As a result, the remedial actions specified |
| in that notification have been discontinued and a follow up written report |
| will not be issued. The Resident Inspector has been notified," |
| |
| The NRC Operations Officer notified the R2DO Ann Boland. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35744 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/20/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 10:23[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/20/1999|
+------------------------------------------------+EVENT TIME: 10:14[EDT]|
| NRC NOTIFIED BY: BRADSKY |LAST UPDATE DATE: 05/20/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 |0 |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FAILURE OF BOTH SAFETY RELATED CONTAINMENT CUBICAL SUMP AIR DRIVEN PUMPS |
| - |
| |
| ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED |
| CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED |
| TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES |
| BUILDING. A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO |
| THE PUMPS WAS APPROVED ON 5/19/99. ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE |
| DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE |
| SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED |
| AIR PRESSURE. |
| |
| THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS |
| ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING |
| IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING. THE PLANT IS |
| CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT |
| RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL. |
| |
| THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION. AT THIS TIME, IT |
| IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH |
| LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER. |
| |
| THE RESIDENT INSPECTOR WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35745 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/20/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/20/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:40[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/20/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON R3 |
| DOCKET: 0707002 |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - DOE NOTIFIED OF URANIUM BEARING SOLUTION LEAKING FROM A POLYBOTTLE - |
| |
| At 1040 on 05/20/99, the DOE was notified of an off-normal event classified |
| as a Level 3 Nuclear Criticality Safety Incident that occurred in the X-706 |
| West Annex which is regulated by the DOE and operated by USEC under a |
| Regulatory Oversight Agreement. The Site DOE Manager and the DOE Regulatory |
| Oversight Manager were verbally notified. The notification stated the |
| following: |
| |
| At 1800 on 05/19/99, plant personnel discovered a small amount of uranium |
| bearing solution leaking from a small diameter storage container |
| (polybottle) in the HEU cylinder cleaning area of the X-705 West Annex. |
| Plant Nuclear Criticality Safety personnel determined the leak to be a loss |
| of geometry control, such that only one of the double contingency controls |
| remained in place. |
| |
| This event is reportable to the NRC per requirements in the plant's Safety |
| Analysis Report, Section 6.9, Table 1, Criteria P, Miscellaneous: USEC |
| shall notify the NRC of any event or situation, related to the health and |
| safety of the public or onsite personnel, or protection of the environment, |
| for which a news release is planned or notification to other government |
| agencies has been or will be made. Such an event may include an onsite |
| fatality or inadvertent release of radioactively contaminated materials. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35746 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/20/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 14:23[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/01/1975|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: TOM McKEE |LAST UPDATE DATE: 05/20/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - COMPONENT COOLING WATER PIPING IS RUN INSIDE A CRANE WALL (NOT MISSILE |
| PROTECTED) - |
| |
| During a 10CFR50.54(f) review of the UFSAR, the licensee discovered a |
| certain component cooling water (CCW) piping run inside a crane wall (i.e., |
| not missile protected from LOCA generated missiles by the crane wall) [DER |
| 99-0840]. After searching plant records, the licensee has not located any |
| initial engineering documentation justifying the running of piping inside |
| the crane wall. Based on this review, the licensee has concluded that the |
| CCW piping may have been outside the system design basis stated in the UFSAR |
| since original operation of the plant in December 1975. The licensee |
| believes that the design requirement (i.e., protected from LOCA generated |
| missiles) for the system was restored in March 1986 based on the NRC Safety |
| Evaluation for Generic Safety Issue A-2. The Safety Evaluation Report (SER) |
| states, in part, that "dynamic effects associated with postulated pipe |
| breaks in the primary coolant system of this facility need not be a design |
| basis." |
| |
| The licensee has declared the CCW piping operable based on the 1986 SER and |
| is continuing to reconcile the design basis of this issue using the |
| 10CFR50.59 process. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35747 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 05/20/1999|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 15:10[EDT]|
| CITY: PLYMOUTH REGION: 2 |EVENT DATE: 05/19/1999|
| COUNTY: WASHINGTON STATE: NC |EVENT TIME: 12:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/20/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANN BOLAND R2 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM ALBRIGHT, NC DRP | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - 15 YEAR OLD MALE OPENED A FIRE EXIT SIGN AND PARTIALLY REMOVED TRITIUM |
| AMPOULES - |
| |
| ON 05/19/99, JAMES ALBRIGHT, NC DIVISION OF RADIATION PROTECTION (DRP), WAS |
| NOTIFIED THAT A 15 YEAR OLD MALE HAD OPENED A FIRE EXIT SIGN WITH A RAZOR |
| KNIFE AND AT LEAST PARTIALLY REMOVED SOME OF THE TRITIUM AMPOULES (INCIDENT |
| #99-09). ON THE MORNING OF 05/19/99, A DRP SURVEY TEAM RESPONDED. ALL |
| AMPOULES HAVE BEEN ACCOUNTED FOR; NONE WERE DAMAGED OR BROKEN. WIPES TAKEN |
| INDICATE NO CONTAMINATION. THE SIGN AND THE AMPOULES ARE CURRENTLY IN THE |
| POSSESSION OF THE WASHINGTON COUNTY, NC, SHERIFF DEPARTMENT. |
| |
| ARRANGEMENTS WILL BE MADE TO RETURN THE SOURCE AMPOULES TO THE MANUFACTURER. |
| |
| NC DRP CONSIDERS THIS INCIDENT CLOSED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35748 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 05/20/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 22:57[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/20/1999|
+------------------------------------------------+EVENT TIME: 21:37[EDT]|
| NRC NOTIFIED BY: MIKE GWIRTZ |LAST UPDATE DATE: 05/20/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF 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
+------------------------------------------------------------------------------+
| - UNIT 1 TRIP FROM 100% DUE TO NEGATIVE RATE TRIP SIGNAL DUE TO A DROPPED |
| CONTROL ROD - |
| |
| AT 2137 ON 05/20/99, UNIT 1 REACTOR AUTOMATICALLY TRIPPED FORM 100% POWER |
| DUE TO A NUCLEAR INSTRUMENTATION NEGATIVE RATE TRIP SIGNAL. PRELIMINARY |
| INDICATIONS ARE THAT THE NEGATIVE RATE TRIP SIGNAL WAS DUE TO THE LOSS OF |
| THE STATIONARY GRIPPER VOLTAGE TO CONTROL ROD #1A3 DUE TO A BLOWN FUSE FOR |
| UNKNOWN REASONS CAUSING CONTROL ROD #1A3 TO DROP INTO THE CORE CAUSING THE |
| NEGATIVE RATE TRIP SIGNAL ON NUCLEAR INSTRUMENT CHANNELS 2 AND 4. NO |
| TESTING WAS BEING CONDUCTED AT THE TIME. ALL OTHER CONTROL RODS INSERTED |
| COMPLETELY. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, AS EXPECTED, DUE TO |
| THE LOW-LOW STEAM GENERATOR LEVELS REACHED DURING THE TRIP, ALSO AS |
| EXPECTED. NO SAFETY OR RELIEF VALVES LIFTED FOLLOWING THE TRIP. DECAY HEAT |
| STEAM IS BEING DUMPED TO THE MAIN CONDENSER. UNIT 1 IS STABLE IN MODE 3 |
| (HOT STANDBY) WITH REACTOR COOLANT SYSTEM TEMPERATURE AT 547�F AND PRESSURE |
| AT 2235 PSIG. |
| |
| NUMBER 11 CONTAINMENT FAN COIL UNIT WAS INOPERABLE PRIOR TO THE REACTOR TRIP |
| AND WILL BE REPAIRED PRIOR TO THE RESTART OF UNIT 1. |
| |
| THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THE REACTOR TRIP, REPAIR THE |
| ROD CONTROL SYSTEM, MAINTAIN HOT STANDBY MODE, AND PREPARE TO RESTART UNIT |
| 1. |
| |
| THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND LOCAL OFFICIALS, |
| AND ON 05/21/99, ISSUE A PRESS RELEASE. |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021