Event Notification Report for January 6, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/05/1999 - 01/06/1999
** EVENT NUMBERS **
35155 35214 35215 35216 35217 35218 35219 35220
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35155 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/16/1998|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 11:07[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 12/16/1998|
+------------------------------------------------+EVENT TIME: 07:24[EST]|
| NRC NOTIFIED BY: BOB KIDDER |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - DIVISION 3 NORMAL BATTERY CHARGER FAILED AND WAS REPLACED BY THE RESERVE |
| CHARGER - |
| |
| AT 0724 ON 12/16/98, THE CONTROL ROOM RECEIVED ANNUNCIATOR ALARMS INDICATING |
| TROUBLE ON THE DIVISION 3 DIESEL GENERATOR (DG) AND DIVISION 3 BATTERY. BUS |
| AND BATTERY VOLTAGE HAD DECREASED FROM 129 VDC TO APPROXIMATELY 122 VDC, AND |
| THE BATTERY WAS DISCHARGING APPROXIMATELY 5 AMPS. SUBSEQUENT INVESTIGATION |
| DETERMINED THAT THE DIVISION 3 NORMAL BATTERY CHARGER HAD NO OUTPUT. |
| |
| AT 0746, PLANT OPERATORS PLACED THE DIVISION 3 DG AND THE HIGH PRESSURE CORE |
| SPRAY (HPCS) SYSTEM IN SECURE STATUS TO PREVENT A POTENTIAL AUTOMATIC |
| INITIATION DUE TO VOLTAGE PROBLEMS AND SHIFTED THE DIVISION 3 ON-LINE |
| BATTERY CHARGER FROM THE NORMAL BATTERY CHARGER TO THE RESERVE BATTERY |
| CHARGER. THE LICENSEE DECLARED THE DIVISION 3 DG AND THE HPCS SYSTEM |
| INOPERABLE [14-DAY LIMITING CONDITION FOR OPERATION (LCO)] EVEN THOUGH THEY |
| ARE FUNCTIONAL. |
| |
| AT 1010, THE LICENSEE VERIFIED THE RESERVE BATTERY CHARGER AND ALL DIVISION |
| 3 SYSTEMS TO BE OPERABLE AND EXITED THE HPCS SYSTEM LCO. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO REPAIR/REPLACE |
| THE FAILED BATTERY CHARGER. |
| |
| * * * UPDATE 1007 EST ON 01/05/99 FROM STERLING SANFORD TO S.SANDIN * * * |
| |
| THIS EVENT IS BEING RETRACTED BASED ON THE FOLLOWING: |
| |
| "AFTER FURTHER REVIEW, IT HAS BEEN DETERMINED THAT THIS EVENT IS NOT |
| REPORTABLE AS A LOSS OF SAFETY FUNCTION. BATTERY VOLTAGE ON DIVISION 3 |
| REMAINED AT APPROXIMATELY 122 VDC. ENGINEERING CALCULATIONS SHOW THIS |
| VOLTAGE TO BE ABOVE THAT WHICH IS REQUIRED FOR HPCS TO PERFORM ITS SAFETY |
| FUNCTION. |
| |
| "OPERATIONS CONSERVATIVELY SECURED DIVISION 3 TO ENSURE THAT NO [ENGINEERED |
| SAFETY FEATURE] ACTUATIONS OCCURRED WHILE TRANSFERRING FROM THE NORMAL TO |
| THE RESERVE BATTERY CHARGER. REASONABLE OPERATOR ACTIONS COULD HAVE BEEN |
| TAKEN TO RESTORE HPCS, IF REQUIRED. THIS IS IN ACCORDANCE WITH NUREG-1022 |
| GUIDANCE. |
| |
| "DURING THIS EVENT, [AUTOMATIC DEPRESSURIZATION SYSTEM], ALL LOW-PRESSURE |
| [EMERGENCY CORE COOLING SYSTEMS], AND [REACTOR CORE ISOLATION COOLING] WERE |
| OPERABLE." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS |
| OFFICER NOTIFIED THE R3DO (CLAYTON). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35214 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 03:19[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/04/1999|
+------------------------------------------------+EVENT TIME: 20:51[PST]|
| NRC NOTIFIED BY: HOWARD SMITH |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOSEPH TAPIA R4 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE DETERMINED THAT THE CCW SYSTEM MAY NOT MEET ITS REQUIREMENT TO |
| OPERATE FOR 7 DAYS WITHOUT MAKE-UP FOLLOWING A SEISMIC EVENT. |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: |
| |
| "AT SAN ONOFRE, THE COMPONENT COOLING WATER (CCW) SYSTEM IS REQUIRED TO |
| PROVIDE COOLING FOR 7 DAYS WITHOUT MAKE-UP. CCW TRAINS 'A' AND 'B' ARE |
| SEISMICALLY QUALIFIED; THE NON-CRITICAL LOOP IS NOT SEISMICALLY QUALIFIED." |
| |
| "UNIT 2 ENTERED MODE 5 AT APPROXIMATELY 0544 PST ON JANUARY 3, 1999, FOR A |
| PLANNED REFUELING/MAINTENANCE OUTAGE. AT 2051 ON JANUARY 4, 1999, WHILE |
| UNIT 2 WAS IN MODE 5, SCE DETERMINED THAT ISOLATION VALVE LEAKAGE BETWEEN |
| CCW TRAIN 'B' AND THE CCW NON-CRITICAL LOOP OBSERVED DURING A [TECHNICAL |
| SPECIFICATION] SURVEILLANCE EXCEEDED ITS ACCEPTABLE LIMIT FOR OPERATION IN |
| MODES 1 THROUGH 4, AND TRAIN B CCW COULD HAVE BEEN INOPERABLE PRIOR TO SHUT |
| DOWN. TESTS WERE PERFORMED TO ATTEMPT TO DETERMINE WHETHER THIS LEAKAGE |
| EXISTED DURING OPERATION IN MODES 1 THROUGH 4 PRIOR TO PLANT SHUT DOWN. |
| HOWEVER, THE TESTS WERE UNABLE TO DETERMINE THAT THE LEAKAGE DID NOT EXIST |
| PRIOR TO SHUT DOWN. DURING THE PAST CYCLE OF PLANT OPERATION, IF A SEISMIC |
| EVENT WERE TO HAVE OCCURRED WHILE TRAIN 'A' WAS OUT OF SERVICE, THERE WAS A |
| POTENTIAL FOR THE CCW TO FAIL TO MEET ITS REQUIRED 7 DAYS OF OPERATION |
| WITHOUT MAKEUP. THEREFORE, SCE IS CONSERVATIVELY MAKING THIS REPORT AS A |
| NON-EMERGENCY 4-HOUR REPORT IN ACCORDANCE WITH 10CFR50.72(b)(2)(iii) - A |
| CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY |
| FUNCTION OF THE CCW. |
| |
| "CCW IS PRESENTLY CAPABLE OF PERFORMING ITS SUPPORT FUNCTION FOR SHUTDOWN |
| COOLING IN MODES 5 AND 6. THE ISOLATION VALVES' ACTUATORS WERE |
| DISCONNECTED, THE VALVES WERE MANUALLY SEATED. THE MEASURED LEAKAGE WAS |
| WELL BELOW THE ACCEPTABLE LEVEL FOR OPERATION IN MODES 1 THROUGH 4. THE |
| ACTUATORS WERE RE-CONNECTED TO PROVIDE FOR REMOTE OPERATION. THE |
| INVESTIGATION OF THE CAUSE AND CORRECTIVE ACTIONS IS ON-GOING. |
| |
| "UNIT 3 IS IN MODE 1 AND UNAFFECTED BY THIS CONDITION." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35215 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 15:12[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 13:40[CST]|
| NRC NOTIFIED BY: TIM BORGEN |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |BRENT CLAYTON R3 |
|10 CFR SECTION: |CHRIS GRIMES, NRR EO |
|AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOSEPH GIITTER, AEOD IRD |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOHN HANNON, NRR EO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION |WAYNE STORE FEMA |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT, AUTOMATIC REACTOR TRIP, AND PARTIAL LOSS OF OFFSITE POWER DUE |
| TO AN EXPLOSION OF A STATION AUXILIARY TRANSFORMER |
| |
| At 1311 CST, a Unit 1 automatic reactor trip occurred due to an explosion of |
| the '1M' station auxiliary transformer. The licensee's fire brigade |
| responded to the subsequent fire and extinguished the fire within several |
| minutes. The '1R' reserve transformer (which is located next to the '1M' |
| transformer) was also lost possibly due to its proximity to the explosion. |
| The loss of both the '1M' and 1R' transformers (which are located outside of |
| the main turbine building) caused the loss of non-safeguards buses 11, 12, |
| 13, and 14. This in turn caused the loss of all condensate and feedwater |
| pumps, circulating water pumps, and reactor coolant pumps. Auxiliary |
| feedwater automatically initiated as required. All Unit 1 safeguards buses |
| remained energized from normal offsite power. All rods fully inserted upon |
| receipt of the reactor trip. There were three first out indicators (low-low |
| steam generator pressure on the 11 steam generator, steam generator low-low |
| level on the 12 steam generator, and high flux rate trip), and the exact |
| causes of the reactor trip and transformer explosion are currently under |
| investigation. There were no emergency core cooling system actuations, and |
| none were expected. All systems functioned as required, and there were no |
| personnel injuries. |
| |
| Unit 1 is currently stable in Hot Shutdown. Normal charging and letdown, |
| auxiliary spray and one pressurizer heater, and natural circulation are |
| being used to maintain primary system inventory, pressure, and transport |
| control. Auxiliary feedwater is supplying water to the steam generators, |
| and secondary steam is being dumped to atmosphere. There is no indication |
| of steam generator tube leakage. Efforts are currently underway to restore |
| power to non-safeguards buses 13 and 14. |
| |
| Unit 2 was unaffected by this event. It is currently operating at 60% |
| reactor power following performance of an outage, and power ascension is in |
| progress. |
| |
| At 1340 CST, the licensee declared a Notification of Unusual Event due to |
| conditions warranting increased awareness by the plant operations staff. |
| This was later revised to be conditions hazardous to plant operations (near |
| or onsite explosion). The licensee currently plans to terminate the Unusual |
| Event when one reactor coolant pump has been returned to service. |
| |
| The licensee notified the NRC resident inspector as well as the applicable |
| state and local agencies. The licensee may also issue a press release. |
| |
| ******************** UPDATE AT 1953 EST ON 01/05/99 FROM TIM BORGEN TO |
| TROCINE ******************** |
| |
| The licensee terminated the Unusual Event at 1843 CST. Unit 1 is currently |
| in a stable condition meeting all technical specification requirements. |
| Power has been restored to the 11, 12, 13, and 14, non-safeguards buses via |
| back feed from the '2R' transformer. The 12 reactor coolant pump was |
| started at 1835 CST, and the licensee plans to start the 11 reactor coolant |
| pump within a few minutes. The circulating pumps were restored to service |
| several hours ago, and the licensee plans to restore condensate pumps |
| shortly. |
| |
| The licensee notified the NRC resident inspector and plans to notify the |
| applicable state and local agencies. The licensee may also issue a press |
| release tomorrow. The NRC Operations Officer notified the R3DO (Clayton), |
| NRR EO (Hannon), AEOD IRD (Giitter), and FEMA (Ken Ciboch). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35216 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 15:12[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 13:40[CST]|
| NRC NOTIFIED BY: RANDY HASTINGS |LAST UPDATE DATE: 01/06/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: |CHRIS GRIMES, EO NRR |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |JOHN HANNON, EO NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOSEPH GIITTER IRD |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - UNIT 1 SHUTTING DOWN DUE TO INOPERABLE SI SYSTEM DUE TO FROZEN |
| RECIRCULATION LINE - |
| |
| UNIT 1 IS AT 100% POWER, AND UNIT 2 IS DEFUELED IN A REFUELING OUTAGE. |
| |
| A PORTION OF THE UNIT 1 SAFETY INJECTION PUMPS' RECIRCULATION LINE TO THE |
| UNIT 1 REFUELING WATER STORAGE TANK APPEARS TO BE FROZEN DUE TO A LOSS OF |
| HEAT TRACING DURING EXTREMELY COLD WEATHER. THIS CONDITION RENDERS BOTH |
| TRAINS OF THE UNIT 1 SAFETY INJECTION SYSTEM INOPERABLE. THE UNIT 1 |
| CONTAINMENT SPRAY PUMPS USE THE SAME RECIRCULATION LINE AND ARE ALSO |
| RENDERED INOPERABLE. THE CONDITIONS OF TECHNICAL SPECIFICATION 15.3.0.B |
| APPLY, AND THIS CONDITION APPEARS TO BE REPORTABLE AS A CONDITION THAT IS |
| OUTSIDE THE PLANT DESIGN BASIS. |
| |
| THE ACTION STATEMENT FOR TECHNICAL SPECIFICATION 15.3.0.B REQUIRES THE |
| LICENSEE TO INITIATE ACTION WITHIN 1 HOUR TO PLACE UNIT 1 IN HOT SHUTDOWN |
| WITHIN 7 HOURS OF ENTERING THIS SPECIFICATION AND IN COLD SHUTDOWN WITHIN 37 |
| HOURS. |
| |
| THE LICENSEE IS CURRENTLY ATTEMPTING TO THAW THE LINE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| ****************** UPDATE AT 1615 EST ON 01/05/98 FROM RANDY HASTINGS TO |
| TROCINE ****************** |
| |
| The licensee initiated the technical specification required load reduction |
| at 1506 CST on 01/05/99. |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Clayton), NRR EOs (Grimes and Hannon),and AEOD |
| IRD (Giitter). |
| |
| ****************** UPDATE AT 2132 EST ON 01/05/99 FROM JOHN CELL TO TROCINE |
| ****************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Enforcement discretion was requested [at approximately 1625 CST] and |
| granted [at approximately 1820 CST] by the NRC regarding the [Unit 1] |
| shutdown required by the frozen [recirculation] line. Unit 1 is presently |
| at 23% reactor power. Plans are to raise reactor power to 30% and hold. |
| |
| "Actions underway include [a] 50.59 evaluation of an alternate recirculation |
| path that will restore the operability of one [safety injection] pump. An |
| operability determination is being written to evaluate the operability of |
| the [containment spray pumps] without the recirculation line. These actions |
| are expected to be completed before the expiration of the enforcement |
| discretion at 0140 CST [on 01/06/99]." |
| |
| The licensee plans to notify the NRC resident inspector. The NRC Operations |
| Officer notified the R3DO (Clayton), NRR EO (Hannon), and AEOD IRD |
| (Giitter). |
| |
| * * * UPDATE 0152 EST 1/6/98 FROM JOHN SELL TAKEN BY STRANSKY * * * |
| |
| "The original frozen line has been thawed and is being maintained warm by |
| fluid circulation. An alternate SI pump recirculation path is currently |
| being utilized which restores the Unit 1 'B' SI pump to operable. The use of |
| this path is supported by a 50.59 evaluation and an operability |
| determination. The same operability determination restores both Unit 1 CSPs |
| to operable status with minor compensatory measures. |
| |
| "Unit 1 is being returned to 100% reactor power. The unit is in a 72-hour |
| LCO until the normal SI recirculation path is restored, which will allow the |
| 'A' SI pump to be declared operable. This is anticipated later today after |
| restoration procedures are approved and the SI recirc line heat tracing is |
| restored." |
| |
| The NRC resident inspector will be informed of this update by the licensee. |
| Notified R3DO (Clayton), EO (Hannon). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35217 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [] [] STATE: MD |NOTIFICATION TIME: 15:17[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 15:12[EST]|
| NRC NOTIFIED BY: TOM O'MEARA |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A SMALL STEAM LEAK ON A MOISTURE SEPARATOR |
| REHEATER DRAIN TANK |
| |
| The licensee plans to notify the State Department of Labor Licensing and |
| Regulation of a small steam leak on the 11 moisture separator reheater drain |
| tank, which is an ASME Section VIII pressure vessel. There is no indication |
| of steam generator tube leakage, there is no effect on plant operations, and |
| there were no personnel injuries. The area has been cordoned off as a |
| precaution, but the licensee does not expect the tank to catastrophically |
| fail. There are two welds for the 1-inch pad on top of the tank that are |
| still holding, and the licensee stated that the steam leak appears to be |
| coming from an inside weld through a tell tail on the 1-inch pad. The |
| outside welds appear to be intact. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35218 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 15:18[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 13:56[EST]|
| NRC NOTIFIED BY: JEFF MOSHER |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING INOPERABILITY OF THE SPILLWAY EMERGENCY |
| DIESEL GENERATOR |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1356 hours on 01/05/99, the Federal Emergency Regulatory Commission |
| (FERC) was notified of the inoperability of the North Anna spillway |
| emergency diesel generator in accordance with the requirements of |
| 18CFR12.10(a). The diesel generator failed its operability test due to the |
| engine water temperature being below the acceptable range of 165 - 195�F. |
| Water temperature during the test was 155�F. A work request has been |
| initiated to identify and correct the cause of this problem in a timely |
| manner. The diesel generator remains available." |
| |
| The licensee stated that the spillway emergency diesel generator is not |
| safety related and that the units are not in any limiting conditions for |
| operation as a result of this issue. |
| |
| In addition to the FERC, the licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35219 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 16:15[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 16:13[EST]|
| NRC NOTIFIED BY: BOB SMITH |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: |SUSAN SHANKMAN, EO NMSS |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |FEMA, DOE, USDA, HHS FAX |
| |EPA, DOT/NAT RES CTR FAX |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Connecticut notified that 840 gallons of waste water containing trace |
| amounts of tritium leaked into Niantic Bay - |
| |
| At 0200 on 01/04/99, a leak in a heater loop for the Unit 3 'A' waste test |
| tank (WTT) was discovered. Waste water in the WTT contained radioactivity |
| and boric acid. The leak (approximately 1 - 2 gallons per minute) was |
| isolated. Initial indications were that this waste water was contained |
| within the yard drain system. Upon subsequent investigations, it was |
| determined that, conservatively estimated, 840 gallons of liquid (4% of tank |
| volume) leaked from the WTT. A berm surrounding the tank had been installed |
| due to a prior leak but did not contain this leak. Sampling performed at |
| discharge serial number DSN-006 taken after the event indicated the presence |
| of tritium. |
| |
| Based on the above, it is believed that waste water from this leak flowed to |
| a nearby yard drain and then discharged to Niantic Bay via DSN-006. The |
| waste water from this leak contained radioactivity which is not addressed in |
| the Millstone NPDES permit at DSN-006 nor are the WTTs listed as a source of |
| waste water for DSN-006. Additionally, upon subsequent surveys of the storm |
| drain system, tritium was detected at the DSN-006 sample point. As a |
| result, this event was reported by the licensee to the Connecticut |
| Department of Environmental Protection Spills Division and Permitting |
| Division and local officials. |
| |
| The licensee plans to inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35220 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 19:14[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 15:18[EST]|
| NRC NOTIFIED BY: FREDERICK SMITH |LAST UPDATE DATE: 01/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON 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 95 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC START OF AN ANNULUS EXHAUST GAS TREATMENT SYSTEM FAN DURING TRAIN |
| RESTORATION |
| |
| While returning annulus exhaust gas treatment system (AEGTS) train 'B' to |
| standby readiness from secured status, the 'B' fan automatically started |
| when the fan control switch was placed in the 'standby' position. The |
| licensee believes that the initiating signal may not have been valid and |
| that the cause may have been a faulty flow switch. Reportability is still |
| under investigation. |
| |
| The licensee notified the NRC resident inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021