Event Notification Report for March 6, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/03/2000 - 03/06/2000
** EVENT NUMBERS **
36660 36662 36707 36750 36751 36752 36753 36754 36755 36756 36757 36758
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36660 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/04/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 17:14[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/04/2000|
+------------------------------------------------+EVENT TIME: 16:39[EST]|
| NRC NOTIFIED BY: M VASELY |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY DIMITRIADIS 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 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALIDITY OF ASSUMPTIONS FOR THE 30 MINUTE NITROGEN BACKUP SUPPLY IN QUESTION |
| |
| |
| During the review of Consolidated Edison calculation FIX-0030-02, Nitrogen |
| Backup Supply for control of Auxiliary Feedwater Flow Control Valves, |
| Turbine Driven Auxiliary Feedwater Pump, and Atmospheric Steam Dump |
| Controls, questions arose as to the validity of the assumption statements |
| that resulted in the design basis for 30 minutes of nitrogen could not be |
| sustained. The assumptions are in the process of being validated. A third |
| nitrogen bottle has been placed in backup alignment to maintain the 30 |
| minute requirement. |
| |
| 3 of the 6 Nitrogen Backup Bottles are now valved in instead of 2. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 0936 ON 03/03/00 BY PHIL SANTINI TO JOLLIFFE * * * |
| |
| Additional licensee engineering review has determined that the Nitrogen |
| Backup Supply for control of Auxiliary Feedwater Flow Control Valves, |
| Turbine Driven Auxiliary Feedwater Pump, and Atmospheric Steam Dump Controls |
| does meet the design basis as documented in licensee calculation |
| FIX-0030-02. |
| |
| Thus, the licensee desires to retract this event. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO Jim Trapp. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36662 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/05/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:42[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/04/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:00[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/03/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |TONY VEGEL R3 |
| DOCKET: 0707001 |JOE HOLONICH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM HORN FAILED SURVEILLANCE |
| |
| At 1600 on 02-04-2000 the PSS was informed of the failure of a criticality |
| accident alarm system (CAAS) air horn to sound during the performance of |
| surveillance testing. The cause of the failure was determined to be debris |
| in the air line fouling the flow path for the horn. Subsequently, after |
| this horn was repaired and the air horn line blown out, another air horn on |
| the same branch line became clogged and would not sound sufficiently. This |
| horn was also repaired and its line blown out. The system was retested |
| satisfactorily and declared operable at 2245 on 02-04-00. It is possible |
| that the system would not have performed its intended safety function if it |
| had been required to before it was declared inoperable. |
| |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which |
| equipment required by the TSR is disabled or fails to function as designed. |
| |
| The NRC Senior Resident Inspector has been notified of this event. |
| |
| * * * UPDATE ON 3/3/00 @ 1732 BY WALKER TO GOULD * * * RETRACTION |
| |
| THIS EVENT HAS BEEN RETRACTED. Subsequent testing of the C-337A CAAS horn |
| system with the subject horn valved out, has shown that the CAAS meets the |
| requirements for audibility in this area without this horn. Engineering |
| Evaluation EV-C-812-00-003 Rev. 0 was completed to document the conclusions |
| of this testing. |
| |
| The NRC Resident inspector was informed. |
| |
| The Reg 3 RDO(Jordan) and NMSS EO(Sherr) were notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36707 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/18/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:03[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/18/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: [EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/03/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| At 1335 hours on 02/17/00 a see and flee emergency was initiated at the |
| X-330 building Tails position #1. The see and flee was Initiated as a result |
| of a process gas release from the pigtail on Tails position #1. The release |
| was large enough to exceed the capacity of portable mini-gulper staged In |
| the area. The mini-gulper is used to divert and contain any small releases |
| that may occur during pigtail connect/disconnect operations. The release of |
| process gas caused a valid actuation of the pyrotronics smokehead safety |
| system. The pyrotronics smokeheads and pigtail line isolation safety systems |
| operated as designed during this event. |
| |
| UPDATE AT 1445EST ON 3/300 FROM KURT SISLER TO S.SANDIN * * * |
| |
| The Regulatee is retracting this report based on the following: |
| |
| "Nuclear Regulatory Affairs has reviewed the basis for Portsmouth Event |
| Report Notification PTS-2000-017, 'X-330 Tails Withdrawal, Pyrotronics |
| Smokehead Actuation due to PG Release Exceeding the Capacity of the Gulper', |
| and determined that the event should be retracted. (Reference problem report |
| PR-PTS-00.-0096S). |
| |
| "On February 17, 2000 at 1335 hours, an outgassing occurred during the |
| connection of an empty cylinder at Tails position 1. The outgassing was |
| attributed to pressure inside the evacuation manifold due to a cylinder |
| burping operation which had just been completed at Tails position 3. When |
| position 3 was burped, the 1-inch diameter evacuation piping and the |
| position 1 pigtail, which was valved into the evacuation header, would have |
| been exposed to UF6 at above atmospheric pressure. When the burping |
| operation was completed, the position 3 evacuation was valved off and UF6 |
| withdrawal was restarted. |
| |
| "The operator proceeded to complete the connection of a new cylinder at |
| position 1. The operator, who was wearing appropriate personal protective |
| equipment, cracked open and closed the pigtail safety valve per procedure, |
| to evacuate the small space between the cylinder safety valve and the |
| pigtail safety switch, which plugs the safety valve when it is not connected |
| to a cylinder This exposed the space to UF6. As the operator began to |
| remove the pigtail safety switch, he observed smoke which was contained by |
| the gulper. The operator closed the valve and attempted to tighten fittings. |
| When the pigtail safety valve was again cracked open and closed to evacuate |
| the line, smoke exceeded the capacity of the gulper to contain the release |
| and set off both Pyrotronics smokeheads above position 1. The pigtail safety |
| valve was already closed and the Pigtail Line Isolation System closed the |
| manifold safety valve at position 1 automatically. The event was initially |
| determined to be reportable as a Safety System actuation of the Pigtail Line |
| Isolation System in accordance with the Safety Analysis Report Section 6.9, |
| Table 6.9-1, J.2. |
| |
| "The TSR 2.5.3.4 Basis Statement indicates that the purpose of the Pigtail |
| Line Isolation System is to minimize a release of liquid UF, due to pigtail |
| failure during a withdrawal (Modes II and III). Since the pigtail was |
| isolated from the liquid UF, system while the cylinder was being connected, |
| Tails Withdrawal position 1 was in preparation mode (Mode I) and the Pigtail |
| Line Isolation System safety function was not required. |
| |
| "The reporting criteria in Table 6.9-1, J.2 states that an actuation is |
| reportable for events having the potential for significant impact on the |
| health and safety of personnel. Events having the potential for significant |
| impact are those events where actual plant conditions existed that the |
| system was designed to protect against. Since position 1 was not in a Mode |
| for which the safety system was required to be operable, this event has been |
| determined to not be reportable to NRC. Accordingly, this was not a valid |
| actuation of a safety system. The event notification PTS-2000-017 may be |
| retracted." |
| |
| Operations informed the NRC Resident Inspector and the DOE Site |
| Representative. Notified R3DO(Jordan) and NMSS(Cool). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36750 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 10:38[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 09:50[EST]|
| NRC NOTIFIED BY: KEVIN SMALL / KEN HILL |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |LEN WERT R2 |
|10 CFR SECTION: |TAD MARSH NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
|NOCM COMM ASST BRIEF |KEN CIBOCH FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER TO 4 kV EMERGENCY |
| BUSES (REFER TO EVENT #36751 AND EVENT #36752 FOR ADDITIONAL INFORMATION.) - |
| |
| |
| At 0950 on 03/03/00, with Unit 1 in a refueling outage, the licensee |
| declared an Unusual Event due to a loss of offsite power to 4 kV emergency |
| buses E-1 and E-2 due to a mispositioned switch during relay testing. All |
| four emergency diesel generators (two for each unit) started; both Unit 1 |
| EDGs are in operation powering buses E-1 and E-2. Shutdown cooling was lost |
| but has been restored; spent fuel pool temperature is normal at 83�F. The |
| licensee has suspended all fuel movement and is restoring power to systems |
| that lost power. Unit 1 is stable. Unit 2, which is at 100% power, is |
| unaffected by this event. |
| |
| The licensee notified the NRC Resident Inspector and state and local |
| officials. |
| |
| * * * UPDATE ON 3/3/00 @ 1226 BY HILL TO GOULD * * * |
| |
| WHILE ATTEMPTING TO COME OUT OF THE LOSS OF OFF SITE POWER CONDITION, THE |
| PLANT HAD AN OVERCURRENT ALARM ON THE D/G-2, AND THEY LOST POWER FROM THE |
| NORMAL AND EMERGENCY POWER SOURCES TO THE E-2 BUS AT 1200. THIS IN TURN |
| RESULTED IN THE LOSS OF SHUT DOWN COOLING. SHUTDOWN COOLING WAS RESTORED |
| AT 1218 WITH MINIMAL TEMPERATURE INCREASE. THEY ALSO HAD THE HALON SYSTEM |
| ACTUATION IN THE D/G BASEMENT AREA. THE CAUSE OF THIS MAY HAVE BEEN RELATED |
| TO THE GROUND ON THE E-2 BUS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. THE REG 2 RDO(WERT), NRR EO(HANNON), |
| AND IRO(CONGEL) WERE NOTIFIED. |
| |
| * * * UPDATE ON 3/3/00 @ 1615 * * * COMMISSIONER'S ASSISTANTS BRIEF |
| |
| MALLETT(BRIEFER), MARSH(NRR EO), REYES(RA), EASLICK(RI), COLLINS(NRR), |
| MILLER(IRO), WERT(RDO), WIENS(NRR), BEECHER(PA), LOHAS(SP), FAULKNER(IP), |
| SATORIUS(EDO), BATES(SECY), CHAN(CHAIRMAN MESERVES' ASST), OLENCZ(COMM. |
| DICUS' ASST), SHARFEY(COMM. MCGAFFIGAN'S ASST), CASTLEMAN(COMM. DIAZ'S |
| ASST), AND McCABE(COMM. MERRIFIELD"S ASST). |
| |
| * * * UPDATE ON 3/3/00 @ 1844 FROM JOLICOEUR TO GOULD * * * |
| |
| NOUE TERMINATED AT 1840 DUE TO RESTORING POWER FROM NORMAL OFF-SITE SOURCES |
| TO THE E-1 AND E-2 BUSSES. |
| |
| The NRC Resident Inspector was notified. |
| |
| REG 2 RDO(WERT), NRR EO(HANNON), IRO(CONGEL), AND FEMA(STIENDRUF) WERE |
| NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36751 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:25[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 09:31[EST]|
| NRC NOTIFIED BY: JESTER |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD ESF ACTUATION DURING THE LOSS OF OFFSITE POWER EVENT. (REFER |
| TO EVENT #36750 AND EVENT #36752 FOR ADDITIONAL INFORMATION.) |
| |
| With Brunswick Unit 1 shutdown for refueling at approximately 09:31 on |
| 3/3/00 while performing procedure TM-TTBUS1A (Trip Testing of 230KV Bus 1A) |
| a loss of power to the Unit 1 BOP 4160 and emergency busses occurred. This |
| caused an automatic start of 4 diesel generators with diesels number 1 and 2 |
| loading and restoring power to their respective emergency busses. Unit 1 |
| received a group 8 isolation signal that caused a loss of shutdown cooling. |
| Core alterations were secured and shutdown cooling was reestablished at |
| 09:52. A small rise in reactor coolant temperature occurred (89�F was the |
| maximum) and the coolant system did not approach boiling temperatures. Six |
| group isolation signals occurred with various valves closing depending on |
| initial (pre-event) position. |
| |
| The following actuations occurred: 4 Diesel generators started, Reactor |
| Building HVAC isolated, Standby |
| Gas trains started, and an RPS trip occurred (no rod motion occurred due to |
| all rods being inserted). |
| Systems and components performed as designed based on initial assessment of |
| the event. An Unusual Event |
| was declared at 09:50 (event #36750) due to a loss of offsite power to the |
| emergency busses. |
| |
| At approximately 12:00 an actuation of the diesel building fire protection |
| halon system occurred with an isolation of the control building ventilation |
| system. A subsequent loss of emergency bus E2 occurred due to a trip of |
| DG#2, which resulted in a second loss of shutdown cooling on Unit 1. Group |
| isolations similar to those occurring initially also occurred. Shutdown |
| cooling was reestablished at 12:18. The plant is stable and investigation |
| into the cause of the DG trip is underway. The plant fire brigade responded |
| and found no immediate evidence of a fire. |
| |
| The NRC Resident Inspector was notified along with state and local |
| officials. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36752 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 14:29[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 13:57[EST]|
| NRC NOTIFIED BY: HILL |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 |99 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SHUT DOWN DUE TO ENTERING TS 3.0.3. LCO ACTION STATEMENT. (REFER TO |
| EVENT #36750 AND EVENT #36751 FOR ADDITIONAL INFORMATION.) |
| |
| At 1300 hours, Unit 2 entered Technical Specification 3.0.3 due to the loss |
| of diesel generator #2 while two off-site AC circuits were inoperable as |
| required by Limiting Condition of Operation 3.8.1, Condition I. The loss of |
| AC power and the diesel generator failure were previously reported in ENS |
| #36751. At 1357 hours, Unit 2 reactor shutdown commenced from 100% power. |
| |
| INITIAL SAFETY SIGNIFICANCE EVALUATION: The significance of this occurrence |
| is minimal. Sufficient redundant equipment remains operable such that no |
| safety functions have been lost. Plant conditions are stable at this time. |
| |
| CORRECTIVE ACTION(S): Efforts to restore the inoperable equipment are in |
| progress. Reference ENS # 36751 |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE ON 3/3/00 @ 2008 BY BELLER TO GOULD * * * |
| |
| PLANT EXITED THE 3.0.3 LCO AT 1756 WHEN THE UNIT 1 STARTUP AUX TRANSFORMER |
| WAS USED TO POWER THE EMERGENCY BUSSES. THEY ARE STILL IN A 12-HOUR LCO |
| ACTION STATEMENT TO RESTORE UNIT 1 UNIT AUXILLARY TRANSFORMER TO SERVICE OR |
| BE IN HOT SHUTDOWN IN THE FOLLOWING 12 HOURS. POWER HAD BEEN REDUCED TO |
| APPROXIMATELY 60%. |
| |
| THE NRC RESIDENT WAS INFORMED BY THE LICENSEE. THE NRC OPERATIONS OFFICER |
| NOTIFIED THE R2DO (WERT). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36753 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 15:56[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 14:17[EST]|
| NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WAYNE LANNING R1 |
|10 CFR SECTION: |JIM TRAPP R1 |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOHN HANNON NRR |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 28 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FOLLOWING A LOSS OF FEEDWATER SEAL INJECTION FLOW |
| DURING PLANT SHUTDOWN |
| |
| "WHILE PERFORMING A NORMAL SHUTDOWN, THE REACTOR WAS MANUALLY SCRAMMED AT |
| 1417EST DUE TO A LOSS OF SEAL WATER TO THE OPERATING FEEDWATER PUMP AND ITS |
| POTENTIAL FAILURE. ALL RODS FULLY INSERTED. SUBSEQUENT TO THE MANUAL |
| SCRAM, AN AUTOMATIC SCRAM WAS RECEIVED ON REACTOR WATER LEVEL 3. AN ATTEMPT |
| WAS MADE TO MANUALLY INITIATE REACTOR CORE ISOLATION COOLING TO ASSIST WITH |
| REACTOR WATER LEVEL CONTROL. THE RCIC SYSTEM FAILED TO INITIATE DUE TO A |
| TRIPPED TRIP THROTTLE VALVE. AT 1420EST THE RCIC SYSTEM WAS DECLARED |
| INOPERABLE. THE RCIC SYSTEM HAS BEEN RESTORED TO STANDBY. THE OPERATING |
| FEEDWATER PUMP CURRENTLY REMAINS IN SERVICE AND SCRAM RECOVERY PROCEDURE AND |
| REACTOR COOLDOWN ARE IN PROGRESS." |
| |
| FOLLOWING THE SCRAM MINIMAL SEAL INJECTION FLOW WAS AVAILABLE TO THE |
| OPERATING FEEDWATER PUMP. DECAY HEAT IS CURRENTLY BEING REJECTED TO THE |
| MAIN CONDENSER. |
| |
| THE NRC RESIDENT INSPECTOR WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36754 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 17:34[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 11:15[CST]|
| NRC NOTIFIED BY: PFEFFER |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ISOLATION CONTROLS FOR THE TIP GUIDE TUBE ARE NOT DESIGNED/QUALIFIED FOR |
| SAFETY RELATED SERVICE. |
| |
| The Transverse Incore Probe (TIP) guide tube primary containment isolation |
| controls are not designed or qualified for safety-related service. This |
| could result in a condition outside the Design Basis of the plant because |
| multiple failures could cause the undesirable opening of the TIP ball valves |
| during a Design Basis Accident. However, the TIP valve and TIP Shear Valve |
| Actuation circuits remain operable and continue to be capable of operating |
| as containment isolation valves. The TIP Ball Valve power source is through |
| the TIP Drive Mechanism. The TIP Ball Valves will be disabled by removing |
| the power source from the drive Mechanism when the TIP system is not in use. |
| The drive Mechanism power will be restored, under administrative controls, |
| when the TIP system is required to be used. |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36755 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/03/2000|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 17:42[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/2000|
+------------------------------------------------+EVENT TIME: 16:30[EST]|
| NRC NOTIFIED BY: NANCE |LAST UPDATE DATE: 03/03/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN 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 |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE DETERMINED A CONDITION FOUND WHICH COULD HAVE RESULTED IN THE |
| PLANT BEING SERIOUSLY DEGRADED. |
| |
| As a result of an Engineering evaluation of all safety-related large bore |
| piping, a number of as-built discrepancies were found with portions of the |
| Unit 2 Residual Heat Removal, Safety Injection and Containment Spray piping |
| systems. This analysis has concluded that these piping systems deviate from |
| the design criteria USAS 831.1-1967, which is the code of record for the |
| Cook Nuclear Plant. |
| |
| As the design and construction of the corresponding systems in Unit 1 are |
| similar, this notification is being made for both units despite the fact |
| that the Unit 1 review effort has not been completed. |
| |
| Though informal evaluations have concluded that the piping is unlikely to |
| fail in a postulated seismic event, no formal analysis exists to support |
| this conclusion. The engineering efforts to evaluate and resolve these |
| issues are ongoing. |
| |
| Both units are currently in no Technical Specification Operating mode with |
| both cores unloaded. |
| |
| The Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36756 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 03/04/2000|
| UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 02:37[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/04/2000|
+------------------------------------------------+EVENT TIME: 00:18[CST]|
| NRC NOTIFIED BY: WESS CUMBEE |LAST UPDATE DATE: 03/04/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT 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 Y 0 Startup |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED AUTOMATIC AUXILIARY FEEDWATER PUMP START |
| |
| While passing through Mode 2 in the process of shutting down Unit 1 to enter |
| refueling outage #16, the last running feedwater pump was secured without |
| defeating the automatic start defeat switch on the balance of plant. This |
| resulted in the automatic start of the 'B' motor-driven auxiliary feedwater |
| pump. The other auxiliary feedwater pump was already running. |
| |
| The licensee stated that a procedure step was missed and that an occurrence |
| report has been initiated to determine why the procedure step was missed. |
| The licensee also stated that all systems functioned as required and that |
| there was noting unusual or not understood. The unit is currently in Mode 3 |
| (Hot Standby). |
| |
| The licensee notified the NRC resident inspector who was at the site |
| observing the unit shutdown. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36757 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 03/04/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:05[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/04/2000|
+------------------------------------------------+EVENT TIME: 08:45[EST]|
| NRC NOTIFIED BY: TERRY BELTZ |LAST UPDATE DATE: 03/04/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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
+------------------------------------------------------------------------------+
| DISCOVERY OF A REACTOR CORE ISOLATION COOLING (RCIC) FLOW CONTROL |
| IRREGULARITY DURING THE PERFORMANCE OF SURVEILLANCE TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "A RCIC flow control irregularity was identified during quarterly RCIC |
| surveillance testing. Upon reaching the required flow rate of 400 gpm, RCIC |
| flow dipped to approximately 360 gpm for 1 - 2 minutes before stabilizing at |
| 400 gpm. Engineering is evaluating this condition. In the interim, the |
| RCIC system has been declared inoperable. The plant is in a 7-day |
| [technical specification limiting condition for operation (LCO)]." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36758 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/06/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 02:39[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/05/2000|
+------------------------------------------------+EVENT TIME: 22:00[CST]|
| NRC NOTIFIED BY: STEVEN JOBE |LAST UPDATE DATE: 03/06/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
|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 N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE TO MEET DRYWELL-TO-SUPPRESSION CHAMBER LEAKAGE TEST ACCEPTANCE |
| CRITERIA |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The acceptance criteria specified for the DRYWELL-TO-SUPPRESSION CHAMBER |
| LEAKAGE TEST was not met. The as-found value of 0.51 [inches] H2O/Min |
| exceeded the operability value of <= 0.2 [inches] H2O/Min. Based on this, |
| the operability of the drywell-to-suppression chamber vent pipes, vent |
| header down corners, and vacuum breakers cannot be assumed. Primary |
| containment was declared inoperable based on a failure to meet the |
| requirements of [surveillance requirement (SR)] 3.6.1.1.2, Verify drywell to |
| suppression chamber bypass leakage is equivalent to a hole < 1.0 inch in |
| diameter." |
| |
| "[The unit] entered [limiting condition for operation (LCO)] 3.6.1.1, |
| Condition A, requiring the restoration of primary containment to an operable |
| status within 1 hour. If this required action is not met, Condition B.1 |
| requires having the reactor in Mode 3 within 12 hours and B.2 requires |
| having the reactor in Mode 4 within 36 hours." |
| |
| "Currently[, the unit is] in Mode 3 for commencing [a] planned refueling |
| outage." |
| |
| "Engineering evaluation of test results is continuing, and the resident |
| inspectors will be kept apprised." |
| |
| The licensee notified the NRC resident inspectors. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021