Event Notification Report for August 7, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/06/2002 - 08/07/2002
** EVENT NUMBERS **
39090 39111 39112 39114
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|General Information or Other |Event Number: 39090 |
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| REP ORG: MISSISSIPPI DIV OF RAD HEALTH |NOTIFICATION DATE: 07/25/2002|
|LICENSEE: BURNS, COOLEY AND DENNIS, INC |NOTIFICATION TIME: 11:30[EDT]|
| CITY: JACKSON REGION: 2 |EVENT DATE: 07/24/2002|
| COUNTY: STATE: MS |EVENT TIME: [CDT]|
|LICENSE#: MS61901 AGREEMENT: Y |LAST UPDATE DATE: 08/06/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |JOHN HICKEY NMSS |
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| NRC NOTIFIED BY: JOSH GRISHAM | |
| HQ OPS OFFICER: MIKE NORRIS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE |
| |
| A Troxler gauge model 3440, serial number 31621, was stolen out of the bed |
| of a truck in front of a private residence. The vehicle was parked at 2300 |
| on 7/24/02 and the gauge was found missing at 0700 on 7/25/02. The gauge |
| contains 8 millicuries of Cs-137 and 40 millicuries of Am-241:Be. Local law |
| enforcement has notified and a press release is planned for the local |
| newspaper. |
| |
| * * * UPDATED AT 1220 EDT ON 8/6/02 BY JOSH GRISHAM TO FANGIE JONES * * * |
| |
| The gauge has been recovered in good condition. |
| |
| Notified R2DO (Caudle Julian) and NMSS EO (Charlie Miller). |
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|Power Reactor |Event Number: 39111 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 08/06/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 04:34[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/05/2002|
+------------------------------------------------+EVENT TIME: 23:33[CDT]|
| NRC NOTIFIED BY: BRIAN HUPKE |LAST UPDATE DATE: 08/06/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
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EVENT TEXT
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| LOSS OF RESIDUAL HEAT REMOVAL (RHR) HEAT REMOVAL CAPABILITY. |
| |
| "At 23:33 on 8/5/02 both loops of RHRSW (Residual Heat Removal Service |
| Water) were declared inoperable due to experiencing high differential |
| pressure greater than 12 psid across the 'A' loop RHRSW strainer and the 'B' |
| loop RHRSW strainer. |
| |
| "On 8/4/02 while running a surveillance for the 'B' RHRSW pump a high |
| strainer differential pressure annunciator was received, which comes in a 6 |
| psid. 'B' pump flow at the time was 2400 GPM. The in plant operator was |
| sent locally to investigate the local differential pressure indication and |
| discovered the instrument was pegged high at > (greater than ) 15 psid. The |
| pump was secured and the corresponding Limiting Condition of Operation of 7 |
| days was entered for the 'B' RHRSW loop. Maintenance was immediately |
| planned and begun to clean the 'B' RHRSW strainer. At the time plans were |
| also made to inspect the 'B' RHRSW/ESW (Emergency Service Water) pit and |
| Stilling Basin. |
| |
| "On 8/5/02 after inspections of the Stilling basin found algae growth, plans |
| were made to run the 'A' side RHRSW pumps to determine operability of the |
| 'A' loop of RHRSW. At that time the Stilling basin cleaning also began. |
| After the completion of stilling basin cleaning on 8/5/02, the 'A' RHRSW |
| pump was started and strainer differential was between 2.5 - 4.5 psid at a |
| pump flow of 2400 GPM which was held for 15 minutes. At this time the 'C' |
| RHRSW pump was started and flow raised to 4100 GPM at which time strainer |
| differential pressure was steady at 5.5 - 6.0 psid. As flow was raised to |
| 5000 GPM Strainer differential pressure pegged high at > (greater than) 15 |
| psid within 3 minutes. The 'A' RHRSW pump was then secured and flow lowered |
| to 2100 GPM where strainer differential pressure remained at 10 - 12 psid |
| and then pegged high at greater than 15 psid. The 'C' RHRSW pump was then |
| secured and the 'A' RHRSW loop was declared inoperable at 23:33 on 8/5/02. |
| The LCO for both loops of RHRSW inoperable was then entered at 23:33 on |
| 8/5/02. |
| |
| "This report is being made under 50.72(b)(3)(v)(B) 'Any event or condition |
| that at the time of discovery could have prevented the fulfillment of the |
| safety function of structures or systems that are needed to remove residual |
| heat.' " |
| |
| |
| All other Emergency Core Cooling Systems are fully operable if needed. |
| |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 39112 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 08/06/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 10:16[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/06/2002|
+------------------------------------------------+EVENT TIME: 07:53[CDT]|
| NRC NOTIFIED BY: DAVID MANKIN |LAST UPDATE DATE: 08/06/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: |BOB DENNING NRR |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |TIM MCGINTY DIRO |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |62 Power Operation |
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EVENT TEXT
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| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO BOTH RESIDUAL HEAT
REMOVAL |
| SERVICE WATER SUBSYSTEMS BEING DECLARED INOPERABLE. |
| |
| |
| "Initiated plant shutdown in accordance with Tech Spec 3.7.1, Required |
| Action E.1 due to required actions and associated completion times not meet |
| (met) for both Residual Heat Removal Service Water subsystems being |
| inoperable. Per Tech Specs, plant is required to be in Mode 3 by 1933 hours |
| today (8/6/2002) and in Mode 4 by 1933 hours on 8/7/2002. Plant shutdown was |
| commenced at 0753 hours today. |
| |
| "This report is being made under 50.72(b)(2)(I), 'The initiation of any |
| nuclear plant shutdown required by plant's Technical Specifications." |
| |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are |
| fully operable if needed. The electrical grid is stable. The licensee |
| will reduce reactor power down to between 10 to 15 percent power then |
| manually scram the reactor. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| See event # 39111 for background information. |
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|Power Reactor |Event Number: 39114 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/06/2002|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 16:08[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 08/06/2002|
+------------------------------------------------+EVENT TIME: 10:00[CDT]|
| NRC NOTIFIED BY: STEVE GIFFORD |LAST UPDATE DATE: 08/06/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHUCK CAIN R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| LICENSEE DISCOVERED A POST-FIRE SAFE SHUTDOWN FUNCTION THAT MAY NOT
BE MET |
| |
| "On August 6, 2002, conditions were discovered where a postulated fire could |
| cause the pressurizer to blow down to the pressurizer relief tank (PRT). |
| Wolf Creek is in Mode 1, at 100% power. |
| |
| "During reviews associated with post-fire safe shutdown reanalysis work, |
| Wolf Creek personnel discovered that power and control cables for a |
| pressurizer power operated relief valve (PORV) and its associated motor |
| operated block valve are routed in electrical raceways with no horizontal |
| separation. The two valves are in the same electrical separation group but |
| are redundant in their post-fire safe shutdown function to prevent reactor |
| coolant system (RCS) blowdown to the PRT. Further investigation determined |
| that the power and control cables in the opposite separation group have the |
| same configuration. This does not meet our commitments to 10 CFR 50 Appendix |
| R.lll.G as reflected in our approved Fire Protection Plan. |
| |
| "During a fire in the plant, it is the function of PORV valves and block |
| valves to provide a barrier to blowing down the RCS into the PRT. A fire in |
| any of the affected fire areas in which the circuits are routed has the |
| potential to damage cables in a manner that cause a the PORV to spuriously |
| open (due to a hot short), and to damage cables in a manner that causes the |
| block valve to not respond to a close signal (due to an open circuit or a |
| hot short). This would cause a non-isolable RCS blowdown to the PRT. |
| |
| "Based on the guidance provided in NUREG 1022 Revision 2, this situation |
| meets the criterion of 10 CFR 50.72(b)(3)(ii)(B) for an 8-hour ENS |
| notification, as it relates to being in an unanalyzed condition. |
| |
| "The licensee has implemented a 1-hour fire watch and is developing |
| compensatory measures. |
| |
| "The licensee notified the NRC Resident Inspector." |
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Page Last Reviewed/Updated Thursday, March 25, 2021