Event Notification Report for March 23, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/22/2001 - 03/23/2001
** EVENT NUMBERS **
37824 37856 37857 37858 37859 37860
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|Power Reactor |Event Number: 37824 |
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| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/10/2001|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 22:29[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/10/2001|
+------------------------------------------------+EVENT TIME: 15:15[EST]|
| NRC NOTIFIED BY: JAMES JOHNSTONE |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 72 Power Operation |71 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TECHNICAL SPECIFICATION (TS) SHUTDOWN |
| |
| "At time 2058 (EST) on 03/10/01, Unit 2 commenced a normal rampdown to cold |
| shutdown for refueling. The unit was in action statement that expires at |
| 1515 on 03/11/01. The action statement of TS 3.6.1.3.b had been entered at |
| 1515 on 03/10/01 when 2-PT-62.1 failed. This test was a routine pre-outage |
| test on the containment equipment hatch personnel access air lock. The unit |
| shutdown was planned for this date and time. Repairs to the failed |
| component will be made with unit in mode 5." |
| |
| The licensee thinks that the equipment hatch inner air lock door equalizing |
| valve is leaking by. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1301 EST ON 3/22/01 BY JIM CROSSMAN TO FANGIE JONES * * * |
| |
| |
| The licensee is retracting this event notification. The original |
| notification was conservatively made. At the time the plant had planned to |
| shutdown for a refueling outage and it was unknown at the time if repairs |
| could have been made within the 24 hour time clock required by technical |
| specifications. The problem with the hatch turned out to be minor in nature |
| and easily corrected, thus the plant would not have been required to |
| shutdown per the technical specifications. The problem was excessive amount |
| of hardened grease applied to the seal surface. The grease was removed and |
| the air lock successfully passed leakage testing all within about one hour. |
| |
| |
| The licensee notified the NRC Resident Inspector. The R2DO (Mark Lesser) |
| was notified. |
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|Power Reactor |Event Number: 37856 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/22/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 02:16[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/21/2001|
+------------------------------------------------+EVENT TIME: 21:30[CST]|
| NRC NOTIFIED BY: DUSTIN WRIGHT |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| DRYWELL TO TORUS BYPASS LEAKAGE NOT REEVALUATED FOR POWER RERATE |
| |
| "An unanalyzed plant condition may exist due to Drywell to Torus bypass |
| leakage as defined in Tech Spec Bases 3.7.A was not reevaluated for power |
| rerate. The original evaluation determined that the maximum allowable |
| leakage capacity was 0.12 square feet. When power rerate was being |
| evaluated, General Electric assumed that Monticello was bound by a generic |
| evaluation for the drywell to torus allowable capacity of an 0.01 square |
| feet." |
| |
| Corrective action includes a reevaluation, as appropriate. The licensee |
| informed the NRC resident inspector. |
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+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37857 |
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| REP ORG: U.S. ARMY |NOTIFICATION DATE: 03/22/2001|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 14:34[EST]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 02/21/2001|
| COUNTY: STATE: IL |EVENT TIME: [CST]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 03/22/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SHEAR R3 |
| |MARK LESSER R2 |
+------------------------------------------------+JOHN HICKEY NMSS |
| NRC NOTIFIED BY: JEFF HAVENNER | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MISSING M187 PANORAMIC TELESCOPE LEVEL DEVICE |
| |
| A M187 panoramic telescope was found with a missing level vial, a sealed |
| tritium source of 0.075 curies at Fort Bragg, North Carolina. The second |
| level vial was broken and a wipe test indicated no contamination of the |
| instrument. A search was conducted of the reservation with negative |
| results. A written report will be made to NRC Region 3. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37858 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/22/2001|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 16:10[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/22/2001|
+------------------------------------------------+EVENT TIME: 11:10[EST]|
| NRC NOTIFIED BY: GUY GRIFFIS |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|*INB 50.72(b)(3)(v)(B) POT RHR INOP | |
|*IND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RCIC DECLARED INOPERABLE |
| |
| During an investigation of a ground on Div I 125/250 volt D.C. bus, the |
| source of the ground was determined to be 2E51-F008 primary containment |
| isolation valve. 2E51-F008 is the outboard steam supply to reactor core |
| isolation coolant (RCIC). It was closed and de-energized. 2E51-F008 |
| closure rendered RCIC system inoperable. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37859 |
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| REP ORG: COGEMA MINING, INC. |NOTIFICATION DATE: 03/22/2001|
|LICENSEE: COGEMA MINING, INC. |NOTIFICATION TIME: 16:54[EST]|
| CITY: LINCH REGION: 4 |EVENT DATE: 03/21/2001|
| COUNTY: STATE: WY |EVENT TIME: [MST]|
|LICENSE#: SUA-1341 AGREEMENT: N |LAST UPDATE DATE: 03/22/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+MICHAEL LAYTON NMSS |
| NRC NOTIFIED BY: JOHN VASELIN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NMIN MINING EVENT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| CONDITION OF LICENSE REPORT INVOLVING MINE IN EXCURSION STATUS |
| |
| The following is taken from a faxed report: |
| |
| Notification of a Reportable Event per License Section 11.2 |
| |
| Reported Event: |
| |
| A routine monthly water sample collected on March 21, 2001 from monitor well |
| 5MW43, exceeded 2 of its 3 upper control limits (UCLs). A confirmation |
| sample was collected March 22, which also exceeded 2 UCLs. Monitor well |
| 5MW43 was then placed on excursion status as per license Section 11.2 and |
| its sampling frequency increased to weekly. 5MW43 is a perimeter ore zone |
| monitor well located approximately 300 feet south of the Mine Unit 5 |
| boundary at the Christensen Mine, Campbell County Wyoming. Note that Mine |
| Unit 5 is currently in groundwater restoration and that the nearest |
| community is Linch, Wyoming approximately 16 miles to the southeast. |
| |
| Analysis Data: |
| |
| Conductivity |
| Uranium |
| Date Chloride mg/l umhos/cm2 |
| Alkalinity mg/I mg/l U308 |
| Sampled UCL 22.7 UCL 1004 UCL |
| 134.3 no UCL |
| 3-21-01 7.5 1116 |
| 163.0 <0.4 |
| 3-22-01 7.4 1133 |
| 169.0 <0.4 |
| |
| Health and Environmental Hazards: |
| |
| None |
| |
| Investigative Action: |
| |
| Collect additional samples from this well to further evaluate the water |
| quality. Since the chloride concentration remains near its baseline level, |
| it is felt that this is not an actual excursion from the Mine Unit. |
| |
| Written Notification: |
| |
| A written notification with further information will be submitted to NRC |
| Fuel Cycle Licensing Branch Chief within 7 days. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37860 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/22/2001|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 17:06[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/22/2001|
+------------------------------------------------+EVENT TIME: 14:43[MST]|
| NRC NOTIFIED BY: RUSSELL STROUD |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SECURITY REPORT |
| |
| Unescorted access was granted inappropriately. Immediate compensatory |
| measures were taken upon discovery. (Contact the NRC operations center for |
| additional details.) The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021