Event Notification Report for August 14, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/13/2001 - 08/14/2001
** EVENT NUMBERS **
38130 38203 38204 38205 38206
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38130 |
+------------------------------------------------------------------------------+
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 07/11/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 23:01[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 07/11/2001|
+------------------------------------------------+EVENT TIME: 16:50[CDT]|
| NRC NOTIFIED BY: DAVID BARNETT |LAST UPDATE DATE: 08/13/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
|ASHU 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
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EVENT TEXT
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| PRIMARY CONTAINMENT DECLARED INOPERABLE - TECH SPEC REQUIRED SHUTDOWN |
| |
| The licensee found a shipping restraint installed on a drywell-to-torus vent |
| pipe bellows, apparently in place since construction (about 30 years). This |
| device was discovered due to another licensee with similar containment |
| configuration notifying Monticello of their discovery. This device would |
| partially impede axial motion. The primary containment was declared |
| inoperable at 1650 CDT on 07/11/01, and removal was initiated. This is an |
| 8-hour report under 10CFR50.72(b)(3)(ii)(a) as a degraded condition and |
| 10CFR50.72(b)(3)(v)(c and d), control of radiation release and accident |
| mitigation. |
| |
| The licensee initiated a required shutdown at 2050 CDT on 07/11/01 per |
| Technical Specification 3.7.A.2.a, as a result of declaring primary |
| containment inoperable because the drywell-to-torus vent pipe bellows |
| shipping installation attachments were still installed. This is a 4-hour |
| report under 10CFR50.72(b)(2)(i), technical specification required |
| shutdown. |
| |
| The licensee notified the NRC resident inspector and intends to notify state |
| and local agencies. |
| |
| ***** UPDATE FROM DAVE BARNETT RECEIVED BY LEIGH TROCINE AT 0039 EDT ON |
| 07/12/01 ***** |
| |
| The four shipping fasteners have been removed from each of the eight |
| drywell-to-torus vent pipe bellows, and primary containment was declared |
| operable at 2304 CDT on 07/11/01. The technical specification required |
| shutdown was terminated while the reactor was at 90% power. The licensee |
| currently plans to restore reactor power to 100%. |
| |
| The licensee plans to notify the NRC resident inspector as well as the |
| applicable state and county agencies. The NRC operations officer notified |
| the R3DO (Hills). |
| |
| |
| **** RETRACTION ON 08/13/01 AT 1253ET BY D. BARNETT TAKEN BY MACKINNON **** |
| |
| Subsequent evaluation has shown the bellows as well as the drywell and torus |
| attachments capable of performing their design safety functions. Therefore, |
| Primary Containment was considered operable at all times and this event is |
| not considered reportable. The licensee will notify state and local |
| officials of this retraction. R3DO (T. Kozak) notified. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38203 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 08/13/2001|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 15:04[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 08/13/2001|
+------------------------------------------------+EVENT TIME: 13:10[EDT]|
| NRC NOTIFIED BY: BREEN |LAST UPDATE DATE: 08/13/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) 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
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| OFFSITE NOTIFICATION TO THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION |
| |
| An immature green sea turtle was rescued from the plant's intake canal. The |
| turtle is alive but in need of rehabilitation. As required by the plant's |
| sea turtle permit, the Florida Department of Environmental Protection |
| (Florida Fish and Wildlife) was notified of this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|General Information or Other |Event Number: 38204 |
+------------------------------------------------------------------------------+
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| REP ORG: SCIENTECH, INC. |NOTIFICATION DATE: 08/13/2001|
|LICENSEE: NUS INSTRUMENTS, INC. |NOTIFICATION TIME: 17:14[EDT]|
| CITY: GAITHERSBURG REGION: 1 |EVENT DATE: 08/07/2001|
| COUNTY: STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 08/13/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RONALD BELLAMY R1 |
| |VERN HODGE, FAX NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARTIN BOOSKA | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POTENTIAL DEFECT |
| |
| SCIENTECH, Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined |
| that a Basic Component, supplied to Rochester Gas and Electric Ginna Station |
| Nuclear Plant under RG&E purchase order 5000002014, contains a potential |
| defect that is reportable under 10CFR21. NUSI determined that the potential |
| defect was reportable under the provisions of 10CFR21 on August 07, 2001. |
| SCIENTECH, Inc. President was informed August 13, 2001. RG&E is aware of |
| this problem and the affected component is being modified to restore this |
| item to an acceptable status by August 17. |
| |
| A formal written report will be provided within 30 days of this |
| notification. The component, delta T Time Domain Module, M/N: |
| TMD500-08/08/08/08-08-08-1/2, P/N: MBA-E063PA-1, Rev. 0 (1ea.), S/N:9800771, |
| was originally manufactured as P/N: MBA-E062PA-1 (voltage output) by NUSI. |
| NUSI performed a conversion of this item to P/N: MBA-E063PA-1 (current |
| output) resulting in a defect. A total of six items were converted under |
| this purchase order for use in Safety Related Systems. NUSI has opened a |
| 10CFR21 file concerning this component and has numbered it as 21-01-01. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 38205 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/13/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:40[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/13/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:15[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/13/2001|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |THOMAS KOZAK R3 |
| DOCKET: 0707002 |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LOSS OF ONE CONTROL OF THE DOUBLE CONTINGENCY PRINCIPLE |
| |
| NRC BULLETIN 91-01 24 HOUR NOTIFICATION |
| |
| At 1415 8/13/01 loose plastic wrap was discovered on a storage shelf in an |
| inadvertent container area and was not configured or secured such that it |
| cannot be deformed into an inadvertent container with an unsafe accumulation |
| potential. This is a violation of control # 5 of NCSA705_076.A03, "Use Of |
| Inadvertent Containers". A pump located on a lower shelf apparently had a |
| pump flange cover dislodged, uncovering a potential inadvertent container. |
| This is a violation of control # 3 of the same NCSA. |
| |
| The PSS entered an anomalous condition. The plastic wrap and pump were |
| removed from the inadvertent Container area. The PSS exited the anomalous |
| condition. |
| |
| SAFETY SIGNIFICANCE OF THE EVENTS: LOW |
| |
| There was no leak of uranium bearing material in the vicinity of the plastic |
| or the uncovered pump. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO OF HOW CRITICALITY |
| COULD OCCUR): |
| |
| For a criticality to occur, the following events would be required: The |
| microfiltration system would have to be processing uranium bearing liquid |
| with an unknown or high concentration of uranium. Then a leak in this |
| system must occur such that an unsafe amount of liquid sprays from the |
| system onto the plastic wrap or uncovered pump. The plastic would then have |
| to deform or the pump would have to fill such that 2.5 liters collects to a |
| depth of greater than 1.5 inches. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| volume, geometry |
| |
| Inadvertent containers are controlled based upon volume (2.5 liter) or |
| geometry (1.5" or 4" diameter). Flexible material is specifically controlled |
| such that solution cannot pool to a depth greater than 1.5 inches. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): |
| |
| No uranium material was involved in this event. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| Loose plastic wrap was not configured or secured to prevent deformation into |
| an inadvertent container. The pump flange cover was dislodged. The pump |
| was located on a lower shelf in the same area. This is a violation as |
| control # 5 and # 3 respectively of NCSA-705_076.A.03. |
| |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| The plastic wrap and pump were removed from the inadvertent container area. |
| |
| |
| |
| The NRC Resident Inspector was notified of this event report by the |
| certificate holder. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38206 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/13/2001|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 21:31[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 08/13/2001|
+------------------------------------------------+EVENT TIME: 17:53[EDT]|
| NRC NOTIFIED BY: V. FALLACARA |LAST UPDATE DATE: 08/13/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR SCRAM DURING LOGIC SYSTEM TESTING OF EMERGENCY BUS A5. |
| |
| Pilgrim Unit 1 scrammed from 100% during performance of Logic System Testing |
| of Emergency Bus A5. This is the first time that the Logic System Testing |
| of Emergency Bus A5 had been performed at power. The test is performed once |
| every 24 months and had just been rewritten to be performed at power. The |
| cause of the scram is under investigation at this time but the initiating |
| transient was the loss of Emergency Bus A5. All rods fully inserted into |
| the core. The plant is at 700 lbs. and a controlled depressurization is in |
| progress. Plans are to cooldown to less than or equal to 150 lbs. and |
| repair the outboard RCIC steam isoaltion valve. |
| |
| Due to deenergization of Emergency Bus A5 Recirculation Pump A tripped and |
| there was a fast transfer of the swing bus (this was expected). The |
| licensee is looking into the transfer of the swing bus causing the trip of |
| Recirculation Pump B. Loss of both operating Recirculation Pumps at power |
| will cause a reactor scram. All systems operated properly. The |
| electrical grid is stable and all Emergency Core Cooling systems are fully |
| operable if needed. The Recirculation pumps will be restarted when the |
| differential temperature between the top and bottom head are within |
| specification. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021