Event Notification Report for February 21, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/20/2002 - 02/21/2002
** EVENT NUMBERS **
38710 38711 38712 38713 38714
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|Power Reactor |Event Number: 38710 |
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| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/20/2002|
| UNIT: [] [2] [3] STATE: CT |NOTIFICATION TIME: 09:26[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/19/2002|
+------------------------------------------------+EVENT TIME: 15:30[EST]|
| NRC NOTIFIED BY: JOE RUTTAR |LAST UPDATE DATE: 02/20/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL MODES R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
|3 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| FITNESS FOR DUTY REPORT |
| |
| A contract supervisor tested positive on pre-access screening drug test. |
| Access was never granted to site. The licensee notified the NRC Resident |
| Inspector and will notify the State of Connecticut. |
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|Hospital |Event Number: 38711 |
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| REP ORG: MONTGOMERY HOSPITAL |NOTIFICATION DATE: 02/20/2002|
|LICENSEE: |NOTIFICATION TIME: 13:17[EST]|
| CITY: MORRISTOWN REGION: 1 |EVENT DATE: 02/20/2002|
| COUNTY: STATE: PA |EVENT TIME: 10:00[EST]|
|LICENSE#: 3712110-02 AGREEMENT: N |LAST UPDATE DATE: 02/20/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL MODES R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROSEMARY NACE | |
| HQ OPS OFFICER: MIKE NORRIS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAA1 20.1906(d)(1) SURFACE CONTAM LEVELS | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| SHIPMENT WITH REMOVABLE RADIOACTIVE SURFACE CONTAMINATION EXCEEDING
THE |
| LIMITS |
| |
| A shipment of 170 millicuriesTc-99 diagnostic vials was shipped to |
| Montgomery Hospital, Morristown PA from Mallinckrodt Pharmacy, Philadelphia, |
| PA. An incoming survey on the outside of the shipping package indicated |
| loose smearable levels of 938,000 to 1,000,000 dpm/smear of beta-gamma |
| contamination. Surveys of the shipping vehicle and driver indicated no |
| removable contamination. No personnel at the Hospital were contaminated and |
| the shipping package is stored in the hospital hot cell. The material was |
| shipped non-exclusive use. |
| |
| Licensee contacted Michelle Beardsley at R1 and the shipper. |
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|Power Reactor |Event Number: 38712 |
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| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 02/20/2002|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:25[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/20/2002|
+------------------------------------------------+EVENT TIME: 08:00[EST]|
| NRC NOTIFIED BY: CHRISTOPHER SEATA |LAST UPDATE DATE: 02/20/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL MODES R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| FITNESS FOR DUTY REPORT |
| |
| A non-licensed Supervisory employee was determined to have failed to comply |
| with FFD procedures during random test. The employee's access to the plant |
| has been terminated. Contact the HOO for additional details. |
| |
| The Resident Inspector has been notified. |
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|Power Reactor |Event Number: 38713 |
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| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 02/20/2002|
| UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 16:34[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/20/2002|
+------------------------------------------------+EVENT TIME: 15:00[EST]|
| NRC NOTIFIED BY: MICHAEL HOWARD |LAST UPDATE DATE: 02/20/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| SAFE SHUTDOWN CAPABILITY IMPACTED BY NON-CONSERVATIVE SG NR SETPOINT
|
| |
| "Based on the review of [Operating Experience (GE)] 13294 from Diablo Canyon |
| regarding unexpected response of Steam Generator [(SG)] Narrow Range level |
| trip not responding as expected, an assessment was performed of the narrow |
| range (NR) Steam Generator level channels at Sequoyah 1 and 2. This |
| assessment determined that the current 10.7% lo-lo level trip setpoint did |
| not account for the uncertainties associated with the differential pressure |
| (dP) created by the steam flow past the mid-deck plate in the moisture |
| separator section of the steam generator. This dP phenomena will cause the |
| SG NR level channels to read higher than actual water level at high steam |
| flows. Thus, the lo-lo level trip setpoint is non-conservative. |
| |
| "In the unlikely event of a Loss of Normal Feedwater or a Loss of Offsite |
| Power, the potential exists that a required reactor trip on lo-lo steam |
| generator level may be delayed or may not be received at all. In this |
| scenario, other trip functions such as overtemperature delta-T would be |
| expected to actuate in response to the initiating event. However, these |
| would arrive in a different sequence, and the net effect on the UFSAR |
| Chapter 15 accident analysis results is unknown. Thus, a condition exists in |
| that a safety function could have been prevented. |
| |
| "As a conservative measure, upon identification of this condition by |
| Westinghouse via NSAL 02-3, the environmental allowance monitor (EAM) was |
| actuated on U-1and U-2 on Friday, February 15, 2002. This feature changes |
| the S/G Lo-Lo Level Rx Trip setpoint from 10.7% to 15%. Since the known S/G |
| channel uncertainty is 8.3% with a narrow range span uncertainty of 5.3%, it |
| was determined that operating with the EAMs continuously actuated will allow |
| continued operation. After further evaluation of this condition, it has |
| been determined that 10CFR 50.72(b)(3)(v)(A) applies as a condition that at |
| the time of discovery could have prevented the fulfillment of the safety |
| function of structures or systems that are needed to shutdown the reactor |
| and maintain it in a safe shutdown condition. |
| |
| "EAMs actuated on U-1 at time of discovery (vent in progress). EAMs |
| actuated at 1814 on 2/20/02." |
| |
| The licensee informed the NRC Resident Inspector. |
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|General Information or Other |Event Number: 38714 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE:
02/21/2002|
|LICENSEE: ROB GREGER |NOTIFICATION TIME: 00:20[EST]|
| CITY: REGION: 4 |EVENT DATE: 02/21/2002|
| COUNTY: STATE: CA |EVENT TIME: [PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 02/21/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROB GREGOR | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 24 HOUR AGREEMENT STATE REPORT - STOLEN NUCLEAR DENSITY GAUGE |
| |
| A report of a stolen CPN moisture density gauge. CPN is Campbell Pacific |
| Nuclear. |
| |
| A fax of the report was to follow. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021