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Event Notification Report for August 20, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/17/2001 - 08/20/2001

                              ** EVENT NUMBERS **

38119  38214  38218  38219  38220  38221  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38119       |
+------------------------------------------------------------------------------+
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| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 07/05/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 16:03[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        07/05/2001|
+------------------------------------------------+EVENT TIME:        10:00[EDT]|
| NRC NOTIFIED BY:  COSEI                        |LAST UPDATE DATE:  08/17/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS FOR OPRM SCRAM SETPOINTS                           |
|                                                                              |
| On July 5, 2001, Detroit Edison received confirmation from General Electric  |
| of a non-conservative analysis that supports Operation Power Range Monitor   |
| (OPRM) scram setpoints.  The non-conservative analysis is generic and been   |
| determined to affect Fermi 2.   The OPRM had been conservatively declared    |
| inoperable on June 27, 2001, at 1333 hours as a result of preliminary        |
| notification by General Electric.                                            |
|                                                                              |
| The consequences of the non-conservative analysis are that the associated    |
| OPRM Reactor Protective System (RPS) scram setpoints are non-conservative.   |
| The non-conservative RPS setpoints may result in violating the Minimum       |
| Critical Power Ratio (MCPR) safety limit during a thermal-hydraulic          |
| instability.                                                                 |
|                                                                              |
| All OPRM channels have been declared inoperable. Technical Specification     |
| 3.3.1.1 Action J requires an alternate method of detecting and suppressing   |
| thermal-hydraulic instabilities to be implemented within 12 hours.           |
| Alternate methods have been established, thus, the Technical Specification   |
| required action is satisfied.   Fermi 2 has 120 days to restore the OPRMs to |
| an operable condition.                                                       |
|                                                                              |
| This initial report is being made in accordance with 10CFR50.72 (B)(3)(V)(A) |
| as a condition that could have prevented the fulfillment of the safety       |
| function of a system needed to shutdown the reactor.                         |
|                                                                              |
| See EN #38104, GE Nuclear Energy 10CFR21 report.                             |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| * * * RETRACTED AT 1443 EDT ON 8/17/2001 BY PATRICK FALLON TO FANGIE JONES * |
| * *                                                                          |
|                                                                              |
| The licensee is retracting the event notification.                           |
|                                                                              |
| "Subsequent design calculations have concluded that there was sufficient     |
| conservatism in the existing OPRM RPS scram setpoints to accommodate         |
| corrections for the non-conservative analysis performed by General Electric, |
| which was the subject of their 10 CFR 21 Notification dated June 29, 2001    |
| (SC01 -01), and still provide protection for the Minimum Critical Power      |
| Ratio (MCPR) Safety Limit during a thermal-hydraulic instability throughout  |
| the current operating cycle. The OPRM RPS scram function was not required to |
| be operable prior to the current operating cycle. Since the existing OPRM    |
| RPS scram setpoints have been shown to be set conservatively, the OPRM       |
| system was operable, and therefore no situation existed which was            |
| reportable."                                                                 |
|                                                                              |
| The licensee has notified the NRC Resident Inspector.  The R3DO (Thomas      |
| Kozak) has been notified.                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38214       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 08/16/2001|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 11:40[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        08/16/2001|
+------------------------------------------------+EVENT TIME:        09:25[EDT]|
| NRC NOTIFIED BY:  PETER ORPHANOS               |LAST UPDATE DATE:  08/17/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| ALL EMERGENCY OFFSITE SIRENS INOPERABLE                                      |
|                                                                              |
| The licensee determined that all 16 Emergency Offsite Sirens were            |
| inoperable.  The exact cause of the failure is unknown and a plan is being   |
| developed to repair the sirens.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector and intends to notify the   |
| state and local authorities.                                                 |
|                                                                              |
| * * * UPDATED AT 1735 EDT ON 8/16/2001 BY PETER ORPHANOS TO FANGIE JONES * * |
| *                                                                            |
|                                                                              |
| "As of 1300 August 16, 2001 163 of 165 Limerick Generating Station Emergency |
| Offsite Sirens are determined to be functional.                              |
|                                                                              |
| "A plan has been developed and investigation continues into the cause of the |
| inoperability of the sirens."                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (William Ruland) |
| has been notified.                                                           |
|                                                                              |
| * * * UPDATED AT 1751 EDT ON 8/17/2001 BY GREG SOSSON TO FANGIE JONES * * *  |
|                                                                              |
| "As of 17:30, August 17, 2001 163 of 165 Limerick Generating Station         |
| Emergency Offsite Sirens remain fully functional The status of the sirens is |
| being continuously monitored as part of the troubleshooting plan             |
|                                                                              |
| "There was one 20 minute interruption of the siren system early this morning |
| Since then, the sirens have continued to function properly.                  |
|                                                                              |
| "The investigation and troubleshooting will continue through the weekend.    |
|                                                                              |
| "Contingency public notification plans have been confirmed to be in place    |
| with the counties."                                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Ronald Bellamy) |
| has been notified.                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38218       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 08/17/2001|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 00:31[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        08/16/2001|
+------------------------------------------------+EVENT TIME:        23:25[EDT]|
| NRC NOTIFIED BY:  STEVE TANNER                 |LAST UPDATE DATE:  08/17/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM RULAND       R1      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       82       Power Operation  |82       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY SIREN REMOTE ACTUATION CAPABILITY                          |
|                                                                              |
| "Omni phone system was lost resulting in a loss of Emergency Siren remote    |
| actuation control.  Power was lost 8/16/01 22:25 EDT and restored 8/16/01    |
| 23:55 EDT.  Per reportability manual ID# E-02 and Event# SAF 1.10, loss of   |
| assessment capability is reportable after 8 hours, but loss of greater than  |
| 25% of the sirens for more than one hour constitutes immediate               |
| notification.                                                                |
|                                                                              |
| "The omni phone system was lost due to the associated battery voltage        |
| becoming too low to support system operation.  This was caused by a          |
| temporary battery charger installed in place of the normal charger (due to a |
| failed transformer) not maintaining the battery adequately charged.          |
| Immediate omni system recovery was effected using available AC power from an |
| alternate source to power up the equipment.  Long term plans are to replace  |
| the failed transformer and return the normal charger to service."            |
|                                                                              |
| The licensee informed the NRC resident inspector and will inform state/local |
| agencies.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38219       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  McMINN'S ASPHALT CO., INC.           |NOTIFICATION DATE: 08/17/2001|
|LICENSEE:  McMINN'S ASPHALT CO., INC.           |NOTIFICATION TIME: 04:59[EDT]|
|    CITY:  MANHEIM                  REGION:  1  |EVENT DATE:        08/17/2001|
|  COUNTY:                            STATE:  PA |EVENT TIME:        00:30[EDT]|
|LICENSE#:  371965901             AGREEMENT:  N  |LAST UPDATE DATE:  08/17/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM RULAND       R1      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GARY LUTZ                    |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER GAUGE DAMAGED BY VEHICLE AT CONSTRUCTION SITE                        |
|                                                                              |
| At 0030EDT on 8/17/01 a light pickup truck struck a Troxler gauge at a road  |
| construction project on State Road 340 in Lancaster, PA.  The East Lampeter  |
| Police Department responded (Incident # 01-414) briefly closing traffic.     |
| The RSO surveyed the device and confirmed that the sealed source was intact  |
| prior to removal.  The Troxler is a model 4640B containing an 8-millicurie   |
| Cs-137 source.  The licensee is returning the device to the manufacturer's   |
| service center in Timonium, MD for inspection and repair.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38220       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 08/17/2001|
|    UNIT:  [] [] [3]                 STATE:  AZ |NOTIFICATION TIME: 21:19[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        08/17/2001|
+------------------------------------------------+EVENT TIME:        16:45[MST]|
| NRC NOTIFIED BY:  RUSSELL STROUD               |LAST UPDATE DATE:  08/17/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|10 CFR SECTION:                                 |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       97       Power Operation  |55       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE A LEAK FROM THE FUEL POOL INTO CONTAINMENT   |
|                                                                              |
| "On August 17, 2001 at approximately 1245 MST, Palo Verde Unit 3 was at      |
| approximately 97 percent power and at normal RCS temperature and pressure,   |
| when operations personnel detected an increase in containment sump level.    |
| Subsequent investigation revealed the quick operating closure device (QOCD)  |
| (EQID #PCE-M01) that isolates the containment from the fuel transfer tube    |
| was leaking by borated water from the fuel transfer canal at approximately 1 |
| gallon per minute. Operations personnel entered TS LOC 3.6.1 Containment,    |
| Required Action A. This action requires the containment be restored to an    |
| operable status within one hour.                                             |
|                                                                              |
| "Since containment integrity was uncertain, and compliance with LCD 3.6 1    |
| Required Action A could not be met within one hour, operations personnel     |
| entered LCD 3.6.1, Required Action 8.1 at 1345 MST. Required Action B.1      |
| requires the unit be placed in Mode 3 in 6 hours, and Required Action 8.2    |
| requires the unit be placed in Mode 5 within 36 hours, Following operations  |
| briefings, shutdown was commenced at approximately 1645 MST. At this time,   |
| Palo Verde Unit 3 is continuing to reduce power in an orderly manner and     |
| anticipates being in Mode 3 (Hot Standby) by approximately 1845 MST.         |
|                                                                              |
| "There were no other component failures, testing or work in progress that    |
| contributed to this event. The QOCD leak is allowing 4400 part per million   |
| borated water into the containment. There has been no release of             |
| radioactivity to the environment and no impact to the health and safety of   |
| the public has occurred or is anticipated. There is no elevated RCS activity |
| and heat removal is via normal steaming to the main turbine condenser. The   |
| electric grid is stable."                                                    |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38221       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 08/18/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 08:23[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        08/18/2001|
+------------------------------------------------+EVENT TIME:        05:30[CDT]|
| NRC NOTIFIED BY:  GARY OHMSTEAD                |LAST UPDATE DATE:  08/18/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TECHNICAL SUPPORT CENTER UNAVAILABLE                                         |
|                                                                              |
| The licensee deenergized electrical buses supplying the Technical Support    |
| Center in order to perform regularly scheduled maintenance to a circuit      |
| breaker and transformer. Contingency plans are in place in the event that    |
| the TSC becomes necessary to support onsite activities. The licensee         |
| estimates that power will be restored to the facility within 12 hours. The   |
| NRC resident inspector has been informed of this notification.               |
+------------------------------------------------------------------------------+