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Event Notification Report for November 1, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/31/2001 - 11/01/2001

                              ** EVENT NUMBERS **

38385  38441  38447  38448  38450  38451  38452  
.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38385       |
+------------------------------------------------------------------------------+
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| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 10/14/2001|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 12:14[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        10/14/2001|
+------------------------------------------------+EVENT TIME:        01:59[PDT]|
| NRC NOTIFIED BY:  KUNDSON                      |LAST UPDATE DATE:  10/31/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA HOWELL         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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE REACTOR COOLANT SYSTEM LEAKAGE                                      |
|                                                                              |
| During an inspection, while the plant was in shutdown mode 3, a dry white    |
| residue was discovered on a loop 2 hot leg spare thermowell plug.  Being     |
| conservative they looked at this condition as a possible RCS pressure        |
| boundary leakage while  in an operating mode.  However, there was no active  |
| leak from the spare thermowell plug.  The plant has 36 hours to be in mode   |
| 5.  They will determine the type of repair work necessary to remedy the      |
| problem.                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * RETRACTION 1623 10/31/2001 FROM RODRIGUEZ TAKEN BY STRANSKY * * *      |
|                                                                              |
| "On October 14, 2001, at 0914 PDT, Southern California Edison (SCE) made a   |
| 4-hour telephone notification in accordance with 10CFR50.72(b)(2)(i) for the |
| initiation of a nuclear plant shutdown required by Technical Specification   |
| (TS). The purpose of this call is to retract that notification.              |
|                                                                              |
| "On October 14 2001, Unit 2 was being shutdown to Mode 5 to begin secondary  |
| plant equipment repairs. While in Mode 3, plant personnel discovered a white |
| powdery substance on an RCS thermowell and considered that this could be     |
| dried boric acid and evidence of an RCS boundary leak. SCE logged entry into |
| TS 3.4.13, action 'B' to be in Mode 3 within 6 hours and Mode 5 within 36    |
| hours after discovery of RCS pressure boundary leakage. Even though the      |
| plant was shutdown and on its way to mode 5, because TS 3.4.13, action 'B'   |
| also required a reduction in plant mode, SCE conservatively considered this  |
| to be a 'shutdown required by the TS and made the phone report to the NRC in |
| accordance with 10CFR50.72(b)(2)(I)                                          |
|                                                                              |
| "To investigate this finding, SCE:                                           |
| 1. Removed the thermowell threaded plug and the threads were found clean and |
| dry with no evidence of an RCS pressure boundary leak.                       |
| 2. Inspected the thermowell with a fiber-optic scope and found it clean and  |
| dry with no evidence of an RCS pressure boundary leak,                       |
| 3. Inspected the thermowell-to-nozlle weld and found no indications (i.e.,   |
| weld cracks or defects) present.                                             |
| 4. Analyzed the white powder and concluded it was not boric acid crystals.   |
|                                                                              |
| "Based on this evidence, SCE concluded that an RCS pressure boundary leak    |
| did not exist. Therefore, entry into TS 3.4.13, action 'B' was not required  |
| and a phone-report to the NRC for 'initiation of a plant shutdown required   |
| by the TS' was not required and is now being retracted.                      |
|                                                                              |
| "At the time of the initial report Unit 2 was shutdown in mode 3, and Unit 3 |
| was operating at about 100 percent power. The NRC Resident Inspectors will   |
| be notified of this occurrence and will be provided with a copy of this      |
| report."                                                                     |
|                                                                              |
| HOO Notified R4DO (Spitzberg).                                               |
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.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38441       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 10/30/2001|
|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 09:30[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/30/2001|
+------------------------------------------------+EVENT TIME:        08:50[EST]|
| NRC NOTIFIED BY:  ALLEY/HARRIS                 |LAST UPDATE DATE:  10/31/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |R2 IRC TEAM MANAGER  R2      |
|10 CFR SECTION:                                 |JOHN TAPPERT         NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RENE ZAPATA          FEMA    |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling Shutdow|0        Refueling Shutdow|
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO AN UNPLANNED RADIOLOGICAL RELEASE, 
EMERGENCY  |
| ACTION LEVEL 7.2 (LIQUID EFFLUENT).                                          |
|                                                                              |
| "At 0850 on 10/30/2001 a Notification of Unusual Event (NOUE) was declared   |
| and terminated at 0910 on 10/30/2001 at Sequoyah Nuclear Plant due to an     |
| unplanned radiological release.  At 0640 on 10/30/2001 count rate on         |
| 0-RM-90-212, the Station Discharge Rad Monitor, reached the alarm setpoint   |
| of 600 CPM.  An initial Chem Lab sample taken at 0720 indicated no abnormal  |
| activity.  A followup sample completed at 0802 confirmed activity in the     |
| Turbine Building Sump.  The Chem Lab samples confirmed the validity of this  |
| alarm and the REP declaration requirements were met.  At 0810 the release    |
| was terminated by isolating the station sump and realigning to the Low       |
| Volume Waste Treatment Pond.  Readings on 0-RM-90-212 are slowly trending up |
| at present 39000 CPM.  Investigation is in progress to determine and correct |
| the source.  Detailed sample analysis are also in progress to identify the   |
| magnitude and nuclides involved in this release.  Followup information will  |
| be provided when available."  State and Local officials were notified of     |
| this event by the licensee.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * UPDATE 1627EST ON 10/31/01 FROM CALVIN FIELDS TO S. SANDIN * * *       |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "This is an update to the October 30, 2001, notification. Subsequent         |
| analysis show that the total activity in the TB Sump was less than 35% of    |
| the ODCM limit. No release limits were exceeded and, therefore, the NOUE     |
| criteria of 2 times the ODCM limits did not exist. In accordance with        |
| NUREG-1022, Rev. 2, Section 2.8, TVA is retracting the previous notification |
| via this follow-up telephone call."                                          |
|                                                                              |
| The licensee informed the NRC Resident Inspector and will inform both state  |
| and local agencies.  Notified R2IRC.                                         |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38447       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 10/31/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 14:55[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        10/30/2001|
+------------------------------------------------+EVENT TIME:        19:00[EST]|
| NRC NOTIFIED BY:  D. COSEO                     |LAST UPDATE DATE:  10/31/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT DUE TO VIOLATION OF LICENSE CONDITION                         |
|                                                                              |
| "On 10/30/2001 at 1900 hours, during a walkdown of approximately 600 fire    |
| barrier penetrations which had been mistakenly excluded from the Fermi 2     |
| fire barrier penetration seal inspection program, 11 penetrations were found |
| to have no seal material installed. To date, over 350 of the approximately   |
| 600 fire barrier penetrations not included in the program have been          |
| inspected. The lack of seal material in these penetrations constitutes an    |
| inoperable 10 CFR 50, Appendix R fire rated barrier and is reportable under  |
| License Condition 2.F as a violation of License Condition 2.C (9),           |
| 'Modifications for Fire Protection.' The plant is currently shut down for    |
| refueling. Hourly fire watches have been established in the affected areas   |
| as required by the Technical Requirements Manual. Detroit Edison will report |
| any further missing seals that are identified as part of this inspection."   |
|                                                                              |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38448       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 10/31/2001|
|    UNIT:  [] [2] []                 STATE:  MN |NOTIFICATION TIME: 16:59[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/31/2001|
+------------------------------------------------+EVENT TIME:        14:09[CST]|
| NRC NOTIFIED BY:  BODIN                        |LAST UPDATE DATE:  10/31/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL TURBINE/REACTOR TRIP                                                  |
|                                                                              |
| "Unit 2 Turbine Condenser Air Ejector was isolated for a potential steam     |
| leak. After the condenser air ejector was isolated, the A/B condenser        |
| differential reached 2.5" Hg vacuum. This is a procedural requirement to     |
| trip the turbine. Operators initiated a manual reactor/turbine trip at 1409. |
| The main steam isolation valves were manually closed to ensure air ejector   |
| isolation. Steam generator (S/G) power operated relief valves (PORVs) are    |
| controlling RCS temperature at 547 degrees F.                                |
|                                                                              |
| "Both auxiliary feedwater pumps auto started on low S/G levels. N35 NIS      |
| intermediate range detector failed to reach the source range setpoint.       |
| Source range detectors were manually reenergized."                           |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
| The licensee plans to issue a press release regarding this event.            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38450       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GEO ENGINEERING                      |NOTIFICATION DATE: 10/31/2001|
|LICENSEE:  GEO ENGINEERING                      |NOTIFICATION TIME: 18:06[EST]|
|    CITY:  CAROLINA                 REGION:  2  |EVENT DATE:        10/31/2001|
|  COUNTY:                            STATE:  PR |EVENT TIME:             [EST]|
|LICENSE#:  52-25266-01           AGREEMENT:  N  |LAST UPDATE DATE:  10/31/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |R2 IRC TEAM MANAGER  R2      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HEMANES                      |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED MOISTURE/DENSITY GAUGE                                               |
|                                                                              |
| A CPN model MC-1 moisture/density gauge (S/N M15076270) was damaged when it  |
| was run over. The source rod was not exposed at the time of the event. The   |
| Puerto Rico Health Department responded to the scene and surveyed the gauge, |
| but found no evidence of contamination. The gauge has been secured pending   |
| further action by the licensee.                                              |
|                                                                              |
| The licensee has contacted an NRC inspector in Puerto Rico, who is going to  |
| respond to the scene tomorrow.                                               |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38451       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE:
10/31/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:33[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/31/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        13:20[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/31/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FIRE WATER SYSTEM ISOLATION VALVE FOUND CLOSED                               |
|                                                                              |
| "DURING PERFORMANCE OF PROCEDURE XP4-CU-UG6206 'HIGH PRESSURE FIRE
WATER     |
| SYSTEM (HPFW) UNDERGROUND DISTRIBUTION LOOP TESTING,' UTILITY
OPERATIONS AND |
| FIRE FIGHTING PERSONAL DISCOVERED A SECTIONAL ISOLATION VALVE, THAT WAS  
   |
| EXPECTED TO BE OPEN, WAS RESTRICTING FLOW TO THE PORTION OF THE LOOP
BEING   |
| TESTED. THIS RESTRICTION IN THE LOOP CAUSED A PORTION OF THE HPFW
SPRINKLER  |
| SYSTEM FOR THE X-326 BUILDING TO FAIL TO PERFORM ITS INTENDED SAFETY         |
| FUNCTION (FIRE SUPPRESSION). UPON IDENTIFYING THE PROBLEM THE FIRE           |
| DEPARTMENT NOTIFIED THE PLANT SHIFT SUPERINTENDENT (PSS) WHO
IMMEDIATELY     |
| DECLARED THE HPFW SPRINKLERS SYSTEMS IN THE X-326 BUILDING INOPERABLE,
AND   |
| DIRECTED THE REQUIRED TSR ACTIONS TO BE PERFORMED. UTILITY OPERATIONS     
  |
| PERSONNEL SECURED THE TEST AND REOPENED ALL SECTIONAL ISOLATION
VALVES THAT  |
| WERE SHUT FOR THE TEST. AT 1345 HOURS HPFW WAS RESTORED TO THE
ISOLATED      |
| PORTION OF THE LOOP.                                                         |
|                                                                              |
| "ENTIRE EVOLUTION IS UNDER INVESTIGATION AT THIS TIME."                      |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38452       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 10/31/2001|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 18:44[EST]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        10/31/2001|
+------------------------------------------------+EVENT TIME:        14:23[CST]|
| NRC NOTIFIED BY:  KEITH TABER                  |LAST UPDATE DATE:  10/31/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING HYDRAULIC OIL SPILL                           |
|                                                                              |
| "At 1423 hours CST Wednesday October 31, 2001 LaSalle control room received  |
| notification of an oil sheen at the Illinois River intake structure for      |
| LaSalle County Nuclear Stations Unit 1 and 2. Station procedures and the     |
| Spill Prevention Control and Counter Measures Plan was entered and the       |
| station Environmental Specialist and HAZMAT qualified personnel were         |
| dispatched to the scene.                                                     |
|                                                                              |
| The Environmental Specialist notified the Main Control room that hydraulic   |
| fluid from the River intake structure equipment had leaked into the          |
| screenhouse inlet and due to a gap between in the floating boom and the      |
| concrete structure some hydraulic fluid had been released to the Illinois    |
| River. Current estimate is that approximately 5 gals of hydraulic fluid      |
| entered the inlet and approximately 100 milliliters was released into the    |
| Illinois River. Per the Exelon Reportability Manual ENV 3.19, and 40 CFR     |
| 110.10 Discharge of Oil into or upon Navigable Waters or Adjoining           |
| Shorelines the release of oil into the Illinois River is reportable to the   |
| National Response Center and Illinois Emergency Management Agency (IEMA)     |
| with in 1 hour. The National Response Center was notified at 1448 CST and    |
| the Illinois Emergency Management Agency was notified at  1505 CST. Pursuant |
| to Exelon Reportability Manual SAP 1.9, and 10 CFR 50.72(b)(2)(xi)           |
| notification to the NRC is required to be notified within 4 hours, this      |
| notification is being made to address this requirement.                      |
|                                                                              |
| "Currently, the HAZMAT team is at the scene and the oil release to the river |
| has been stopped. Cleanup efforts are underway using oil booms and oil soak  |
| rags."                                                                       |
|                                                                              |
| The NRC resident inspector has been notified of this event.                  |
+------------------------------------------------------------------------------+
.