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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 !!!!!!!
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|Power Reactor |Event Number: 38441 |
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| 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. |
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+------------------------------------------------------------------------------+
|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
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| 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. |
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