Event Notification Report for March 8, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/05/1999 - 03/08/1999
** EVENT NUMBERS **
35349 35433 35441 35442 35443 35444 35445 35446
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35349 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/05/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 17:34[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/05/1999|
+------------------------------------------------+EVENT TIME: 17:25[EST]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JULIAN WILLIAMS R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - RHR & CS SYSTEMS FLOW INSTRUMENT POWER SUPPLY LINES ROUTED IN SAME CABLE |
| TRAY - |
| |
| AT 1725 ON 02/05/99, DURING A REVIEW FOR A DESIGN CHANGE, THE LICENSEE |
| DISCOVERED THAT THE 120-VAC POWER FEED TO POWER SUPPLY #PS10-100B IS ROUTED |
| IN THE SAME DIVISION II CABLE TRAY AS POWER SUPPLY #PS10-100A. THESE TWO |
| POWER SUPPLIES ARE INTENDED TO BE REDUNDANT TO EACH OTHER AND SUPPLY POWER |
| TO REDUNDANT TRAINS OF RESIDUAL HEAT REMOVAL (RHR) SYSTEM AND CORE SPRAY |
| (CS) SYSTEM FLOW INSTRUMENTATION. A LICENSEE OPERABILITY DETERMINATION |
| CONCLUDED THAT THE FLOW INSTRUMENTATION IS OPERABLE, AND THERE IS NO ADVERSE |
| IMPACT ON PRESENT PLANT OPERATIONS. THE LICENSEE IS DETERMINING CORRECTIVE |
| ACTIONS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
| |
| ***RETRACTION ON 03/05/99 AT 1532ET BY ANDREW WISNIEWSKI TAKEN BY |
| MACKINNON*** |
| |
| EVENT IS BEING RETRACTED AFTER FURTHER EVALUATION DETERMINED THAT THE ABOVE |
| MENTIONED FLOW INSTRUMENTATION IS STILL CLASSIFIED UNDER THE ORIGINAL SER |
| (REG. GUIDE 1.97 SUBMITTAL) AS TYPE "D", CATEGORY 2 AND 3, WHICH DOES NOT |
| REQUIRE REDUNDANCY. IN ADDITION A REVIEW HAS CONFIRMED THAT THIS IS NOT |
| TECHNICAL SPECIFICATION REQUIRED INSTRUMENTATION. R1DO(MICHAEL MODES ) |
| NOTIFIED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS RETRACTION BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35433 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: INTERNATIONAL PAPER CO. |NOTIFICATION DATE: 03/02/1999|
|LICENSEE: INTERNATIONAL PAPER CO |NOTIFICATION TIME: 17:52[EST]|
| CITY: LOCK HAVEN REGION: 1 |EVENT DATE: 03/02/1999|
| COUNTY: STATE: PA |EVENT TIME: 15:00[EST]|
|LICENSE#: GL1933-70 AGREEMENT: N |LAST UPDATE DATE: 03/06/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL MODES R1 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LAIRD | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE IS MISSING A CONSISTENCY GAUGE FOR A PAPER MACHINE |
| |
| THE GAUGE, NDC SYSTEMS MODEL # 104, CONTAINS 80 MILLICURIES OF AM-241 AND IS |
| USUALLY MOUNTED TO THE PAPER MACHINE. IT WAS LAST INVENTORIED 6 MONTHS AGO |
| WHEN IT WAS LOCATED IN A BOX IN ONE OF THEIR OFFICES. THEY MAY BE ABLE TO |
| LOCATE IT WHEN THEY CAN CONTACT AN EMPLOYEE WHO MAY KNOW WHERE IT IS. |
| |
| * * * UPDATE 0947EST ON 3/6/99 FROM LARRY LAIRD TO S.SANDIN * * * |
| |
| THE LICENSEE LOCATED THE MISSING SOURCE. IT WAS FOUND IN THE ORIGINAL |
| SHIPPING CONTAINER STORED IN THEIR TEAM ROOM. NOTIFIED R1DO(MODES) AND |
| EO(HODGES). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35441 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/05/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:49[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 03/05/1999|
+------------------------------------------------+EVENT TIME: 09:51[EST]|
| NRC NOTIFIED BY: RICHARD SWEENY |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STATE NOTIFIED OF A KEMP'S RIDLEY SEA TURTLE RETRIEVED FROM THE PLANT INTAKE |
| WATER |
| |
| A young healthy Kemp's Ridley sea turtle was taken from the water at the |
| intake of Crystal River Unit 3. The turtle was transported to the Crystal |
| River Mariculture Center. The Florida Department of Environmental |
| Protection was notified of the retrieval of the sea turtle. The turtle will |
| be transported to the Clearwater Marine Science Center. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35442 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: UNIVERSITY RADIOLOGY GROUP |NOTIFICATION DATE: 03/05/1999|
|LICENSEE: UNIVERSITY RADIOLOGY GROUP |NOTIFICATION TIME: 12:15[EST]|
| CITY: NEW BRUNSWICK REGION: 1 |EVENT DATE: 03/05/1999|
| COUNTY: STATE: NJ |EVENT TIME: 07:30[EST]|
|LICENSE#: 29-17475-01 AGREEMENT: N |LAST UPDATE DATE: 03/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL MODES R1 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BOB TOKARZ | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS AND RECOVERY OF DISPOSABLE RUBBER GLOVES CONTAMINATED WITH LESS THAN 10 |
| MILLICURIES OF IODINE-131. |
| |
| Last night a cleaning crew accidentally removed a clear plastic bag from the |
| licensee's hot lab and placed the plastic bag into the facilities regular |
| trash system. The trash was picked up by the local trash company early this |
| morning. Before the trash truck arrived at the dump the licensee had |
| stopped the trash truck and recovered the clear plastic bag containing the |
| contaminated disposable rubber gloves. No one was contaminated or received |
| exposure from the contaminated disposable rubber gloves. The plastic bag |
| is back in the hot lab and the licensee's corrective action is not to let |
| the cleaning crew enter the hot lab. |
| |
| NRC Region 1 (Lodhi) was notified of this event by the NRC Headquarters |
| Operations Officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35443 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 03/05/1999|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 13:26[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 03/05/1999|
+------------------------------------------------+EVENT TIME: 10:15[PST]|
| NRC NOTIFIED BY: CONOSCENTI/PENNA |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |DALE POWERS R4 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOHN DAVIDSON, IAT |
| |ROBERTA WARREN, IAT |
| |ROSANO, IAT |
| |CHAMBERLAIN, IAT R4 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOMB THREAT. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. OUTSIDE |
| AGENCY INVOLVED, (FBI). |
| |
| LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
| |
| AT 1343 ET THE UNITED STATES NUCLEAR REGULATORY COMMISSION ENTERED |
| MONITORING PHASE OF NORMAL MODE. |
| |
| ***COMMISSIONER'S ASSISTANCE BRIEFING ON 03/05/99 AT 1600 ET BRIEFED BY PAT |
| GWYNN (ACTING NRC REGION 4 REGIONAL ADMINISTRATOR) |
| |
| PARTICIPANTS: IRO (FRANK CONGEL), PAO (SUE GAGNER), STATE PROGRAMS |
| (SOLLENBERGER), CAO (TOM COMBS), EDO OFFICE (TOM HILTZ), DEDE (MAL KNAPP & |
| J. MITCHELL), NRR (SAM COLLINS), CHAIRMAN'S OFFICE (MARK MILLER), COMM. |
| MCGAFFIGAN'S OFFICE (JIM BEALL), COMM. DIAZ'S OFFICE (TONY HSIA), COMM. |
| DICUS' OFFICE (TERENCE CHAN), COMM. MERRIFIELD'S OFFICE (BRIAN McCABE), |
| NMSS (LIZ TEN EYCK), & IAT (ROBERTA WARREN). R4DO (DID NOT PARTICIPATE). |
| |
| |
| |
| ***** UPDATE AT 1527 ET ON 03/05/99 BY MACKINNON ********** |
| |
| THE UNITED STATES NUCLEAR REGULATORY COMMISSION EXITED MONITORING PHASE OF |
| NORMAL MODE AFTER THE ALERT WAS TERMINATED AT 1227 PST. |
| |
| FEDERAL AGENCIES NOTIFIED OF THE ENTERING AND EXITING OF THE ABOVE |
| EVENT(NOTIFIED BETWEEN APPROXIMATELY 1610 HOURS AND ABOUT 1640 HOURS ON |
| 03/05/99): |
| |
| USDA (RON GRAHAM), DOE (BRAD ZACHMAN), HHS (JIM RABB), FEMA (CHARLIE |
| BAGWELL), DOT-NRC (LT. HUDSPETH), EPA REGION IX (ROBIN CLEMENS), AND FBI |
| (TOM CASH). |
| |
| MR. JOSE LUIS DELGADO OF THE MEXICAN NUCLEAR SAFETY COMMISSION WAS NOTIFIED |
| OF THIS EVENT. |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT UPDATE BY THE |
| LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35444 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LACROSSE REGION: 3 |NOTIFICATION DATE: 03/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 18:04[EST]|
| RXTYPE: [1] AC (ALLIS CHAMBERS) |EVENT DATE: 03/05/1999|
+------------------------------------------------+EVENT TIME: 15:45[CST]|
| NRC NOTIFIED BY: MIKE JOHNSEN |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SEISMIC CONCERN WITH MAINTAINING SPENT FUEL POOL WATER LEVEL IF THE SPENT |
| FUEL POOL RETURN LINE (ENTERS BOTTOM OF THE SPENT FUEL POOL) RUPTURES |
| DURING A SEISMIC EVENT. |
| |
| The spent fuel pool has a return line which enters through the bottom of the |
| spent fuel pool. During surveillance testing of the spent fuel pool it was |
| determined that two in series 4 inch check valves (58-26-007, 008; fuel |
| storage well return check valves) have back leakage of between 15 to 16 |
| gallons per minute. Makeup capacity to the spent fuel pool (fuel storage |
| well system) is 5 gallons per minute. If a seismic event (they have never |
| had a seismic event) caused the spent fuel pool return line to rupture the |
| spent fuel pool water inventory could be decreasing between 15 to 16 gallons |
| per minute and regular makeup to the spent fuel pool would be 5 gallons per |
| minute. |
| |
| The spent fuel pool contains 333 fuel assemblies. The cladding for the |
| spent fuel rods is made of stainless steel and the fuel has been in the |
| spent fuel pool since 1987. The temperature of the spent fuel pool is |
| between 110 to 111 degrees F with no spent fuel pooling cooling. |
| |
| Contingency actions being taken by the license: |
| |
| Isolate manual isolation valves as close to the check valves as possible if |
| the line breaks. |
| Reduce spent fuel pool temperature (this weekend) from 110 degrees to |
| between 70 and 80 degrees F. |
| |
| |
| An LER will be submitted within 30 days concerning the potential loss of |
| spent fuel pool water inventory via the return line if it is ruptured during |
| a seismic event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35445 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/05/1999|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 18:40[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/01/1999|
+------------------------------------------------+EVENT TIME: 13:55[CST]|
| NRC NOTIFIED BY: D SLAGER |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF SHUTDOWN COOLING TWICE DURING PAST REFUELING OUTAGE |
| |
| On February 1, and February 2, 1999, the Unit 3 shutdown cooling isolation |
| valves isolated due to an invalid 350 degree F recirculation loop |
| temperature input signal. The actual reactor water temperature was less |
| than 212 degrees F. |
| |
| This event was determined not to be reportable in accordance with the site |
| reportability manual. Upon further review of deficiency documents, it was |
| determined this event should have been reported in accordance with 10 CFR |
| 50.72(b)(2)(ii). |
| |
| The shutdown cooling isolation valves are part of the Primary Containment |
| Isolation System (PCIS) which is an Engineered Safeguard Feature (ESF). The |
| 350 degree F trip signal is electrically part of the PCIS trip logic |
| circuitry. This signal will cause an isolation actuation, which is processed |
| through the PCIS ESF logic, resulting in closure of the shutdown cooling |
| isolation valves. Even though the signal was invalid, the system was not an |
| excepted system and these valves were actuated unnecessarily and therefore |
| this event is being reported as an invalid ESF actuation. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35446 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 03/05/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:02[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/05/1999|
+------------------------------------------------+EVENT TIME: 18:30[EST]|
| NRC NOTIFIED BY: GEORGE E. STOROLIS |LAST UPDATE DATE: 03/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL MODES R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Discrepancies in the post-fire plant operating procedures identified. |
| |
| A review with engineering fire protection self-assessment has identified |
| discrepancies in the post-fire plant operating procedures. Various steps |
| require manual actions to be performed in the fire area of concern. Smoke |
| and heat from the postulated fire could prevent the actions from being |
| accomplished as per the procedure instructions. Specifically in fire area |
| PA-4 (Auxiliary Building, Elevation 755 feet), spurious operation of |
| 2CHS*LCV115C or 2CHS*LCV115E, Volume Control Tank (VCT) outlet to charging |
| pump suction valves, requires that the valve's breaker be opened to allow |
| local closing of the associated valve. Even though the valves are located |
| outside fire area PA-4, the operator has to travel through fire area PA-4 to |
| get to the breakers. This action may not be able to be accomplished due to |
| the fire event. If the VCT outlet is not isolated, there could be intrusion |
| of gases from the VCT which could cause a loss of charging capability. The |
| procedure provides inadequate actions to recover from this scenario. This |
| could result in the plant not being able to achieve a safe shutdown as |
| required by the fire protection analysis. |
| |
| A condition report has been written to document this issue along with other |
| potential procedure discrepancies. Currently Unit 2 is in Mode 5 (Cold |
| Shutdown) where this issue is not an operability concern at this time. The |
| root cause and corrective actions are being addressed via the corrective |
| action program. |
| |
| |
| Similar reviews of Unit 1 are ongoing. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
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