Event Notification Report for December 3, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/02/1999 - 12/03/1999
** EVENT NUMBERS **
36421 36478 36479 36480 36481 36482 36483
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36421 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 11/10/1999|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 19:09[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/10/1999|
+------------------------------------------------+EVENT TIME: 18:15[EST]|
| NRC NOTIFIED BY: DAN HARDIN |LAST UPDATE DATE: 12/02/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES OGLE R2 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| SECURITY REPORT |
| |
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE CORRECTIVE ACTIONS |
| TAKEN UPON DISCOVERY. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
| SEE THE HOO LOG FOR ADDITIONAL DETAILS. |
| |
| * * * RETRACTED AT 1655 EST ON 12/2/1999 BY CHARLES ELBERFELT TO FANGIE |
| JONES * * * |
| |
| Upon further investigation a determination was made that access was not |
| granted inappropriately, thus the licensee is retracting this event. The |
| licensee informed the NRC Resident Inspector and the NRC Headquarters |
| Operations Officer informed the R2DO (Kenneth Barr). |
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|General Information or Other |Event Number: 36478 |
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| REP ORG: FLORIDA DEPARTMENT OF HEALTH |NOTIFICATION DATE: 12/01/1999|
|LICENSEE: PROFESSIONAL ENGINEERING & INSPECTION|NOTIFICATION TIME: 12:50[EST]|
| CITY: JUPITER REGION: 2 |EVENT DATE: 12/01/1999|
| COUNTY: MARTIN STATE: FL |EVENT TIME: [EST]|
|LICENSE#: 2940-1 AGREEMENT: Y |LAST UPDATE DATE: 12/02/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KENNETH BARR R2 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLES ADAMS (fax) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT - LOST TROXLER GAUGE |
| |
| A Troxler Model # 3411B moisture/density gauge (serial no. 13472) was lost |
| from the back of a pickup truck. The gauge contains one 8 mCi Cs-137 source |
| and one 40 mCi Am-241/Be source. The following narrative was submitted via |
| facsimile: |
| |
| "The gauge was in the back of a pickup proceeding down Highway A1A. The |
| tailgate came open and the bed liner and gauge fell out of the vehicle. A |
| county employee working nearby witnessed the incident. He saw a vehicle stop |
| and pick up the bed liner and another vehicle stop and pick up the gauge. |
| The Martin County Sheriff's office is working the case. Martin County |
| Emergency Management and the owner are issuing a joint press release. |
| Florida Bureau of Radiation Control is also investigating the incident." |
| |
| * * * UPDATE ON 12/02/99 AT 0808ET BY JERRY EAKINS TAKEN BY MACKINNON * * * |
| |
| Jerry Eakins of the Florida Bureau of Radiation Control reported that the |
| Troxler gauge was recovered by the Licensee this morning at 0700ET. The |
| Troxler gauge is not damaged and the licensee will perform a leak test of |
| the gauge. The State of Florida case number for this event is Fl 99-0162. |
| |
| |
| NRC R2DO (Ken Barr) and NMSS EO (Scott Moore) notified. |
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|General Information or Other |Event Number: 36479 |
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| REP ORG: ABB POWER T&D COMPANY |NOTIFICATION DATE: 12/02/1999|
|LICENSEE: ABB POWER T&D COMPANY |NOTIFICATION TIME: 10:33[EST]|
| CITY: Florence REGION: 2 |EVENT DATE: 12/02/1999|
| COUNTY: STATE: SC |EVENT TIME: 10:33[EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 12/02/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KENNETH BARR R2 |
| |STEVEN DENNIS R1 |
+------------------------------------------------+GEOFFREY WRIGHT R3 |
| NRC NOTIFIED BY: H. SCOTT BRIDGES |PHIL HARRELL R4 |
| HQ OPS OFFICER: JOHN MacKINNON |VERN HODGE NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TRIP ROLLER - HK CIRCUIT BREAKER, ABB PART # 180097A00 |
| |
| During the 4kV ABB Type HK breaker refurbishment at the DC Cook Plant on |
| October 21, 1999, newly installed trip rollers, ABB Part Number 180097A00, |
| were determined to be below the minimum hardness specification, Rockwell C |
| 50-55. One roller was observed to be "scoring" after 200 cycles. This |
| roller was one of 130 rollers sent to DC Cook through a purchase order from |
| ABB Service Company in Cleveland, Ohio. A sample of rollers indicated that |
| all were below the hardness specification. After communicating this to ABB |
| Service and the ABB Florence facility, the roller with the lowest measured |
| hardness, Rockwell C13, was returned for evaluation at the ABB-Florence |
| factory. |
| |
| ABB Power T&D Company received notification from ABB Service Company, The |
| Woodlands, TX, of a trip roller, 180097A00, problem occurring in November |
| 11, 1998, purchased under ABB Service Company Purchase Order Number |
| 27-04459-P4031, ABB Power T&D Company Order Number CCN0449. The initial |
| investigation points to a roller that has not been heat-treated to its |
| hardness specification as well. This information will serve to address the |
| trip roller issue here as well. |
| |
| An HK Circuit Breaker that contains trip rollers that are not properly |
| hardened may fail to trip at some point during the life of the breaker. ABB |
| Power T&D Company testing indicates that a very soft trip roller measuring |
| Rockwell C13 was able to operate 4000 operations before minimum trip voltage |
| failed to operate the circuit breaker. |
| |
| The information of the defect of the trip roller was obtained on October 21, |
| 1999 |
| |
| This information affects trip rollers that were shipped as Component Orders |
| or as part of Complete Circuit Breakers from October 30, 1995 through June |
| 1999. |
| |
| The hardness critical characteristic was added to the QC Record Card in June |
| 1999 for the trip roller, 180097A00. |
| |
| ABB will notify all customers who purchased this product. |
| |
| Replacement trip rollers may be obtained from ABB Power T&D Company, |
| Sanford, FL, by contacting the Components Group. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Research Reactor |Event Number: 36480 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: UNIV OF TEXAS |NOTIFICATION DATE: 12/02/1999|
| RXTYPE: 1100 KW TRIGA MARK II |NOTIFICATION TIME: 17:26[EST]|
| COMMENTS: |EVENT DATE: 12/01/1999|
| |EVENT TIME: 10:00[CST]|
| |LAST UPDATE DATE: 12/02/1999|
| CITY: AUSTIN REGION: 4 +-----------------------------+
| COUNTY: TRAVIS STATE: TX |PERSON ORGANIZATION |
|LICENSE#: R-129 AGREEMENT: Y |PHIL HARRELL R4 |
| DOCKET: 05000602 |WILLIAM BECKNER NRR |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: SEAN O'KELLY |ALEXANDER ADAMS NRR |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TECHNICAL SPECIFICATION VIOLATION DISCOVERED |
| |
| The licensee has determined that Tech Spec 3.4.2, which limits the amount of |
| explosive material in the reactor to less than 25 milligrams has been |
| exceeded. Following an investigation of bulging of the reactor reflector in |
| October this year it has been determined that an accumulation of hydrogen |
| and oxygen gas of approximately 5000 times the Tech Spec limit has |
| accumulated in the reflector. The reflector is graphite, contained an |
| aluminum can, doughnut shaped, that fits around the reactor. Apparently, a |
| pinhole sized leak allowed water from the reactor pool to seep into the |
| reflector can, which then underwent radiolytic decomposition filling the can |
| with hydrogen and oxygen gas. The reflector has been ultrasonically |
| examined to determine if it was full of water and it is not. |
| |
| The licensee has and is consulting experts concerning their plan to vent the |
| gasses out of the reflector under water in a slow and controlled manner. |
| The reactor is defueled and will remain so until this problem is corrected. |
| |
| The licensee notified the NRC Project Manager concerning this issue. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36481 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/02/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 17:47[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/02/1999|
+------------------------------------------------+EVENT TIME: 16:05[CST]|
| NRC NOTIFIED BY: RICK HUBBARD |LAST UPDATE DATE: 12/02/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PHIL HARRELL R4 |
|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
+------------------------------------------------------------------------------+
| CONTAINMENT SUMP LEVEL DETECTION DOES NOT MEET REQUIREMENT FOR RCS LEAK |
| DETECTION |
| |
| "While investigating concerns with the containment instrument tunnel sump |
| leak detection capabilities and satisfying the requirements for RCS leak |
| detection in the Improved Tech Specs (TS 3.4.15) an issue was identified |
| with the Normal Containment Sump Level Monitoring capability. From review |
| and investigation of this issue, it was identified that the current |
| calculation for the instrument tunnel sump leak rate would not always be |
| able to detect a 1 gpm leak in one hour to satisfy the Reg Guide 1.45 basis |
| for this Tech Spec. After even further review, it has been concluded that |
| the current calculation for the containment normal sumps is performed in a |
| similar manner. Thus, the containment normal sumps will not always provide |
| adequate leak detection to ensure that a 1 gpm RCS leak is detected in one |
| hour. |
| |
| "The Wolf Creek Updated FSAR states that one of the design bases of the |
| reactor coolant system leakage detection systems is to be capable of |
| detecting a 1 gallon per minute leak consistent with Regulatory Guide 1.45 |
| and 10 CFR 50, Appendix A, General Design Criteria 30. Regulatory Guide 1.45 |
| states that the systems must be capable of detecting a 1 gpm leak within 1 |
| hour. Since the Wolf Creek Containment Normal sump does not meet this design |
| basis, it is believed that the plant may be outside its design basis, in |
| accordance with the reporting criteria of 10 CFR 50.72(b)(1)(ii)." |
| |
| The fix is a software change to the Plant Computer and the licensee has it |
| and intends to have it in operation well within the 30 day shutdown |
| requirement of Tech Specs. |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36482 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 12/02/1999|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 18:11[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/02/1999|
+------------------------------------------------+EVENT TIME: 16:47[EST]|
| NRC NOTIFIED BY: JEFF MOSHER |LAST UPDATE DATE: 12/02/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KENNETH BARR R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 95 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP AFTER MAIN FEEDWATER PUMP TRIP ON LOW SUCTION PRESSURE |
| |
| The reactor was manually tripped (all rods fully inserted) after two of |
| three main feedwater pumps tripped due to low suction pressure. The low |
| suction pressure was due to a secondary system transient which caused the |
| loss of one of the high pressure heater drain pumps. The transient was from |
| feedwater heater level system. The exact cause is under investigation. |
| |
| All auxiliary feedwater pumps started, as designed, on low steam generator |
| level and the steam dumps opened to the condenser to remove excess heat. |
| The unit is stabilized in Mode 3. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36483 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/03/1999|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 00:09[EST]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/02/1999|
+------------------------------------------------+EVENT TIME: 22:25[EST]|
| NRC NOTIFIED BY: BREIDENBAUGH |LAST UPDATE DATE: 12/03/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEVEN DENNIS R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PERFORMANCE OF RHR LOGIC FUNCTIONAL TEST DEFEATS THE AUTOMATIC START OF ALL |
| FOUR RHR PUMPS |
| |
| A review of the Residual Heat Removal (RHR) logic system functional test |
| identified that during part of the performance of the test the automatic |
| start of all four RHR pumps was defeated. Manual initiation remained |
| available. This test was last performed on both Unit 2 and Unit 3 in 1997. |
| This report is being made due to the loss of the automatic initiation of the |
| Low Pressure Coolant Injection (LPCI) mode of RHR. This alone could have |
| prevented the fulfillment of a safety function. |
| |
| The NRC Resident Inspector will be notified of this event by the Licensee. |
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