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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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       |
+------------------------------------------------------------------------------+
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| 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                                   
+------------------------------------------------------------------------------+
| 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).                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36478       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36479       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.   |
+------------------------------------------------------------------------------+