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Event Notification Report for November 15, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/12/1999 - 11/15/1999

                              ** EVENT NUMBERS **

36387  36428  36429  36430  36431  36432  36433  36434  36435  36436  36437  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36387       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 11/02/1999|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 19:06[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/02/1999|
+------------------------------------------------+EVENT TIME:        16:56[CST]|
| NRC NOTIFIED BY:  ERNEST MATHES                |LAST UPDATE DATE:  11/13/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MSIVs LEAKING ABOVE ACCEPTABLE LEAK RATE DURING AN LLRT -                  |
|                                                                              |
| During local leak rate testing with the plant in a refueling outage, the     |
| licensee discovered excess leakage past the 'A' main steam line inboard and  |
| outboard main steam isolation valves (#B21-F022A and #B21-F028A).  This      |
| condition exceeded the acceptable leak rate.  The licensee is determining    |
| corrective action.                                                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 0331 ON 11/13/99 BY ERNEST MATHES TO JOLLIFFE * * *          |
|                                                                              |
| During additional local leak rate testing, the licensee discovered gross     |
| leakage past the 'C' main steam line inboard and outboard main steam         |
| isolation valves (#B21-F022C and #B21-F028C).  This condition exceeded the   |
| acceptable leak rate.  The licensee plans to test the remaining MSIVs and    |
| rebuild the leaking valves prior to plant restart.                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R4DO Linda Smith.                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36428       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  EATON CUTLER-HAMMER                  |NOTIFICATION DATE: 11/12/1999|
|LICENSEE:  EATON CUTLER-HAMMER                  |NOTIFICATION TIME: 09:58[EST]|
|    CITY:                           REGION:     |EVENT DATE:        11/12/1999|
|  COUNTY:                            STATE:     |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  11/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAN HOLODY           R1      |
|                                                |CHARLES OGLE         R2      |
+------------------------------------------------+MICHAEL PARKER       R3      |
| NRC NOTIFIED BY:  PAT PATTERSON                |LINDA SMITH          R4      |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |VERN HODGE (by fax)  NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CDEG 21.21(c)(3)(i)      DEFECTS/NONCOMPLIANCE  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT -                                                      |
|                                                                              |
| Eaton Cutler-Hammer personnel identified a potential safety concern          |
| involving the potential for the malfunction of the Eaton Cutler-Hammer DS    |
| and DSL Class 1E circuit breakers due to the improper application of zinc    |
| chromate plating to hardened parts during breaker reconditioning.            |
|                                                                              |
| The failure of hardened parts to maintain their design integrity due to      |
| cracking and the potential for the total separation of pieces during a       |
| seismic event or normal operation and their subsequent infiltration of the   |
| breaker operating assembly could cause the failure of the breaker to perform |
| its design function.  In addition, mechanical interlocks may not perform as  |
| expected or the breaker may not be able to be charged depending on the       |
| actual failure which could occur.                                            |
|                                                                              |
| The installed base of the DS style circuit breakers is spread throughout the |
| nuclear industry.  However, it is unknown to Eaton Cutler-Hammer             |
| specifically which utilities may have had reconditioning performed on their  |
| breakers that included plating of parts.                                     |
|                                                                              |
| Eaton Cutler-Hammer recommends that a thorough inspection be conducted on    |
| all breakers which may have undergone previous reconditioning activities     |
| which included plating or replating of component parts.  Specific attention  |
| should be directed toward spiral pins, which are constructed of hardened     |
| spring steel.                                                                |
|                                                                              |
| See the Eaton Cutler-Hammer Part 21 report for additional details.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36429       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  EATON CUTLER-HAMMER                  |NOTIFICATION DATE: 11/12/1999|
|LICENSEE:  EATON CUTLER-HAMMER                  |NOTIFICATION TIME: 10:09[EST]|
|    CITY:                           REGION:     |EVENT DATE:        11/12/1999|
|  COUNTY:                            STATE:     |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  11/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAN HOLODY           R1      |
|                                                |CHARLES OGLE         R2      |
+------------------------------------------------+MICHAEL PARKER       R3      |
| NRC NOTIFIED BY:  PAT PATTERSON                |LINDA SMITH          R4      |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |VERN HODGE (by fax)  NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CDEG 21.21(c)(3)(i)      DEFECTS/NONCOMPLIANCE  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT -                                                      |
|                                                                              |
| Eaton Cutler-Hammer personnel identified a potential safety concern          |
| involving the potential for the malfunction of the Eaton Cutler-Hammer DS    |
| and DSL Class 1E circuit breakers due to the application of incorrect torque |
| values during breaker reconditioning.                                        |
|                                                                              |
| Previous industry DS Circuit Breaker Maintenance Guidance originally         |
| published by Westinghouse Nuclear Services Division in June 1993 and         |
| subsequently revised in March 1999 contained incorrect torque specifications |
| for DS circuit breaker arc chute mounting bolts.  Specifically, this         |
| guidance as originally published, was in error by a factor of at least 2     |
| (two) regarding the DS 206 and by a factor of at least 3 (three) for the DS  |
| 416 when compared to the torque values identified in the Manufacturing       |
| Instructions utilized by the OEM (Cutler-Hammer) factory during the          |
| manufacturing process.  The current revision information while being closer  |
| to the proper values is still incorrect.  Multiple instances of longitudinal |
| cracks have been observed in the mounting bolt block portion of the arc      |
| chute case.  In addition, the "O" rings used as a retaining or capture       |
| device for the arc chute mounting bolts have been damaged.  Pieces of the    |
| "O" rings have been found laying around the inside of circuit breakers.  The |
| failure of the arc chute case to maintain its design integrity due to        |
| cracking and the potential for the total separation of pieces during a       |
| seismic event or normal operation and their subsequent infiltration of the   |
| breaker operating assembly could cause the failure of the breaker to perform |
| its design function.  Likewise, "O" ring failure could result in the same    |
| final effect.                                                                |
|                                                                              |
| The installed base of the DS style circuit breakers is spread throughout the |
| nuclear industry.  However, it is unknown to Eaton Cutler-Hammer             |
| specifically which utilities may have incorporated this erroneous            |
| information into their maintenance programs.                                 |
|                                                                              |
| Eaton Cutler-Hammer recommends that a thorough inspection be conducted with  |
| the arc chutes properly torqued into place on the circuit breaker.  Please   |
| note that the cracks may not be visible once the arc chutes have been        |
| removed from the breaker.  A second inspection should be conducted of the    |
| "O" rings following removal of the arc chute from the breaker.               |
|                                                                              |
| See the Eaton Cutler-Hammer Part 21 report for additional details.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36430       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARIZONA RADIATION REG AGENCY         |NOTIFICATION DATE: 11/12/1999|
|LICENSEE:  COLORADO ENGINEERING & INSTRUMENTATIO|NOTIFICATION TIME: 13:22[EST]|
|    CITY:  PHOENIX                  REGION:  4  |EVENT DATE:        11/11/1999|
|  COUNTY:                            STATE:  AZ |EVENT TIME:        09:00[MST]|
|LICENSE#:  AZ 7-457              AGREEMENT:  Y  |LAST UPDATE DATE:  11/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |CATHERINE HANEY      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  AUBREY GODWIN (by fax)       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN MOISTURE/DENSITY GAUGE.                                               |
|                                                                              |
| On 11/11/99, the Arizona Radiation Regulatory Agency was notified by         |
| Colorado Engineering & Instrumentation Company that a Campbell Pacific MC    |
| series nuclear moisture/density gauge (Serial number MC-90204820) containing |
| 10 millicuries of Cs-137 and 50 millicuries of Am-241 was stolen from a work |
| site at 34th Street and Gelding in Phoenix, AZ.  The gauge was in its        |
| shipping container.  The Phoenix Police Department (Report number            |
| 1999-91880807) is investigating the theft.  The licensee is offering a       |
| $500.00 reward for the return of the gauge.  A press announcement of the     |
| reward will be made on 11/12/99.                                             |
|                                                                              |
| The Arizona Radiation Regulatory Agency is investigating the radiation       |
| safety issues.                                                               |
|                                                                              |
| The FBI (Phoenix), Mexico, and the States of California, Colorado, Nevada,   |
| Utah, and New Mexico are being notified of this incident.                    |
|                                                                              |
| (Call the NRC operations officer for contact information.)                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36431       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPT OF HLTH BUR OF RAD CNTL   |NOTIFICATION DATE: 11/12/1999|
|LICENSEE:  PRICE CONSTRUCTION                   |NOTIFICATION TIME: 17:52[EST]|
|    CITY:  LAREDO                   REGION:  4  |EVENT DATE:        11/11/1999|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|
|LICENSE#:  TX L05205             AGREEMENT:  Y  |LAST UPDATE DATE:  11/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS                |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER SOIL GAUGE STOLEN                                                    |
|                                                                              |
| ON 11/11/99, A TROXLER MODEL-3430 SOIL GAUGE WAS STOLEN FROM PRICE           |
| CONSTRUCTION AT A CONSTRUCTION SITE IN LAREDO, TX.  THE GAUGE CONTAINED 8    |
| MILLICURIES OF Cs-137 AND 40 MILLICURIES OF Am-241.  THE GAUGE WAS CHAINED   |
| AND LOCKED IN THE BACK OF A PICKUP TRUCK PARKED BEHIND A CONSTRUCTION ROLLER |
| AT THE CONSTRUCTION SITE.                                                    |
|                                                                              |
| THE LICENSEE REPORTED THE THEFT TO THE LOCAL POLICE DEPARTMENT.  THE         |
| LICENSEE NOTIFIED THE TEXAS DEPARTMENT OF HEALTH BUREAU OF RADIATION CONTROL |
| (FILE #I-7539) ON 11/12/99.                                                  |
|                                                                              |
| (CALL THE NRC OPERATIONS OFFICER FOR CONTACT INFORMATION.)                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36432       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 11/12/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 18:34[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        11/12/1999|
+------------------------------------------------+EVENT TIME:        10:08[EST]|
| NRC NOTIFIED BY:  MILLER                       |LAST UPDATE DATE:  11/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH SAFETY PARAMETER DISPLAY SYSTEMS/EMERGENCY RESPONSE INFORMATION SYSTEMS |
| (SPDS/ERIS) WERE OUT OF SERVICE FOR LONGER THAN 8 HOURS.                     |
|                                                                              |
| At 1008 on 11/12/99, both SPDS/ERIS systems failed.  Maintenance activities  |
| were ongoing at the time of failure.  In accordance with site procedures,    |
| SPDS/ERIS out of service for longer than 8 hours constitutes a loss of       |
| emergency response capability.  Efforts to restore both SPDS/ERIS systems to |
| service are in progress.                                                     |
|                                                                              |
| This report is being made in accordance with 10 CFR 50.72(b)(I)(v), any      |
| event that results in a major loss of emergency assessment capability.       |
|                                                                              |
| At 1823, one of the SPDS/ERIS systems was returned to service.  The plant    |
| did not enter any LCO action statement.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36433       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 11/13/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 11:19[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/13/1999|
+------------------------------------------------+EVENT TIME:        09:45[EST]|
| NRC NOTIFIED BY:  HOPE CREEK                   |LAST UPDATE DATE:  11/13/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - EMERGENCY RESPONSE DATA SYSTEM INOPERABLE FOR LONGER THAN 1 HOUR -         |
|                                                                              |
| DURING TESTING OF THE SAFETY PARAMETER DISPLAY SYSTEM, THE LICENSEE          |
| DISCOVERED THAT THE EMERGENCY RESPONSE DATA SYSTEM WAS INOPERABLE FOR LONGER |
| THAN 1 HOUR.                                                                 |
|                                                                              |
| THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Research Reactor                                 |Event Number:   36434       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: UNIV OF MICHIGAN                     |NOTIFICATION DATE: 11/13/1999|
|   RXTYPE: 2000 KW POOL                         |NOTIFICATION TIME: 13:01[EST]|
| COMMENTS:                                      |EVENT DATE:        11/13/1999|
|                                                |EVENT TIME:             [EST]|
|                                                |LAST UPDATE DATE:  11/13/1999|
|    CITY:  ANN ARBOR                REGION:  3  +-----------------------------+
|  COUNTY:  WASHTENAW                 STATE:  MI |PERSON          ORGANIZATION |
|LICENSE#:  R-28                  AGREEMENT:  N  |MICHAEL PARKER       R3      |
|  DOCKET:  05000002                             |LEDYARD (TAD) MARSH  NRR     |
+------------------------------------------------+TED MICHAELS         PM      |
| NRC NOTIFIED BY:  BECKER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REPORTABLE OCCURRENCE NO. 21 - REACTOR OPERATION IN VIOLATION OF TECHNICAL   |
| SPECIFICATION 3.5, AIRBORNE EFFLUENTS                                        |
|                                                                              |
| This is a preliminary report to inform the Commission of a violation of      |
| Technical Specifications 3.5.2.a and 3.5.2.b due to improper retest of the   |
| Radiation Recorder.  Due to an improper range setting, the Mobile Air        |
| Particulate monitors (MAP) provided incorrect lower readings of Airborne     |
| Effluent Concentration (AEC) for approximately 1 week.                       |
|                                                                              |
| On 11/05/99, the Radiation Recorder was retested following repairs.  The     |
| retest consisted of a channel check of the Bridge Radiation Recorder and     |
| verification of signals present on the remaining 9 channels.                 |
|                                                                              |
| On 11/08/99, the reactor was placed into operation to perform core reloading |
| activities.                                                                  |
|                                                                              |
| On 11/09/99, the reactor was placed into operation to perform the remaining  |
| portions of the core reloading and remained in operation at zero power.  At  |
| 1840, a reactor startup to 20 kW was performed for rod testing followed by   |
| continued operation at 2 MW.                                                 |
|                                                                              |
| On 11/11/99 at 1037, the health physics staff reported that during the       |
| weekly checks of the MAPs, the indication in the control room was 25 - 30%   |
| of the locally indicated count rates.  A review by the Assistant Manager for |
| Operations and the Shift Supervisor concluded that the MAPs were operational |
| and that 24 hours were allowed for review of the operability determination.  |
|                                                                              |
| On 11/12/99 at 0738, the Reactor Manager was notified of the discrepancy     |
| between the local and control room readings for the MAPs and, at 0900,       |
| ordered a reactor shutdown.  A review board reversed the operability         |
| determination and determined that this incident is reportable as per         |
| Technical Specification 6.6.2.a.                                             |
|                                                                              |
| Safety Implications:  It has been determined that the pool floor MAP was     |
| indicating one half the actual reading and that the stack MAP was indicating |
| one fifth the actual reading.  In this condition, the AEC necessary to       |
| exceed the alarm setpoint had been increased by a factor of two and five,    |
| respectfully.  These decreased indications and increased alarm set points    |
| would have still allowed for the MAPs to notify the operator upon release of |
| a significant quantity of particulate radioactivity which would have         |
| threatened to increase the yearly averaged AEC.  The area radiation          |
| monitoring system and gaseous activity detectors would have also provided    |
| the operators an indication of a significant release.  A review of the count |
| rates recorded showed that, during this period, the effluent from the        |
| facility did not exceed the normal particulate release of less than 1% of    |
| the AEC specified in 10 CFR Part 20.                                         |
|                                                                              |
| Corrective Action:  The Radiation Recorder was repaired and fully channel    |
| tested or channel checked.  Review of this event is ongoing and will include |
| Reportable Occurrence No. 19, "Reactor Operation with In-Operable Alarm      |
| Circuit on the Bridge Radiation Monitor."  Further corrective actions will   |
| be presented in the required followup report.  Analysis of the isokinetic    |
| sampling locations is in progress.                                           |
|                                                                              |
| The licensee considers this event to be significant due to its similarity    |
| with Reportable Occurrence No 19.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36435       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 11/13/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 15:01[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/13/1999|
+------------------------------------------------+EVENT TIME:        10:55[EST]|
| NRC NOTIFIED BY:  BRUCK                        |LAST UPDATE DATE:  11/13/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |LEDYARD (TAD) MARSH  NRR     |
|NINF                     INFORMATION ONLY       |DAVIDSON             IAT     |
|                                                |ROSANO               IAT     |
|                                                |GAGNER               PAO     |
|                                                |JOSEPH GIITTER       IRO     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TWO INJURED PERSONNEL TRANSPORTED TO THE LOCAL HOSPITAL WITH GUNSHOT WOUNDS  |
|                                                                              |
| At 1055 on 11/13/99, the Shift Manager requested an off-site ambulance to    |
| transport two people from the Cook Plant indoor rifle range to the Lakeland  |
| Hospital.  Local law enforcement personnel were using the Cook Plant indoor  |
| rifle range when a weapon inadvertently discharged.  The bullet ricocheted   |
| off the concrete floor striking one person in the lower leg.  A second       |
| person was also hit in the leg by either a piece of the bullet or some       |
| concrete debris.  Responding Emergency Medical Technicians reported that the |
| injuries were not life threatening and that both officers were in good       |
| spirits.                                                                     |
|                                                                              |
| The rifle range is located on Cook Plant controlled property, outside the    |
| restricted area.  The personnel involved, Benton Township Police Officers,   |
| are not employees or contractors at the Cook Plant and do not have           |
| unrestricted access.  Michigan State Police are investigating this           |
| accidental shooting.                                                         |
|                                                                              |
| The Resident Inspector was notified.  The licensee does not plan on a press  |
| release at this time.                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36436       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 11/13/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 15:39[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/13/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:45[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/13/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MICHAEL PARKER       R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  SISLER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 4-HOUR 91-01 BULLETIN RESPONSE - VACUUM SWEEPER FIRE/LOSS OF ONE CONTROL     |
| (GEOMETRY)                                                                   |
|                                                                              |
| At 1110 hours on 11-13-99, Emergency Forces responded to report of a vacuum  |
| sweeper fire in X-326 Process Building.  The Fire Department reported light  |
| smoke in the area.  Dry extinguishing agent was used to put out a smoldering |
| fire.  The smoldering fire was verified extinguished at 1124 hours.  There   |
| was no activation of any safety system during this response.  All air        |
| samples were less than detection.                                            |
|                                                                              |
| At 1145 hours, during the air quality and radiological assessment, it was    |
| reported to the incident Commander that a GP container failed on a favorable |
| Geometry Vacuum Cleaner.  This constituted a loss of one control (geometry)  |
| of NCSA PLANT012.A01.  Interaction (spacing) was maintained throughout this  |
| event.                                                                       |
|                                                                              |
| Initial assessment of the GP container attributes the failure to a chemical  |
| reaction that occurred inside the container.  All maintenance and cleanup    |
| activities utilizing Favorable Geometry Vacuum Cleaners in X-326 Side Purge  |
| have been stopped pending further evaluation.                                |
|                                                                              |
| 1)  Safety Significance of Events:                                           |
|                                                                              |
| The safety significance of this event is low.  The GP container is a         |
| favorable geometry container made of polyethylene.  This container was less  |
| than 1/2 full on a favorable geometry vacuum cleaner.  The nominal           |
| enrichment of the Side Purge piping is less than 10%, and the maximum        |
| credible enrichment is 40% based on historical operation.  The material in   |
| the container reacted with moisture in the air.  This reaction generated     |
| heat which melted the container and caused the container to break into two   |
| pieces.  The spilling of a full GP container on to a concrete floor          |
| reflected by a sprinkler discharge was analyzed by NCSE-PLANT 006.E03 and    |
| found to be subcritical for up to 80% enriched optimally moderated           |
| material.                                                                    |
|                                                                              |
| 2)  Potential Criticality Pathways Involved (Brief scenario(s) of how        |
| criticality could occur):                                                    |
|                                                                              |
| The potential pathway to criticality is that a full container is spilled,    |
| and then another container or piece of equipment is brought within 2 feet of |
| the spill.                                                                   |
|                                                                              |
| 3)  Controlled Parameters (Mass, Moderation, Geometry, Concentration,        |
| Etc.):                                                                       |
|                                                                              |
| The controlled parameters for this event are geometry and interaction.       |
|                                                                              |
| 4)  Estimated Amount, Enrichment, Form of Licensed Material (include process |
| limit and % worst case of critical mass):                                    |
|                                                                              |
| The estimated amount of material is unknown, but the container was known to  |
| be less then 1/2 full. The GP container dimensions are nominally 5 inches    |
| inside diameter and 24 inches tall.  The nominal enrichment of the Side      |
| Purge piping is less than 10%, and the maximum credible enrichment is 40%    |
| based on historical operation.                                               |
|                                                                              |
| 5)  Nuclear Criticality Safety Control(s) or Control System(s) and           |
| Description of Failures or Deficiencies:                                     |
|                                                                              |
| The material being vacuumed generated heat which melted the GP container     |
| causing a failure of the geometry control spilling the fissile material on   |
| to the floor.  A spill from a full container has been shown by calculations  |
| to be subcritical.  The present configuration is a slab with no material     |
| greater than an inch in depth.                                               |
|                                                                              |
| The NRC resident Inspector was notified.  The Department of Energy           |
| Representative will be notified.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36437       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WAUPACA FOUNDRY                      |NOTIFICATION DATE: 11/13/1999|
|LICENSEE:  WAUPACA FOUNDRY                      |NOTIFICATION TIME: 18:27[EST]|
|    CITY:  TELL CITY                REGION:  3  |EVENT DATE:        11/13/1999|
|  COUNTY:                            STATE:  IN |EVENT TIME:        15:30[CST]|
|LICENSE#:  48-15031-01           AGREEMENT:  N  |LAST UPDATE DATE:  11/13/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL PARKER       R3      |
|                                                |ROBERT PIERSON       NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  GREUBEL                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NDAM                     DAMAGED GAUGE/DEVICE   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| TWO INDUSTRIAL GAUGES CONTAINING Cs -137 WERE OVERHEATED AT A FOUNDRY.       |
|                                                                              |
| THE WAUPACA FOUNDRY REPORTED THAT TWO TN TECHNOLOGIES MODEL-5200 DEVICES     |
| CONTAINING 100 MILLICURIES OF Cs -137 PER DEVICE WERE OVERHEATED AT A        |
| FOUNDRY.  THESE DEVICES WERE MOUNTED 10' APART ABOVE ONE ANOTHER ON THE SIDE |
| OF A CUPOLA (A TALL SILO TYPE TANK WHICH IS USED TO MELT IRON).  THE CAUSE   |
| OF THE OVERHEATING OF THESE TWO GAUGES WAS CAUSED WHEN THE IGNITION SOURCE   |
| FOR THE CUPOLA WAS INADVERTENTLY IGNITED WITHOUT COOLING IN PLACE  FOR 3.5   |
| HOURS.  THE CAUSE OF THIS COULD POSSIBLY BE DUE TO PERSONNEL ERROR, BUT THEY |
| ARE STILL INVESTIGATING.  THERE IS NO APPARENT DAMAGE TO THE SOURCE          |
| CONTAINERS, BUT A SURVEYED @ 15' MEASURED 3.5 mR WHEN THE NORMAL READING IS  |
| APPROXIMATELY 0.2 mR.  THEY HAVE ISOLATED THE AREA AND HAVE CONTACTED THE    |
| MANUFACTURER WHO IS SENDING A TEAM TO THE SITE.                              |
|                                                                              |
| (CALL THE NRC OPERATIONS OFFICER FOR CONTACT INFORMATION.)                   |
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