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Event Notification Report for October 9, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/05/2001 - 10/09/2001

                              ** EVENT NUMBERS **

37596  38352  38353  38355  38356  38357  38358  38359  38360  38361  38362 
38363  38364  38365  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37596       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 18:02[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        17:15[EST]|
| NRC NOTIFIED BY:  DAVID DVORAK                 |LAST UPDATE DATE:  10/05/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|--APR50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|KSNM 70.52(a)            LOSS OF SNM/CRIT       |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LOCATION OF 2 FUEL PINS IN THE SPENT FUEL POOL IS UNKNOWN                |
|                                                                              |
| "As part of the ongoing decommissioning of Millstone Unit 1, a detailed      |
| documentation of the fuel currently in the Unit 1 spent fuel pool is         |
| underway. A detailed verification of spent fuel pool content records was     |
| part of this effort. During this process, workers identified a discrepancy   |
| in the paperwork relating to the location of two spent fuel pins that were   |
| removed from a fuel assembly in October 1972. A search is underway; however, |
| these fuel pins have not yet been located among the 2,884 fuel assemblies    |
| containing more than 140,000 fuel pins currently in the spent fuel pool. In  |
| addition, workers are also searching pertinent records.                      |
|                                                                              |
| "Due to the radiation levels of the fuel pins, if they were removed from the |
| spent fuel pool, the use of a shielded cask would have been required and the |
| shipment could have only been made to a licensed facility. Any other         |
| movement of these pins from the site would have been immediately detected by |
| the site radiation monitoring system. Therefore, there is a high degree of   |
| confidence that these pins are not in an unrestricted area and are under the |
| control of a licensed facility; either here in the spent fuel pool or        |
| possibly at a licensed radioactive waste disposal site. As a result, we are  |
| also confident that no overexposure of workers or members of the public has  |
| resulted. An independent team with relevant expertise is on-site to assist   |
| in an ongoing investigation to determine the location of the 2 fuel pins."   |
|                                                                              |
| The licensee notified NRC Region 1 (Todd Jackson) and the state of           |
| Connecticut.  The licensee intends notifying the NRC Resident Inspector.     |
|                                                                              |
| * * * UPDATE 1031EDT ON 10/5/01 FROM R. MALONEY TO S. SANDIN * * *           |
|                                                                              |
| The licensee is updating this report as follows to include the results of    |
| their investigation:                                                         |
|                                                                              |
| "DETAIL:                                                                     |
|                                                                              |
| "On October 1, 2001, Northeast Utilities provided its final report on the    |
| Millstone Unit No. 1 fuel rod accountability project to DNC (Dominion        |
| Nuclear Connecticut). This project was undertaken after it was determined    |
| that 2 fuel pins from a Millstone Unit No. 1 spent fuel assembly could not   |
| be accounted for. The NU project team conducted extensive inspections of the |
| Millstone Unit No. 1 spent fuel pool as well as comprehensive reviews of     |
| material accountability and waste shipment records and interviews of         |
| personnel historically involved with these activities. On the basis of this  |
| report, DNC concludes it is unlikely that the pins are in the Millstone Unit |
| No. 1 fuel pool. The investigation into the disposition of the pins found no |
| evidence to indicate that the pins were diverted and concluded that the pins |
| were most likely intermingled with other contaminated material removed from  |
| the Unit No. 1 spent fuel pool and shipped to a licensed low level waste     |
| repository. The report concludes, based on a study performed by a reputable  |
| expert, that the health and safety of the public has not been adversely      |
| impacted by this condition.                                                  |
|                                                                              |
| "This condition is reportable under 10CFR70.52(a) as a loss of special       |
| nuclear material.                                                            |
|                                                                              |
| "ACTIONS TAKEN:                                                              |
|                                                                              |
| "A team of DNC personnel has reviewed the report and interviewed members of  |
| the NU project team to obtain clarifications and additional information. A   |
| separate root cause is being prepared by NU for this event.                  |
|                                                                              |
| "RECOMMENDED ACTIONS:                                                        |
|                                                                              |
| "Incorporate into the MP1 decommissioning plan, as necessary, any DNC        |
| recommendations for additional future spent fuel pool inspections.           |
|                                                                              |
| "ADDITIONAL INFORMATION:                                                     |
|                                                                              |
| "Dominion Nuclear Connecticut (the licensee) will be delivering copies of    |
| the final report to NRC Headquarters and Region I offices for placement on   |
| the docket today (10/05/01)."                                                |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Conte), NRR EO (Tappert), NMSS EO (Brown), IRO    |
| (Wessman), NRR IAT (Skelton), NMSS IAT (Weber), NMSS (Essig), Region 1       |
| (Pangburn), OPA (Jasinski), and Liaison Team (Stauss).                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38352       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 10/05/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 04:30[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/05/2001|
+------------------------------------------------+EVENT TIME:        00:26[EDT]|
| NRC NOTIFIED BY:  J. A. WITTER                 |LAST UPDATE DATE:  10/05/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO TWO TRAINS OF SERVICE WATER  DECLARED  |
| INOPERABLE                                                                   |
|                                                                              |
| "At 0026 hrs on October 5, 2001, Beaver Valley Power Station Unit 2          |
| experienced a trip of the 'A' Train Service Water (SWS) Pump. 2SWS-P21 C was |
| operating on the 'A' SWS header when the pump tripped on Motor Ground Over   |
| Current. Both A and B Train Emergency Service Water Pumps (SWE) auto started |
| as designed and Service Water header pressure returned to normal values. Due |
| to a piping class break, safety/non-safety, between the SWS and SWE systems, |
| the unit entered Technical Specification 3.0.3 due to two trains of Service  |
| Water being Inoperable. The unit entered and completed the Abnormal          |
| Operating Procedure for Loss of Service Water, and the Bravo Train of        |
| Service Water was restored Operable when 2SWE-P21 B was secured and isolated |
| from the 'B' SWS header. 25W5-P21 B continued to operate normally during     |
| this event. Technical Specification 3.0.3 was exited at 0037 hrs. The plant  |
| is currently stable and operating at 100% power. Technical Specification     |
| 3.7.4.1 for Service Water (72-hour action) is applicable, as the only        |
| operating pump on the 'A' SWS header is 2SWE-P21A. The Alpha Service Water   |
| Pump, 2SWS-P21 A is unavailable due to Intake Structure Bay cleaning.        |
| Currently efforts are under way to recover the Intake Bay and restore        |
| 2SWS-P21A Operable. It is expected that both trains of Service Water will be |
| Operable within 12 hours. The Non Safety Related Chiller units tripped due   |
| to the SWS low pressure conditions, and were recovered shortly there after.  |
| No additional failures or equipment challenges occurred as a result of this  |
| event."                                                                      |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38353       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ABB INC.                             |NOTIFICATION DATE: 10/05/2001|
|LICENSEE:  ABB INC.                             |NOTIFICATION TIME: 14:26[EDT]|
|    CITY:                           REGION:     |EVENT DATE:        10/05/2001|
|  COUNTY:                            STATE:     |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |VERN HODGE (FAX)     NRR     |
|                                                |RICHARD CONTE        R1      |
+------------------------------------------------+FRANK JAPE           R2      |
| NRC NOTIFIED BY:  RUSS GONNAM                  |DAVID HILLS          R3      |
|  HQ OPS OFFICER:  FANGIE JONES                 |CLAUDE JOHNSON       R4      |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT CONCERNING A CLASS 1E RELAY                            |
|                                                                              |
| The following is the faxed report:                                           |
|                                                                              |
| Subject:  Initial Notification of Potential Defect per 10 CFR Part 21 Type   |
| CVE/CVE-1 Relays                                                             |
|                                                                              |
| Provided By:  ABB Inc., Substation Automation & Protection Division          |
|                                                                              |
| This letter is the initial notification of a deviation concerning our Class  |
| 1E relay type CVE/CVE-1. The deviation concerns the difference between the   |
| original zero period acceleration value and the recent zero period           |
| acceleration value as reported to us by an independent dedicating entity.    |
|                                                                              |
| Details will be provided in our written notification forthcoming within the  |
| next thirty days.                                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   38355       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  AVERA McKENNAN HOSPITAL              |NOTIFICATION DATE: 10/05/2001|
|LICENSEE:  AVERA McKENNAN HOSPITAL              |NOTIFICATION TIME: 16:50[EDT]|
|    CITY:  FREEMAN                  REGION:  4  |EVENT DATE:        10/04/2001|
|  COUNTY:                            STATE:  SD |EVENT TIME:             [MDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLAUDE JOHNSON       R4      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARK EWING                   |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|IBAC 30.50(b)(1)         UNPLANNED CONTAMINATION|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SPILL OF TECHNETIUM IN PUBLIC AREA                                           |
|                                                                              |
| The mobile lab of Avera McKennan Hospital was on site at the Freeman         |
| Hospital, Freeman, S.D. when a cracked vial containing 250 mCi of Technetium |
| leaked on to the floor of the kitchen.  The area was secured and the only    |
| exposure/contamination was the shoes of the medical technician transporting  |
| the vial.  A containment area was established and gross cleanup was          |
| completed on 10/4/01.  The area was checked again this morning and further   |
| evaluation will be taken tomorrow, 10/6/01, after 8:00 PM, which will be     |
| greater than ten half-lives.                                                 |
|                                                                              |
| NRC Region 4 (Bob Brown) has been notified by the hospital chief technician. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38356       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 10/05/2001|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 17:11[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/05/2001|
+------------------------------------------------+EVENT TIME:             [CDT]|
| NRC NOTIFIED BY:  ED TIEDEMANN                 |LAST UPDATE DATE:  10/05/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM |
| POWER LEVEL VIOLATION                                                        |
|                                                                              |
| "This report is being made in accordance with Clinton Power Station Unit #1  |
| Operating License Condition #2.G as a  potential violation of License        |
| Condition #2.C(1), Maximum Power Level.                                      |
|                                                                              |
| "GE Report titled 'Impact of Steam Carryover Fraction on Process Computer    |
| Heat Balance Calculations', September 2001, documents a non-conservative     |
| assumption for the moisture carryover fraction used in the calculation of    |
| core thermal power. The assumed carryover fraction of 0.1 % was discovered   |
| to be potentially closer to zero and therefore non-conservative in later     |
| model GE BWRs.                                                               |
|                                                                              |
| "A review of Clinton Power Station Unit #1 moisture carryover test data      |
| performed on May 21 2001 found a moisture carryover value of 0.0046% and on  |
| October 4, 2001 found a moisture carryover value of 0.0020% inducing an      |
| estimated bias of approximately 2.4 MWth. Based on this potential            |
| non-conservatism on Unit #1 indicated Maximum Power Level shift average is   |
| being administratively controlled 4 MWth below the licensed power level of   |
| 2894 MWth.                                                                   |
|                                                                              |
| "Exelon staff is continuing to evaluate the effect of the moisture carryover |
| term in the heat balance calculation. The NRC resident has been notified."   |
|                                                                              |
| (Refer to event numbers 38330, 38337, 38340, 38344, 38445, 38347, 38349, and |
| 38357 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Columbia   |
| Generating Station, Limerick 2, River Bend, and Limerick 1.)                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38357       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 10/05/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 17:10[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        10/05/2001|
+------------------------------------------------+EVENT TIME:        11:15[EDT]|
| NRC NOTIFIED BY:  PETER M. ORPHANOS            |LAST UPDATE DATE:  10/05/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM |
| POWER LEVEL VIOLATION                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee.   |
|                                                                              |
| "This report is being made in accordance with Limerick Generating Station    |
| Unit 1 Operating License Condition 2.F as a potential violation of License   |
| Condition 2.C(1), Maximum Power Level."                                      |
|                                                                              |
| "GE Report titled, 'Impact of Steam Carryover Fraction on Process Computer   |
| Heat Balance Calculations,' September 2001, documents a non-conservative     |
| assumption for the moisture carryover fraction used in the calculation of    |
| core thermal power.  The assumed carryover fraction of 0.1% was discovered   |
| to be potentially closer to zero and therefore non-conservative in later     |
| model GE BWRs."                                                              |
|                                                                              |
| "A review of Limerick Unit 1 moisture carryover test data performed in       |
| September of 1999 found a moisture carryover value of 0.1%.  However, it is  |
| believed that the results of the test may be more in line with the Limerick  |
| Unit 2 data of 0.0277%.  This results in an estimated bias of approximately  |
| 2.8 MWth Based on this potential non-conservatism on Unit 1, an input        |
| parameter of the Process Computer has been changed to eliminate this bias."  |
|                                                                              |
| 'Exelon staff is continuing to evaluate the effect of the moisture carryover |
| term in the heat balance calculation."                                       |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| (Refer to event numbers 38330, 38337, 38340, 38344, 38445, 38347, 38349, and |
| 38356 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Columbia   |
| Generating Station, Limerick 2, River Bend, and Clinton.)                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38358       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 10/05/2001|
|LICENSEE:  AMEC EARTH & ENVIRONMENT             |NOTIFICATION TIME: 17:31[EDT]|
|    CITY:  UNIVERSITY PLACE         REGION:  4  |EVENT DATE:        10/04/2001|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  WN-1093-1             AGREEMENT:  Y  |LAST UPDATE DATE:  10/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLAUDE JOHNSON       R4      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+JOHN DAVIDSON        IAT     |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE                                |
|                                                                              |
| The following is the faxed report:                                           |
|                                                                              |
| City and state: Spokane, WA                                                  |
| License number: WN-l093-1                                                    |
| Type of license: Portable Gauge                                              |
|                                                                              |
| Date of event: October 4, 2001                                               |
| Location of Event: University Place, WA                                      |
|                                                                              |
| ABSTRACT: A Troxler portable gauge was stolen from a pick-up parked at a     |
| residence.  An authorized user was returning home late from a job site and   |
| knowing he had to go back early the next morning requested permission from   |
| the licensee's Radiation Safety Officer to take the gauge home and secure it |
| there.  The authorized user's home was closer than the licensee's storage    |
| location.  Permission was given and the gauge, a Troxler model 3440, serial  |
| number 31199, was locked and chained in the bed of the pick-up.  The         |
| pick-up, which did not have a canopy, was parked in the residence's drive    |
| way on the evening of October 4.  The authorized user discovered early the   |
| next morning that the chain had been cut and the gauge stolen.  Neighbors    |
| reported hearing noises about 11:45 PM that night.   The theft was reported  |
| to the local police, the licensee's corporate RSO and to the Department.  A  |
| reward is being offered for the gauge which contains 10 millicuries of       |
| cesium 137 and 50 millicuries of americium 241/beryllium.                    |
|                                                                              |
| What is the notification or reporting criteria involved?  WAC 246-221-240    |
| (Reports of stolen, lost or missing radiation sources.)                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   38359       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  RESEARCH MEDICAL CENTER              |NOTIFICATION DATE: 10/05/2001|
|LICENSEE:  RESEARCH MEDICAL CENTER              |NOTIFICATION TIME: 17:34[EDT]|
|    CITY:  KANSAS CITY              REGION:  3  |EVENT DATE:        10/05/2001|
|  COUNTY:  JACKSON                   STATE:  MO |EVENT TIME:        10:30[CDT]|
|LICENSE#:  24-18625-01           AGREEMENT:  N  |LAST UPDATE DATE:  10/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID HILLS          R3      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  STEVEN SLACK                 |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION INVOLVING A MISSING IRIDIUM-192 SEED               |
|                                                                              |
| At 0830 CDT on 10/05/01, the licensee discovered that 1 of 71 iridium-192    |
| seeds was missing following a brachytherapy treatment involving both         |
| cesium-137 tubes and iridium-192 ribbons.  The licensee's investigation      |
| revealed that the missing iridium-192 seed remained inside the patient.  The |
| licensee determined that this event was reportable at 1030 CDT on 10/05/01.  |
|                                                                              |
| The patient was in surgery at the time of this event notification.  As a     |
| result, the total dose the patient has not yet been determined.  The missing |
| iridium-192 seed had an activity of 0.89 millicuries.                        |
|                                                                              |
| ***** UPDATE FROM STEVEN SLACK TO LEIGH TROCINE AT 1819 EDT ON 10/05/01      |
| *****                                                                        |
|                                                                              |
| The missing iridium-129 seed was successfully recovered at 1645 CDT on       |
| 10/05/01.                                                                    |
|                                                                              |
| The NRC operations officer notified the R3DO (David Hills) and NMSS EO       |
| (Patricia Holahan).                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38360       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 10/07/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 03:13[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/07/2001|
+------------------------------------------------+EVENT TIME:             [EDT]|
| NRC NOTIFIED BY:  RONALD GREEN                 |LAST UPDATE DATE:  10/07/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DURING TESTING                                           |
|                                                                              |
| "On 10/06/01, testing personnel and the Control Room crew were performing    |
| 1BVT-1 .1.7, 'Rod Position Indication System Calibration Verification' and   |
| 1BVT-1.1.1, 'Rod Drop Testing' in preparation for reactor startup after Unit |
| 1's 14th Refueling Outage. At 1959 hours, the Control Room operators         |
| observed indications of 2 dropped control rods (rod position indication      |
| reading zero steps and rod bottom lights on), and entered 1AOP-1.1.8         |
| (Abnormal Operating Procedure - Rod Inoperability). The Reactor Operator     |
| opened the reactor trip breakers in accordance with the Abnormal Operating   |
| Procedure and the Reactivity Management Plan that included reactivity limits |
| and recommended contingency actions. It was subsequently discovered that the |
| indications were caused by the test crew repositioning knife switches to     |
| place the rod drop computer in service. The action and resulting indications |
| were not communicated to the Control Room crew. This event is being reported |
| under 10CFR 50.72(b)(3)(iv)(A), as a Specified System Actuation (RPS),       |
| because a valid manual RPS signal (opening the reactor trip breakers from    |
| the Control Room) was initiated which was not part of the pre-planned        |
| testing in progress. All equipment functioned as expected, and no additional |
| failures or equipment challenges occurred as a result of this event. There   |
| were no radiological releases associated with this event."                   |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38361       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 10/07/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 06:11[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/07/2001|
+------------------------------------------------+EVENT TIME:        04:59[CDT]|
| NRC NOTIFIED BY:  JOHN WEEKLEY                 |LAST UPDATE DATE:  10/07/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLAUDE JOHNSON       R4      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 OPERATIONS CENTER WITHOUT ELECTRICAL POWER FOR SCHEDULED           |
| MAINTENANCE                                                                  |
|                                                                              |
| The licensee reported that the Emergency Operations Facility (EOF) will be   |
| without power for approximately eight hours so that preplanned maintenance   |
| can be performed. The NRC resident inspector has been informed.              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38362       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 10/07/2001|
|    UNIT:  [] [2] []                 STATE:  MI |NOTIFICATION TIME: 13:02[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/07/2001|
+------------------------------------------------+EVENT TIME:        09:50[EDT]|
| NRC NOTIFIED BY:  STEVE CHERBA                 |LAST UPDATE DATE:  10/07/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       8        Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR TRIP DURING PLANT STARTUP OPERATIONS                      |
|                                                                              |
| ". . . . This event occurred at 0950 hours this morning (10-7-01). Currently |
| the Unit is in Mode 3 with all systems normal. At the time of the trip the   |
| unit was at approximately 8 % power (by RCS AT indication, about 6 to 7 % on |
| Power Range Nuclear Instrumentation) in power ascension and was just         |
| preparing to roll the main turbine.                                          |
|                                                                              |
| "RCS Tavg was noted to decrease below the normal 547 F no-load post-trip    |
| value to about 535 F by the Reactor Operator monitoring the temperature. At |
| the time of the trip one main feedwater pump was supplying the Steam         |
| Generators (SG), with low-flow feedwater pre-heating in service. Main        |
| feedwater isolated on the trip with the SGs being supplied post trip by the  |
| motor driven Auxiliary Feedwater (AFW) Pumps. The RCS cooldown was           |
| attributed to the #4 SG AFW flow control valve not closing as expected on    |
| high flow thus allowing too much flow to #4 SG, as well as steam that was    |
| still being supplied to low flow feedwater preheating. Operator actions      |
| taken in response to the cooldown were to close the main steam stop valves,  |
| and review AFW valve positions so as to limit steam flow from, and feed flow |
| to, the SGs. These actions were completed by 0959 hours, and were sufficient |
| to maintain temperature control. RCS temperature shortly recovered to 547 F |
| at about 1032 hours, 10-7-01. No other significant abnormalities were noted, |
| pressurizer pressure decreased in response to the temperature transient, and |
| the subsequent RCS shrink caused RCS letdown to isolate on low pressurizer   |
| level. The plant is presently stable in Mode 3. No other RPS or SI setpoints |
| were exceeded due to the trip and subsequent temperature transient. All      |
| other systems and equipment functioned normally.                             |
|                                                                              |
| "The initiating RPS signal was a high Power Range Nuclear Instrument Rate    |
| Trip on 2 out of 4 channels. Cause of this rate trip is not definitively     |
| known at this time, rapid event teams to investigate and evaluate the trip   |
| have been initiated. Suspected cause is a Rod Control System problem."       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38363       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STERIGENICS                          |NOTIFICATION DATE: 10/07/2001|
|LICENSEE:  STERIGENICS                          |NOTIFICATION TIME: 17:38[EDT]|
|    CITY:  ROCKAWAY                 REGION:  1  |EVENT DATE:        10/06/2001|
|  COUNTY:  MORRIS                    STATE:  NJ |EVENT TIME:        10:15[EDT]|
|LICENSE#:  29-30308-01           AGREEMENT:  N  |LAST UPDATE DATE:  10/07/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLIFF ANDERSON/REG 1 IRC     |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+RICHARD WESSMAN      IRO     |
| NRC NOTIFIED BY:  STANLEY YAP                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|MAAA 36.83(a)(1)         UNSHIELD STUCK SOURCE  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COMMERCIAL IRRADIATOR FACILITY REPORT REGARDING A SOURCE HANG UP             |
|                                                                              |
| Sterigenics is a panoramic, wet-source storage, commercial, irradiator       |
| facility.  At approximately 2215 EDT on 10/07/01, a 2.6-megacurie cobalt-60  |
| source got stuck in the unshielded position.  The licensee attempted to lift |
| the source rack and had to release the ear out of the cylinder in the cell   |
| to free it.  The source rack was successfully returned it to its shielded    |
| position within approximately 1 hour.  There were no personnel radiation     |
| exposures or injuries as a result of this event, and there was no source     |
| leakage.                                                                     |
|                                                                              |
| The licensee is still investigating the cause of this event and has ceased   |
| operations until engineering personnel can complete their evaluation.        |
|                                                                              |
| (Call the NRC operations officer for a site contact telephone number and     |
| street address.)                                                             |
|                                                                              |
| (Refer to event #38342 for a similar event at Sterigenics on 10/07/01.)      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38364       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 10/08/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 08:33[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/08/2001|
+------------------------------------------------+EVENT TIME:        01:10[EDT]|
| NRC NOTIFIED BY:  CHRIS SERATA                 |LAST UPDATE DATE:  10/08/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT DECLARED INOPERABLE DURING SURVEILLANCE TESTING        |
|                                                                              |
| "During performance of the secondary containment drawdown test, reactor      |
| building vacuum fluctuated between 0.49 and 0.50 inches wg. The acceptance   |
| criterion for the test is greater than or equal to 0.50 inches wg vacuum.    |
| Secondary Containment was therefore declared inoperable at 01:10.            |
| Surveillance Requirement (SR) 4.6.5.1.c requires verification that the FRVS  |
| will draw down the secondary containment to greater than or equal to 0.25    |
| inches wg vacuum. The test acceptance criterion ensures that vacuum          |
| throughout the reactor building meets the SR acceptance criterion. Hope      |
| Creek entered Technical Specification action statement 3.6.5.1 .a which      |
| requires SECONDARY CONTAINMENT INTEGRITY to be restored within 4 hours or    |
| the plant to be in HOT SHUTDOWN within the next 12 hours.                    |
|                                                                              |
| "The FRVS reactor building pressure controller setpoint was found to be      |
| incorrectly set. The controller was returned to the required setpoint and    |
| reperformance of the test is in progress.                                    |
|                                                                              |
| "PSEG Nuclear is evaluating the test acceptance criterion and the            |
| instrumentation used for the test."                                          |
|                                                                              |
| The licensee will inform the Lower Alloways Creek Township and the NRC       |
| resident inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38365       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 10/08/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 17:48[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        10/08/2001|
+------------------------------------------------+EVENT TIME:        16:30[EDT]|
| NRC NOTIFIED BY:  RICKY RAWLS                  |LAST UPDATE DATE:  10/08/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON, REGION 2 IRC     |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A THROUGH-WALL LEAK AROUND ONE CONTROL ROD DRIVE MECHANISM      |
| NOZZLE (REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK)                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On October 1, 2001, following shutdown for a scheduled refueling outage,    |
| Crystal River Unit 3 (CR-3) performed a visual inspection of the Reactor     |
| Vessel (RV) Control Rod Drive Mechanism (CRDM) nozzles per NRC Bulletin      |
| 2001-01.  The inspection revealed evidence of boric acid buildup around one  |
| CRDM nozzle (#32).  No other CRDM nozzle showed similar boron buildup.       |
| After the RV head was removed and placed on the storage stand, additional    |
| inspections were performed.  At approximately 1610 on October 8, 2001,       |
| Ultrasonic Test (UT) revealed a through-wall indication.  This confirms that |
| the boron deposits around CRDM #32 indicate a Reactor Coolant System (RCS)   |
| pressure boundary leak.  This condition is consistent with industry          |
| experience with Primary Water Stress Corrosion Cracking (PWSCC) in similar   |
| components that have been evaluated as part of the NRC Generic Letter 97-01  |
| and NRC Bulletin 2001-01.  Additional nozzles are being examined by UT in    |
| accordance with CR-3's response to NRC Bulletin 2001-01.  This condition did |
| not pose a significant safety risk during plant operation.  CR-3 plans to    |
| perform repairs during the current refueling outage.  Since the condition    |
| resulted in leakage through the RCS pressure boundary, it is being reported  |
| as a non-emergency [8-hour] report in accordance with 10 CFR                 |
| 50.72(b)(3)(ii)(A) and 50.73(A)(2)(II)."                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+