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Event Notification Report for January 18, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/17/2002 - 01/18/2002

                              ** EVENT NUMBERS **

38518  38596  38618  38631  38633  38634  38635  38636  38637  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38518       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/26/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 13:37[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/26/2001|
+------------------------------------------------+EVENT TIME:        12:32[CST]|
| NRC NOTIFIED BY:  ROBERT ADAMS                 |LAST UPDATE DATE:  01/17/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE JORGENSEN      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  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERDS INOPERABLE DUE TO PLANNED OUTAGE OF THE PLANT PROCESS COMPUTER
SYSTEM   |
| (PPCS)                                                                       |
|                                                                              |
| AT 1232 CT, the Point Beach Nuclear Plant ERDS became inoperable as a result |
| of modifications to change out the plant process computer system (PPCS).     |
| This is a planned evolution.  ERDS will remain inoperable until              |
| approximately, December 18, 2001.                                            |
|                                                                              |
| This information was verbally provided to a representative of NRR during the |
| week of 10/15/2001.  The senior resident inspector has also been briefed on  |
| the modifications and schedule.  NMC to NRC letter (NRC 01-0080) dated       |
| 11/21/2001 stated we would be submitting this Non-Emergency report.          |
|                                                                              |
| ***** UPDATE FROM RICK ROBBINS TO LEIGH TROCINE AT 2006 EST ON 11/27/01      |
| *****                                                                        |
|                                                                              |
| The following additional information is a portion of a facsimile received    |
| from the licensee:                                                           |
|                                                                              |
| "As part of the PPCS modification, several inputs to the SPDS monitor were   |
| also made unavailable.  Any out-of-service indications on the SPDS can be    |
| obtained by control room control board indications."                         |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations center |
| notified the R3DO (Bruce Jorgensen).                                         |
|                                                                              |
| * * * UPDATE 1259EST ON 12/22/01 FROM RYAN RODE TO S. SANDIN * * *           |
|                                                                              |
| The licensee provided the following information as an update:                |
|                                                                              |
| "On 11/26/01 at 12:32, the PBNP ERDS and SPDS were declared out of service   |
| for the PPCS upgrade project.  EN #38518 indicated to the NRC that the       |
| systems would remain unavailable until approximately December 18, 2001.  Due |
| to reliability issues with the newly installed PPCS, that expected date has  |
| been delayed to approximately January 3, 2002."                              |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R3DO(Phillips).  |
|                                                                              |
| * * * UPDATE ON 01/03/02 @1430 BY MEYER TO GOULD * * *                       |
|                                                                              |
| During the installation of the new PPCS, issues were identified which need   |
| to be resolved to allow SPDS and ERDS to be placed back in service fully.    |
| Currently, the new PPCS is only partially operable.  Work is continuing on   |
| the new PPCS to allow full operability.  The current estimate for return to  |
| service of SPDS and ERDS is 01/19/02.  This date may need to be extended     |
| again due to parts availability.                                             |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Notified Reg 3 RDO(Shear)                                                    |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1855 BY HARRSCH TO GOULD * * *                     |
|                                                                              |
| Update to 1/3/02 update (see below).  Work continues on the Plant Process    |
| Computer System (PPCS) to allow full operability. The Safety Parameter       |
| Display System (SPDS) is still out of service, however the Emergency         |
| Response Data System (ERDS) is now available. As mentioned in the 1/3/02     |
| update, parts availability has been a problem and the date for returning     |
| SPDS to service is now estimated to be 2/16/02.                              |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 3 RDO(Vegel) was informed                                                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38596       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 12/26/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 15:39[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/21/2001|
+------------------------------------------------+EVENT TIME:        20:25[EST]|
| NRC NOTIFIED BY:  VEITCH                       |LAST UPDATE DATE:  01/17/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INDETERMINATE IF HIGH PRESSURE CORE SPRAY (HPCS) EMERGENCY DIESEL
GENERATOR  |
| (DG) COULD  FULFILL ITS REQUIRED SAFETY FUNCTION.                            |
|                                                                              |
| "On 12/21/01, Condition Report 01-4350 was initiated to document the failure |
| of Div . 3 DG to pass SVI-E22-T1319. Specifically, the DG did not come up to |
| frequency/voltage within the required 13 seconds (TS 3.8.1.7.b.2).  The DG   |
| was declared inoperable and an immediate investigation was requested.  The   |
| immediate investigation indicated that the cause of the SVI failure was due  |
| to the DG governor control switch not being properly set during shutdown on  |
| the DG on 12/16/01.  In analyzing the shutdown data from the 12/21/01 DG     |
| surveillance testing, it was determined that the situation had been          |
| corrected, and that the next DG start, the DG would satisfy the TS SR.  The  |
| DG was started on 12/22/01 and satisfied the SR.  The DG was then declared   |
| operable.                                                                    |
|                                                                              |
| "During this time, it is indeterminate if the HPCS DG could fulfill its      |
| required safety function.  The immediate investigation infers that an        |
| operator error occurred when shutting down the DG on 12/16/01.  This error,  |
| the mis-operation of the DG governor control switch, prevented the DG from   |
| properly coming up to the required frequency/voltage within 13 seconds as    |
| identified on 12/21/01.   Hence, it is conservative to assume that the       |
| capability to perform the safety function was not maintained.  This          |
| condition is an 8-hour report pursuant to 50.72(b)(3)(v) and (vi).  It       |
| should be noted that HPCS is a single train system and there are no          |
| redundant features within the same system to perform the safety function."   |
|                                                                              |
| The NRC resident inspector will be notified of this event by the licensee.   |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1204 BY RUSSELL TO GOULD * * *   RETRACTION        |
|                                                                              |
| On 12/26/01, a report was made per 10CFR50.72(b)(3)(v)(D) for the Loss of    |
| Safety Function of the High Pressure Core Spray pump, a single train safety  |
| system.  The cause of the loss of the HPCS pump was the failure of the       |
| DIVISION 3 diesel generator to achieve the required frequency.               |
| Subsequently, it was determined by further engineering evaluation that the   |
| HPCS pump and its supporting systems had sufficient margins available to     |
| perform the required safety functions at the reduced frequency.  Therefore,  |
| no loss of safety function occurred and therefore event notification 38596   |
| is retracted accordingly.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.  The Region 3 RDO (Vegel) was       |
| notified.                                                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38618       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 01/08/2002|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 17:25[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/08/2002|
+------------------------------------------------+EVENT TIME:        09:08[CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  01/17/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A POTENTIAL UNANALYZED CONDITION INVOLVING AN APPENDIX R
SAFE   |
| SHUTDOWN FIRE ANALYSIS                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "While investigating fire risk scenarios associated with the auxiliary       |
| feedwater system (see EN #38541), a potential unanalyzed condition involving |
| an Appendix R safe shutdown fire analysis was discovered.  The problem       |
| involves the availability of sufficient AFW flow capacity for a fire in the  |
| Central 26' and 46' areas of the Primary Auxiliary Building (Fire Area       |
| A01-B/Fire Zones 187 [and] 237)."                                            |
|                                                                              |
| "Cables and equipment associated with all [four] AFW pumps (both turbine-    |
| and motor-driven pumps) are located in this fire area.  A fire in this area  |
| could potentially cause a loss of normal Steam Generator instrumentation for |
| both units.  This would require shutdown of both units.  An alternate cable  |
| routing is available for only the Red channel of instrumentation.  This      |
| channel is only available for the 'B' train steam generators.  Therefore,    |
| the present Appendix R Safe Shutdown Analysis assumes this shutdown would be |
| accomplished using the 'B' steam generators for each unit and the P38B       |
| motor-driven AFW pump, which feeds the 'B' steam generator in each unit,     |
| along with the use of manual actions to mitigate the fire damage to cables   |
| associated with valves and instruments.  The nominal capacity of this AFW    |
| pump is 200 GPM."                                                            |
|                                                                              |
| "An Appendix R calculation shows that approximately 200 gal/min is required  |
| during the initial start-up of AFW flow to maintain sufficient heat removal  |
| capability for one unit.  Under the current conditions with procedural       |
| controls, only the one motor-driven AFW pump is made available, [and] there  |
| may not be enough capacity to provide adequate decay heat removal for both   |
| units.  Without sufficient AFW flow, the Appendix R performance requirement  |
| of 10 CFR [Part] 50, Appendix R III.G.L.2.c, which requires the reactor heat |
| removal function shall be capable of achieving and maintaining decay heat    |
| removal, may not be met.  This condition is potentially an unanalyzed        |
| Appendix R situation."                                                       |
|                                                                              |
| "As a compensatory measure, fire rounds are being conducted in the fire      |
| areas affected."                                                             |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE @ 1349 ON 1/17/02 BY RODE TO GOULD * * *       RETRACTION       |
|                                                                              |
| At 1625 CST on January 8, 2002, ENS Event Notification #38618 was made in    |
| accordance with 10 CFR 50.72(b)(3)(ii)(B) for identification of a potential  |
| unanalyzed condition involving the Appendix R safe shutdown fire analysis.   |
| The notification involved a concern with the availability of sufficient      |
| auxiliary feedwater (AFW) flow capacity for a fire in the Central 26' and    |
| 46' areas of the Primary Auxiliary Building (Fire Area A01 -B/ Fire Zones    |
| 187 & 237). The information documented in the SSAMS (Safe Shutdown Analysis  |
| Management System) database, indicated that the Appendix R fire scenario for |
| Fire Area A01-B relies on the use of a single motor driven AFW pump (P-038B) |
| to provide RCS decay heat removal for both units. The design capacity of     |
| P-038B is approximately 200 gpm @ 1,300 psi. An Appendix R Calculation       |
| demonstrates that approximately 200 gal/min is initially required during     |
| fire safe shutdown to maintain sufficient heat removal capability for each   |
| Unit. Therefore, P-038B, alone, does not provide sufficient decay heat       |
| removal capacity for both units.                                             |
|                                                                              |
| Upon closer examination of the analyses and documentation supporting the     |
| SSAMS, we have identified that this was not an unanalyzed condition but was  |
| due to a SSAMS documentation error.   A PBNP Manual Action Feasibility       |
| Report (FPTE-012) had evaluated the feasibility of the use of two separate   |
| sets of aux. feed water pumps for fires in different areas of Fire Area      |
| A01-B.  That report documented the capability for manually operating the     |
| steam supply valves to start the turbine driven pumps (each with a capacity  |
| in excess of 400 gpm which can be aligned to the unit's B' steam generators) |
| for a fire in Fire Zones 187-199.  For the fire in Fire Zone 237, the        |
| electric driven pumps can be manually aligned to the 'B' steam generators    |
| using the available cross-connect (i.e., opening valves AF-30 and AF-43).    |
| The two electric pumps provide a total capacity of 400 gpm, which is         |
| sufficient decay heat removal capacity for both units. This information was  |
| inadvertently omitted from the SSAMS database.  Based on this more complete  |
| information, we have concluded that an unanalyzed condition did not exist    |
| and are retracting our event notification.                                   |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Region 3 RDO (Vegel) was notified.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38631       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STORA ENSO NORTH AMERICA CORP.       |NOTIFICATION DATE: 01/16/2002|
|LICENSEE:  STORA ENSO NORTH AMERICA CORP.       |NOTIFICATION TIME: 09:56[EST]|
|    CITY:  WISCONSIN RAPIDS         REGION:  3  |EVENT DATE:        01/15/2002|
|  COUNTY:  WOOD                      STATE:  WI |EVENT TIME:        15:00[CST]|
|LICENSE#:  48-01117-01           AGREEMENT:  N  |LAST UPDATE DATE:  01/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTON VEGEL          R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLES CHAPMAN              |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A MISSING CESIUM-137 SOURCE AT A PAPER MILL (STORA ENSO
NORTH   |
| AMERICA CORP.) LOCATED IN WISCONSIN RAPIDS, WISCONSIN                        |
|                                                                              |
| During performance of a quarterly inventory on 01/15/02, the licensee        |
| discovered that a 200-millicurie cesium-137 source was missing.  It was used |
| as part of a fixed volume/density gauge which was mounted on a pipe.         |
| Apparently, the unit had been stored in the locked position on the pipe.     |
| The licensee reported that a paper machine dismantling project was ongoing   |
| near the previous location of the unit.  It is currently believed that the   |
| unit may either have been moved or dismantled and shipped somewhere.  The    |
| licensee's investigation is still in progress.                               |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
|                                                                              |
|                                                                              |
| * * *  UPDATE ON 1/17/02 @ 1711 BY CHAPMAN TO GOULD  * * *                   |
|                                                                              |
| After further investigation the licensee has determined the source may have  |
| been stolen from the site. The licensee has notified the police and Region   |
| 3.  The device manufacturer will be notified.                                |
| Notified RDO 3 (Vegel), NMSS EO(Frant)                                       |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1843 BY BREWSTER TO GOULD * * *                    |
|                                                                              |
| The licensee reported that they had been advised that an individual working  |
| for a contractor took the missing device.  They are further investigating    |
| the incident.                                                                |
|                                                                              |
| Notified RDO 3 (Vegel), NMSS EO(Frant)                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Research Reactor                                 |Event Number:   38633       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WASHINGTON STATE UNIVERSITY          |NOTIFICATION DATE: 01/17/2002|
|   RXTYPE: 1000 KW TRIGA (CONVERSION)           |NOTIFICATION TIME: 12:22[EST]|
| COMMENTS:                                      |EVENT DATE:        01/17/2002|
|                                                |EVENT TIME:             [PST]|
|                                                |LAST UPDATE DATE:  01/17/2002|
|    CITY:  PULLMAN                  REGION:  4  +-----------------------------+
|  COUNTY:  WHITMAN                   STATE:  WA |PERSON          ORGANIZATION |
|LICENSE#:  R-76                  AGREEMENT:  Y  |DALE POWERS          R4      |
|  DOCKET:  05000027                             |NADER MAMISH         IRO     |
+------------------------------------------------+CHRIS GRIMES         NRR     |
| NRC NOTIFIED BY:  SHARP                        |MARVIN MENDOCA       NRR     |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |JOE HOLONICH         IRO     |
+------------------------------------------------+BAGWELL              FEMA    |
|EMERGENCY CLASS:          ALERT                 |                             |
|10 CFR SECTION:                                 |                             |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WASHINGTON STATE UNIVERSITY REPORTED AN ALERT CONDITION AT THEIR
REACTOR     |
|                                                                              |
| The university reported they had a rod stuck 2" out of the core but the      |
| reactor is well shut down and they expect no radiological problems.  They    |
| did evacuate the building and notified their emergency organization, but did |
| not require the police or fire departments.  They will troubleshoot to       |
| determine the cause of the problem.                                          |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1747 BY TRIPARD TO GOULD * * *                     |
|                                                                              |
| Alert terminated at 1449 PST due to the rod being fully inserted and the     |
| reactor being in a safe and stable condition.  They will make an inspection  |
| to determine the problem.                                                    |
|                                                                              |
| Notified Mendonca(NRR), Lyons(EO), Powers(Reg 4 RDO), Sweetser(FEMA) OTHER   |
| AGENCIES by fax                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38634       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 01/17/2002|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 13:07[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        01/17/2002|
+------------------------------------------------+EVENT TIME:        11:45[EST]|
| NRC NOTIFIED BY:  KELLY KORTH                  |LAST UPDATE DATE:  01/17/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION  INVOLVING RECOVERED SEA TURTLE FROM INTAKE CANAL    
  |
|                                                                              |
| At approximately 1130 EST on 01/17/02, a green sea turtle was retrieved from |
| the intake canal and a determination was made that it was in need of         |
| rehabilitation.  As required by the Plant's Sea Turtle Permit, the Florida   |
| Fish and Wildlife Conservation Commission (FFWCC) was notified at 1145 EST.  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| See EN #38513 for 2001 occurrences.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38635       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STORA ENSO NORTH AMERICA CORP        |NOTIFICATION DATE: 01/17/2002|
|LICENSEE:  STORA ENSO NORTH AMERICA CORP        |NOTIFICATION TIME: 17:11[EST]|
|    CITY:  WISCONSIN RAPIDS         REGION:  3  |EVENT DATE:        01/15/2002|
|  COUNTY:                            STATE:  WI |EVENT TIME:        15:00[CST]|
|LICENSE#:  48-01117-01           AGREEMENT:  N  |LAST UPDATE DATE:  01/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTON VEGEL          R3      |
|                                                |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHAPMAN                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING EXIT SIGN                                                            |
|                                                                              |
| The licensee reported that during inventory check a Evanlite model LE exit   |
| sign that was installed in their facility was missing.  They believed the    |
| sign, with a 20,000 millicurie H-3 source,  was removed during ongoing       |
| remodeling.  They are still searching for the sign.                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38636       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OK DEQ RAD MANAGEMENT                |NOTIFICATION DATE: 01/17/2002|
|LICENSEE:  MILLS BIOPHARMACEUTICAL              |NOTIFICATION TIME: 18:14[EST]|
|    CITY:  OKLAHOMA                 REGION:  4  |EVENT DATE:        01/13/2002|
|  COUNTY:                            STATE:  OK |EVENT TIME:             [CST]|
|LICENSE#:  OK27502-01            AGREEMENT:  Y  |LAST UPDATE DATE:  01/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |SUSAN FRANT          NMSS    |
+------------------------------------------------+ROBERT HAAG          R2      |
| NRC NOTIFIED BY:  BISHOP                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OKLAHOMA LICENSEE REPORTED A MISSING SHIPMENT IODINE-125
BRACHYTHERAPY       |
| SEEDS                                                                        |
|                                                                              |
| Mills Biopharmaceutical Co reported that a shipment which left 1/11 via      |
| FedEx did not reach its destination, the Palisades Medical Center in New     |
| Jersey, on the expected date 1/14/02.   The shipment consisted of            |
| brachytherapy seeds containing 13.3 millicuries of I-125.  The               |
| biopharmaceutical company was notified by FedEx on 1/13 that the shipment    |
| had experienced a processing delay in Memphis, TN. and now FedEx can not     |
| locate the shipment.   FedEx is currently looking for it.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38637       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COLORADO DEPT OF HEALTH              |NOTIFICATION DATE: 01/17/2002|
|LICENSEE:  LITTLETON RADIATION ONCOLOGY         |NOTIFICATION TIME: 18:23[EST]|
|    CITY:  DENVER                   REGION:  4  |EVENT DATE:        08/03/2001|
|  COUNTY:                            STATE:  CO |EVENT TIME:             [MST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BONZER (fax)                 |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OCCUPATIONAL EXPOSURE INCIDENT                                               |
|                                                                              |
|                                                                              |
| On August 3, 2001, Littleton Radiation Oncology called to report error codes |
| 4 and 20.   Upon inspection, the Field Service Engineer (FSE) identified a   |
| loop in the source cable at the top of the source drum. The FSE removed the  |
| loop in the cable; however, the source motor would not drive the source out. |
| The source exchange tool was connected to the service port of the emergency  |
| container and the source was driven out manually.  The emergency container   |
| was used to house the source instead of the source shipping pig since the    |
| motor would not drive the source.  Per the FSE, the lead technologist was    |
| informed of the source status within the room and that the source would need |
| to be moved to a secure storage area.                                        |
| The FSE then left the treatment room to discuss the situation with the       |
| physician when the lead technologist interrupted indicating that the source  |
| had been pulled out of the container.  The FSE secured the source in the     |
| emergency container. Parts to make the appropriate repairs were sent         |
| immediately and the afterloader was restored to proper working condition.    |
| In order to identify the problem, secure the source, and make repairs, the   |
| FSE handled a partially shielded to unshielded source on three occasions: i. |
| manually driving the source into the emergency container, ii. securing the   |
| source back into the emergency container after it been pulled out by         |
| ancillary staff, iii. moving the source from the emergency container to the  |
| shipping pig.                                                                |
|                                                                              |
| The FSE wore a self-reading dosimeter along with body and extremity badges   |
| provided by Landauer.   The occupational exposure reported by Landauer for   |
| the period during which the exposure incident occurred is as follows:        |
|                                                                              |
| Deep Dose (DDE) 447 mrem                                                     |
| Extremity (SDE) 760 mrem                                                     |
| The  year to date  (1/15/01-8/14/01) total for the individual is 487 mrem    |
| (DDE).                                                                       |
+------------------------------------------------------------------------------+