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Event Notification Report for September 3, 2002

                 
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/30/2002 - 09/03/2002

                              ** EVENT NUMBERS **

39155  39156  39159  39161  39162  39163  39164  

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|General Information or Other                     |Event Number:   39155       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 08/27/2002|
|LICENSEE:  NITON CORPORATION                    |NOTIFICATION TIME: 16:06[EDT]|
|    CITY:  BILLERICA                REGION:  1  |EVENT DATE:        08/27/2002|
|  COUNTY:                            STATE:  MA |EVENT TIME:             [EDT]|
|LICENSE#:  55-0238               AGREEMENT:  Y  |LAST UPDATE DATE:  08/27/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES NOGGLE         R1      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOSH DAHLER                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - REPORT OF LEAKING SEALED SOURCE                     |
|                                                                              |
| "On August 27, 2002, Niton Corporation provided a report of a leaking sealed |
| source that was discovered by Niton on July 5, 2002 during removal of a      |
| source from a Niton XLi Series X-ray fluorescence device source holder.  The |
| seal source is AEA Model IEC.A1, S/N 8740LG containing Fe-55.  The estimated |
| leakage was 130,000 dpm (0.059 microcuries).                                 |
|                                                                              |
| "The leaking source was placed in a lead pig.  The source holder was         |
| decontaminated.  The workbench and surrounding area were surveyed and found  |
| to be free of contamination.  The leaking source and all decontamination     |
| material were placed into the licensee's waste stream."                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39156       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 08/28/2002|
|LICENSEE:  KLEINFELDER, INC.                    |NOTIFICATION TIME: 00:35[EDT]|
|    CITY:  DIAMOND BAR              REGION:  4  |EVENT DATE:        08/26/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:  6852-19               AGREEMENT:  Y  |LAST UPDATE DATE:  08/28/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID GRAVES         R4      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGER                |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A LOST/STOLEN TROXLER GAUGE                 |
|                                                                              |
| A Troxler gauge, model 3411, was found missing from a storage building at a  |
| Redlands, CA location.  The gauge, serial number 12878, contains Cs-137 and  |
| Am-241/Be.  Local law enforcement has been notified and a reward has been    |
| offered for it's return.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39159       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ROSEMOUNT NUCLEAR INSTRUMENTS, INC   |NOTIFICATION DATE: 08/30/2002|
|LICENSEE:  ROSEMOUNT NUCLEAR INSTRUMENTS, INC   |NOTIFICATION TIME: 14:05[EDT]|
|    CITY:  EDEN PRAIRIE             REGION:  3  |EVENT DATE:        08/30/2002|
|  COUNTY:                            STATE:  MN |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  08/30/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |RONALD GARDNER       R3      |
|                                                |JAMES NOGGLE         R1      |
+------------------------------------------------+STEPHEN CAHILL       R2      |
| NRC NOTIFIED BY:  JEFFREY W. SCHMITT           |DAVID GRAVES         R4      |
|  HQ OPS OFFICER:  STEVE SANDIN                 |VERN HODGE           NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 INVOLVING NON-CONFORMING ROSEMOUNT PRESSURE TRANSMITTERS AND SPARE   |
| PARTS                                                                        |
|                                                                              |
| The following information was received via fax:                              |
|                                                                              |
| "Re: Notification under 10 CFR Part 21 for Model 1153 and 1154 pressure      |
| transmitters with optional adjustable damping circuit boards, and spare      |
| adjustable damping circuit boards                                            |
|                                                                              |
| "Pursuant to 10 CFR Part 21, section 21.21(b), Rosemount Nuclear             |
| Instruments, Inc. (RNII) is writing to inform you that:                      |
|                                                                              |
| (a) certain Model 1153 and 1154 pressure transmitters with special           |
| adjustable damping options N0037, N0039, N0058, N0085, N0102, N0108, N0120   |
| shipped between December 2000 and July 2002, and                             |
|                                                                              |
| (b) certain spare adjustable damping circuit boards with part number         |
| 01154-0021-0004 shipped between December 2000 and July 2002, may not meet    |
| RNII's published Nuclear Steam Pressure/Temperature specification and/or     |
| RNII's published Post DBE Operation specification. Model 1153 and 1154       |
| transmitters which do not contain the special optional adjustable damping    |
| circuit board are not affected. The adjustable damping feature establishes   |
| the time constant of the transmitter's output.  A list of affected Model     |
| 1153 and 1154 transmitters and spare adjustable damping circuit boards       |
| shipped to the end user's facility is provided in Attachment A.              |
|                                                                              |
| "1.0 Name and address of the individual providing the information:           |
|                                                                              |
| Mr. Jeffrey W. Schmitt                                                       |
| Vice President & General Manager                                             |
| Rosemount Nuclear Instruments, Inc.                                          |
| 12001 Technology Drive                                                       |
| Eden Prairie, MN 55344                                                       |
|                                                                              |
| "2.0 Identification of items supplied:                                       |
|                                                                              |
| Model 1153 and 1154 Pressure Transmitters with special adjustable damping    |
| options N0037, N0039, N0058, N0085, N0102, N0108, N0120 as identified by the |
| appropriate model code. The applicable model codes begin with either  '1153' |
| or '1154'  and end with the applicable N option number, for example          |
| '1154DP5RAN0037.'                                                            |
|                                                                              |
| and;                                                                         |
|                                                                              |
| Spare adjustable damping circuit boards with part number 01154-0021-0004.    |
|                                                                              |
| See Attachment A for complete listing of affected equipment shipped to the   |
| end user's facility.                                                         |
|                                                                              |
| "3.0 Identification of firm supplying the item:                              |
|                                                                              |
| Rosemount Nuclear Instruments, Inc.                                          |
| 12001 Technology Drive                                                       |
| Eden Prairie, MN 55344                                                       |
|                                                                              |
| "4.0 Nature of the failure and potential safety hazard:                      |
|                                                                              |
| This notification impacts:                                                   |
|                                                                              |
| (a) certain Model 1153 and 1154 pressure transmitters with special           |
| adjustable damping options N0037, N0039, N0058, N0085, N0102, N0108, N0120   |
| shipped between December 2000 and July 2002 and                              |
|                                                                              |
| (b) certain spare adjustable damping circuit boards with part number         |
| 01154-0021-0004 shipped between December 2000 and July 2002, which may not   |
| meet RNII's published Nuclear Steam Pressure/Temperature specification       |
| and/or RNII's published Post DBE Operation specification.                    |
|                                                                              |
| American Capacitor Corporation, the manufacturer of a capacitor used on the  |
| adjustable damping circuit board recently informed RNII that capacitors      |
| shipped to RNIIs adjustable damping circuit board supplier after June 2000   |
| were inadequately tested for conformance to the required high temperature    |
| insulation resistance (IR) as specified by RNII's procurement documents.     |
| Subsequent RNII testing confirmed that the capacitors were non-conforming to |
| RNII's IR specifications. These non-conforming capacitors were assembled     |
| into certain transmitters and spare circuit boards that were shipped from    |
| RNII between December 2000 and July 2002. Further RNII testing demonstrated  |
| that model 1153 and 1154 transmitters with the optional adjustable damping   |
| circuit boards containing non-conforming capacitors would not meet RNIIs     |
| published Nuclear Steam Pressure/Temperature and Post DBE Operation          |
| specifications for the published temperature profile. Due to the transmitter |
| performance variation present in the test results, RNII cannot provide an    |
| interim specification.                                                       |
|                                                                              |
| Testing has demonstrated that affected adjustable damping circuit boards do  |
| meet product specifications at normal operating temperatures (40-200 degrees |
| F)                                                                           |
|                                                                              |
| RNII does not have sufficient information relative to the end user's         |
| specific applications to determine the potential safety-related impact to    |
| its plant. The end user must determine the impact on its plant operations    |
| and plant safety and take action as deemed necessary.                        |
|                                                                              |
| "5.0 The corrective action which is taken, the name of the individual or     |
| organization responsible for that action, and the length of time taken to    |
| complete that action:                                                        |
|                                                                              |
| (a) Upon notification from the capacitor manufacturer of this issue, RNII    |
| placed holds on all shipments containing potentially affected equipment      |
| (model 1153 and 1154 transmitters with the special adjustable damping        |
| options N0037, N0039, N0058, N0085, N0102, N0108, N0120 and spare adjustable |
| damping circuit boards with part number 01154-0021-0004).                    |
|                                                                              |
| (b) The capacitor manufacturer identified the specific capacitor lots that   |
| were inadequately tested. Only adjustable damping circuit boards built with  |
| capacitors from these lots are affected.                                     |
|                                                                              |
| (c) RNII performed subsequent testing and established that Model 1153 and    |
| 1154 transmitters with special adjustable damping options N0037, N0039,      |
| N0058, N0085, N0102, N0108, N0120 having adjustable damping circuit boards   |
| containing capacitors that do not meet RNII IR specifications would not meet |
| the published Nuclear Steam Pressure/Temperature specification and/or Post   |
| DBE Operation specification for the published temperature profile. Testing   |
| has demonstrated that affected adjustable damping circuit boards do meet     |
| product specifications at normal operating temperatures (40-200 degrees F),  |
|                                                                              |
| (d) RNII has initiated actions with the adjustable damping circuit board     |
| supplier to ensure that all capacitors received from sub-suppliers are       |
| tested to demonstrate compliance with the IR specifications prior to         |
| installation on adjustable damping circuit boards.                           |
|                                                                              |
| (e) Replacement capacitors have been identified and tested which conform to  |
| RNII's procurement specifications. RNII will audit the quality system of the |
| new supplier to assure its quality system meets the requirements of 10CFR    |
| Part 50 Appendix B and all requirements of a qualified supplier to RNII.     |
| Completion: 6 September 2002.                                                |
|                                                                              |
| (f) RNII will repair or replace any affected adjustable damping circuit      |
| board at the end user's request. Completion: As required.                    |
|                                                                              |
| "6.0 Any advice related to the potential failure of the item:                |
|                                                                              |
| "The end user must determine the impact of this deviation upon its plant's   |
| operation and safety and take action as deemed necessary. If the end user    |
| determines that replacement of the affected special adjustable damping       |
| circuit boards is required, please contact Rosemount Nuclear Instruments,    |
| Inc. to obtain a replacement adjustable damping circuit board."              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39161       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 08/30/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:02[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/30/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        01:05[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/30/2002|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |RONALD GARDNER       R3      |
|  DOCKET:  0707002                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REPORT INVOLVING A VALID ACTUATION OF A "Q" SAFETY SYSTEM                    |
|                                                                              |
| "At 0105 hrs, Autoclave (AC) #4 in the X-344 facility experienced a steam    |
| shutdown due to condensate level alarms A and B actuating.   AC #4 was in an |
| applicable TSR mode II (heating) when the alarms actuated. This is           |
| considered a valid actuation of a 'Q' safety system. The AC was placed in    |
| mode 7 (shutdown).  An investigation is underway to determine the cause of   |
| the actuation."                                                              |
|                                                                              |
| Operations informed both the DOE Site Representative and the NRC Resident    |
| Inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39162       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 08/31/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/31/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        01:20[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/31/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |RONALD GARDNER       R3      |
|  DOCKET:  0707001                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  K. A. BEASLEY                |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 24 HOUR REPORT - IMPROPER ISOLATION OF PUMP PRESSURE      |
| ALARMS                                                                       |
|                                                                              |
| The following is taken from a facsimile report.                              |
|                                                                              |
| At 0120, on 8-31-02 the Plant Shift Superintendent (PSS) determined that a   |
| loss of double contingency had occurred in the C-337 process building. In    |
| preparation for maintenance work on the #2 dual Speed Purge and Evacuation   |
| (P&E) pump Instrument Maintenance had been requested to disable the two      |
| delta pressure alarms associated with this pump. The delta pressure alarms   |
| are safety related items (SRI). The SRI requires that both delta pressure    |
| alarms be functional while the P&E pump is isolated from the cascade.        |
| Building Operations personnel later discovered that one of the delta         |
| pressure alarms that had been disabled was an alarm for the #3 P&E pump      |
| which was not undergoing maintenance.  Both delta-pressure alarms for the #3 |
| P&E pump were required to be in service at the time. The C-337 Front Line    |
| Manager and Instrument Maintenance responded to the alarm panel and restored |
| the alarm to the #3 P&E pump.  At that time, double contingency was          |
| restored.                                                                    |
|                                                                              |
| This event resulted in a loss of one leg of double contingency in which      |
| double contingency was restored within 4 hours.                              |
|                                                                              |
| The NRC Resident Inspector has been notified.                                |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| While the R-114 was demonstrated to be dry, an SRI for double contingency    |
| was rendered not functional without the knowledge of the operator.           |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR)                                                     |
|                                                                              |
| In order for a criticality to occur, an unsafe mass uranium deposit would    |
| have to be present in the process gas system, an R-114 leak to the process   |
| gas system would have to occur, the R-114 would have to contain an           |
| unacceptable amount of moisture and moderate the deposit.                    |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. CONCENTRATION, ETC        |
|                                                                              |
| Double contingency is maintained by implementing two controls on             |
| moderation.                                                                  |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORMS OF LICENSED MATERIAL (INCLUDES PROCESS   |
| LIMIT AND % WORST CASE CRITICAL MASS):                                       |
|                                                                              |
| No known mass of licensed material exists in the #3 Dual Speed P & E pump.   |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL SYSTEM(S) OR CONTROL SYSTEM(S) AND        |
| DESCRIPTION OF THE FAILURES OR DEFICIENCIES                                  |
|                                                                              |
| The first leg of double contingency is based on the delta pressure switch    |
| alarming to alert the operator to take action to either verify the R-114 is  |
| dry or to isolate the RCW and remove the R-114 from the system in order to   |
| prevent water from leaking into the process gas system. This delta pressure  |
| alarm was maintained as operable, the SRI was maintained and the control was |
| not violated.                                                                |
|                                                                              |
| The second leg of double contingency is based on the independent delta       |
| pressure switch alarming to alert the operator to take action to either      |
| verify the R-114 is dry or to isolate the RCW and remove the R-114 from the  |
| system in order to prevent water from leaking into the process gas system.   |
| The independent delta pressure alarm was disconnected without first          |
| isolating the RCW system violating the SRI.  The Independent delta pressure  |
| switch was reconnected immediately upon discovery.  This re-established      |
| double contingency.                                                          |
|                                                                              |
| Since double contingency is based on two controls (i.e. SRIs) on one         |
| parameter, double contingency was not maintained.                            |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| 1.  Make the #3 dual speed P&E alarm operable.                               |
| 2.  Independently sample the #3 dual speed P&E R-114 system for moisture.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39163       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U. S. STEEL-GARY WORKS               |NOTIFICATION DATE: 09/01/2002|
|LICENSEE:  U. S. STEEL                          |NOTIFICATION TIME: 14:42[EDT]|
|    CITY:  GARY                     REGION:  3  |EVENT DATE:        09/01/2002|
|  COUNTY:  LAKE                      STATE:  IN |EVENT TIME:        05:02[CST]|
|LICENSE#:  13-079664-08          AGREEMENT:  N  |LAST UPDATE DATE:  09/01/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |RONALD GARDNER       R3      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BRIAN KUNKLE                 |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED SOURCE HOLDER ON STEEL CASTER LEVEL GAUGE                            |
|                                                                              |
| A radioactive source holder on a steel caster unit was damaged from metal    |
| overflow at the U. S. Steel - Gary Works, Steel North Facility #2 Caster,    |
| located in Gary, Indiana. The gauge is a Berthold Mold Level Gauge, Model    |
| LB300ML, Serial Number 2849-12-96. Originally a 10 millicurie Cobalt 60 (Dec |
| 1996) source, it is currently estimated by the licensee to be about 5        |
| millicuries. The damage was  limited to the source holder outer casing.      |
| Neither the shutter closing mechanism nor the source shielding (tungsten)    |
| were damaged. The damaged area involved a top plate where a lock can be      |
| applied to the shutter mechanism and steel lifting lugs. The source was      |
| verified in the source holder and the shutter closed. A radiation survey of  |
| the area was conducted and no contamination or abnormal readings were        |
| detected. The licensee has secured the shielded source and is making         |
| arrangements for repair.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39164       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 09/02/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 22:22[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        09/02/2002|
+------------------------------------------------+EVENT TIME:        21:00[CDT]|
| NRC NOTIFIED BY:  CLARK                        |LAST UPDATE DATE:  09/02/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       9        Power Operation  |7        Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED TS 3.5.3 DUE TO THE RCIC TURBINE SYSTEM BEING DECLARED         |
| INOPERABLE                                                                   |
|                                                                              |
| The plant commenced reactor shutdown at 2100 CDT due to the RCIC turbine     |
| bearing oil system not maintaining the proper oil level.  They are currently |
| troubleshooting the problem but have not yet determine the cause.   The TS   |
| 3.5.3 requires the plant to be in mode 3 by 0028 on 9/3/02 and reduce        |
| reactor steam pressure to less than or equal to 150 lbs. By 0028 on 9/4/02.  |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+