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Event Notification Report for September 10, 2002

                             Operations Center

                              Event Reports For
                           09/09/2002 - 09/10/2002

                              ** EVENT NUMBERS **

39175  39178  39179  

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|Power Reactor                                    |Event Number:   39175       |
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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 09/09/2002|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 13:58[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        09/09/2002|
+------------------------------------------------+EVENT TIME:        10:08[CDT]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  09/09/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHRISTINE LIPA       R3      |
|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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MEDICAL EMERGENCY INVOLVING CONTRACT EMPLOYEE                                |
|                                                                              |
| "Today at approximately 10:08 AM a report was received in the control room   |
| of a medical emergency involving a contract employee at the Point Beach      |
| nuclear power plant. Onsite medical personnel responded and commenced first  |
| aid including CPR. CPR was continued until ambulance personnel arrived on    |
| site. The individual was transported to a local hospital.                    |
|                                                                              |
| "We have been informed by a subsequent report from the hospital that the     |
| individual died from an apparent heart attack.                               |
|                                                                              |
| "The Manitowoc County coroner's office and OSHA have been informed of the    |
| fatality. At this time no press release is planned."                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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|General Information or Other                     |Event Number:   39178       |
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| REP ORG:  ROSEMOUNT NUCLEAR INSTUMENTS, INC    |NOTIFICATION DATE: 09/09/2002|
|LICENSEE:  ROSEMOUNT NUCLEAR INSTUMENTS, INC    |NOTIFICATION TIME: 15:15[EDT]|
|    CITY:  EDEN PRAIRIE             REGION:  3  |EVENT DATE:        09/09/2002|
|  COUNTY:                            STATE:  MN |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  09/09/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID LEW            R1      |
|                                                |DAVID AYRES          R2      |
+------------------------------------------------+CHRISTINE LIPA       R3      |
| NRC NOTIFIED BY:  EMERSON PROCESS MGMT.        |JACK WHITTEN         R4      |
|  HQ OPS OFFICER:  GERRY WAIG                   |TIM MCGINTY          IRO     |
+------------------------------------------------+VERN HODGE           NRR     |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NOTIFICATION UNDER 10 CFR PART 21 FOR MODEL 1153 DIFFERENTIAL PRESSURE       |
| TRANSMITTERS                                                                 |
|                                                                              |
| The following is taken from a facsimile report sent by Emerson Process       |
| Management:                                                                  |
|                                                                              |
| "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 differential pressure transmitters with model codes   |
| beginning with '1153D' or '1153H' shipped between March 2001 and August      |
| 2002, and                                                                    |
|                                                                              |
| (b) spare sensor modules shipped between March 2001 and August t2002 with    |
| kit part numbers:                                                            |
|                                                                              |
| 01153-0320-0232                                                              |
| 01153-0320-0352                                                              |
| 01153-0320-0252                                                              |
|                                                                              |
| "may not meet RNII's published temperature effect specification. Other Model |
| 1152, 1153 and 1154 pressure transmitters are not affected. A list of        |
| affected Model 1153 pressure transmitters and spare sensor modules 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:                                       |
|                                                                              |
| Certain Model 1153 differential pressure transmitters with model codes       |
| beginning with  1153D  or  1153H shipped between March 2001 and August 2002  |
| and;                                                                         |
|                                                                              |
| "Spare sensor modules shipped between March 2001 and August 2002 with kit    |
| part numbers:                                                                |
|                                                                              |
| 01153-0320-0232                                                              |
| 01153-0320-0352                                                              |
| 01153-0320-0252                                                              |
|                                                                              |
| "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:                      |
|                                                                              |
| During the course of quality testing and data review, RNII has determined    |
| that certain Model 1153 differential pressure transmitters and spare sensor  |
| modules may not meet the published temperature effect specification. The     |
| temperature effect specification establishes an expected analog output error |
| interval during normal ambient temperature variations occurring between 40   |
| [degrees] F (4.4 [degrees] C) and 200 [degrees] F (93.3 [degrees] C). While  |
| analysis is still ongoing, the root cause of the potential nonconformance    |
| has been narrowed to the effect of temperature changes on the transmitter    |
| module.                                                                      |
|                                                                              |
| Based on data review and analysis, RNII has established the following        |
| ambient temperature effect specification for transmitters affected by this   |
| notification. This specification supercedes the published temperature effect |
| specification for all pressure transmitters affected by this notification.   |
|                                                                              |
| All Range Codes:  3.0% of Upper Range Limit per 100 [degrees] F (55.6       |
| [degrees] C)                                                                 |
|                                                                              |
| RNII does not have sufficient information relative to each end user's        |
| specific applications to determine the potential safety-related impact to    |
| each end users plant. Each 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) RNII has expanded its temperature effect test screen to include all      |
| model 1153 pressure transmitters to assure that all further shipments of     |
| model 1153 pressure transmitters meet RNII's published temperature effect    |
| specification.                                                               |
|                                                                              |
| (b) RNII has placed a hold on spare sensor module shipments.                 |
|                                                                              |
| (c) RNII has established a new temperature effect specification for pressure |
| transmitters impacted by this notification as noted in Section 4.0.          |
|                                                                              |
| (d) RNII will verify ambient temperature effect performance to the original  |
| specification on any returned Model 1153 differential pressure transmitter   |
| or sensor module affected by this notification and repair or replace if      |
| required.                                                                    |
|                                                                              |
| (e) RNII will continue root cause analysis of the temperature effect         |
| potential non-conformance. Action will be taken consistent with the findings |
| of this analysis to assure conformance to RNII's published temperature       |
| effect specifications. Anticipated completion date: 1 November 2002.         |
|                                                                              |
| (f) RNII will remove the hold on spare sensor modules when actions per 5.0   |
| (e) are complete.                                                            |
|                                                                              |
| "6.0 Any advice related to the potential failure of the item:                |
|                                                                              |
| The end user must determine the impact of this potential non-conformance     |
| upon its plant's operation and safety and take action as deemed necessary.   |
| If the end user determines that return of a pressure transmitter or sensor   |
| module is required, RNII should be contacted to facilitate the return        |
| process.                                                                     |
|                                                                              |
| Rosemount Nuclear Instruments, Inc. has a strong commitment to the nuclear   |
| industry and assures you that we are dedicated to the supply of high quality |
| products and services to our customers. We are sorry for any potential       |
| impact that this notification might cause. If there are any questions, or    |
| you require additional information related to this issue, please contact     |
| Mike Dougherty (952) 828-5626, Gerard Hanson (952) 828-3951, Bob Cleveland   |
| at (952) 828-8255, or Matt Doyle at (952) 828-3480."                         |
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|Power Reactor                                    |Event Number:   39179       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 09/09/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 22:30[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        09/09/2002|
+------------------------------------------------+EVENT TIME:        15:59[CDT]|
| NRC NOTIFIED BY:  RICK HUBBARD                 |LAST UPDATE DATE:  09/09/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JACK WHITTEN         R4      |
|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     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| FAILED RELAY CARD CAUSE AUTOMATIC START OF THE "A" EDG  AND THE TURBINE      |
| DRIVEN AUXILIARY FEED WATER PUMP                                             |
|                                                                              |
| "On September 9, 2002 at 1559, with Wolf Creek in Mode 1 at 100 % power, the |
| Control Room received annunciator 19E, NB01 degraded voltage. Approximately  |
| 90 seconds later, the NB01 normal feeder breaker opened. The 'A' Emergency   |
| Diesel Generator (EDG) started and loaded onto the bus as expected. After    |
| the 'A' EDG restored NB01 bus voltage to normal, annunciator 19E remained    |
| locked in. The cause of the actuation appears to be a failure of the relay   |
| driver card that supplies the degraded voltage signal to the Load Sequencer  |
| Emergency Load Shedder (LSELS). Instrumentation and Control Technicians      |
| (INC) expect repairs to be complete by 0000, September 10, 2002.             |
|                                                                              |
| "As expected, an automatic start of the turbine driven auxiliary feedwater   |
| pump occurred upon the under voltage condition on NB01. After the bus was    |
| re-energized, the shutdown sequencer actuated and emergency loads sequenced  |
| as expected.                                                                 |
|                                                                              |
| "Based on the guidance provided in NUREG 1022, Revision 2, this situation    |
| meets the criteria of 10 CFR 50.72 (b)(3)(iv)(A) for an 8-hour ENS           |
| notification as it relates to actuation of the emergency ac electrical power |
| systems, which includes emergency diesel generators.                         |
|                                                                              |
| "The licensee has notified the NRC resident inspector."                      |
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