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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Page Last Reviewed/Updated Thursday, March 25, 2021