05000498/LER-2007-003
South Texas, Unit 1 | |
Event date: | |
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Report date: | |
Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
4982007003R00 - NRC Website | |
I.�DESCRIPTION OF REPORTABLE EVENT
A. REPORTABLE EVENT CLASSIFICATION
This event is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications (TS). Extended Range Nuclear Instrumentation Channel NI-46 was inoperable for greater than the 7-day Allowed Outage Time permitted by TS 3.3.3.6 due to the installation of an incorrect model Log Count and Rate circuit board.
B. PLANT OPERATING CONDITIONS PRIOR TO THE EVENT
At the time of the event, Unit 1 was operating at 100%.
C. STATUS OF STRUCTURES, SYSTEMS, OR COMPONENTS THAT WERE
INOPERABLE AT THE START OF THE EVENT AND THAT CONTRIBUTED TO THE
EVENT
No equipment that was inoperable at the initiation of the event contributed to the event.
D. NARRATIVE SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE
TIMES
At 1900 on April 6, 2007, with Unit 1 at 100% power, Extended Range Nuclear Instrumentation Channel NI-46 was declared inoperable due to erratic indication.
Subsequent troubleshooting identified that the "A4" Log Count & Rate circuit board was defective and needed to be replaced. Each of the Extended Range Nuclear Instrumentation channels (NI-45 and NI-46) utilizes two printed circuit boards, designated as "A2" and "A4," to condition signals received from the associated Extended Range detector. Instrumentation & Control (I&C) personnel made the decision to use an A2 board as a replacement instead of an A4 board based on information from training material, which indicated the boards were interchangeable, and based on the use of a the stock code number for the A2 board when no stock code number for the A4 board could be found in the Master Equipment Database / Master Parts List (MED/MPL). The training material is not a controlled document, and the stock code field used to assist in making the decision is a reference field only. The correct database information that should have been referred to was the manufacturer's part number, which is a controlled field, and was unique for each board. It should also be noted that older versions of the A2 and A4 boards contain slots that would allow installation in either the A2 or A4 location in the signal processor assembly. This was the case with the A2 board installed on April 7.
The A2 board was installed and calibrated with the post maintenance test (PMT) being completed satisfactorily and NI-46 was declared operable at 0456 on April 7, 2007.
On April 7, 2007 at 1352 a condition report was generated stating that the NI-46 shutdown monitor was reading low when it should be reading high.
On April 14, 2007, a condition report was generated stating the start up rate indication was indicating higher than it should. While performing work under this work order, it was identified that the A2 board installed in the A4 slot on April 7, 2007 was the wrong type of board which caused the startup rate indication to read higher than it should in addition to the shutdown monitor reading lower than expected.
Following replacement of the A2 board with a new A4 board, NI-46 was successfully returned to service and declared operable at 2310 on April 14, 2007.
Additional investigation into this issue has identified that per the Extended Range Nuclear Instrumentation vendor information (Gamma Metrics), prior to 1986 the A2 and A4 boards were interchangeable. However, in the April 10, 1986 revision to the vendor manual, the A4 board design was changed, although this information was not well documented in this or subsequent revisions of the manual. Additionally, no information exists to indicate that STPNOC received information from the vendor regarding the A4 board design change.
This resulted in a lack of review by STPNOC which would have evaluated this design change for impact and properly documented and annotated the changes within STP process and programs.
E.�THE METHOD OF DISCOVERY OF EACH COMPONENT OR SYSTEM FAILURE, OR
PROCEDURAL OR PERSONNEL ERROR
Installation of the incorrect Log Count and Rate board in the NI-46 Extended Range Nuclear Instrumentation channel was, discovered during maintenance troubleshooting of NI-46 erratic / unexpected indication on April 14, 2007.
The original reportability review of this occurrence performed in April 2007 did not reach the correct reportability conclusion, however, subsequent re-evaluation of this issue led to the determination on October 5, 2007, that this was a reportable event per 10 CFR 50.73(a)(2)(i)(B) as an event involving operation or condition prohibited by Technical Specifications (i.e., inoperability greater than TS Allowed Outage Time).
II.�COMPONENT OR SYSTEM FAILURES
A. FAILURE MODE, MECHANISM, AND EFFECTS OF EACH FAILED COMPONENT
This issue documented in this Licensee Event Report is not a result of a failed component.
B. CAUSE OF EACH COMPONENT OR SYSTEM FAILURE
Not applicable.
C. SYSTEMS OR SECONDARY FUNCTIONS THAT WERE AFFECTED BY FAILURE OF
COMPONENTS WITH MULTIPLE FUNCTIONS
None.
D. FAILED COMPONENT INFORMATION
Not applicable.
III.�ANALYSIS OF THE EVENT A.�SAFETY SYSTEM RESPONSES THAT OCCURRED No safety system responses were required or occurred.
B. DURATION OF SAFETY SYSTEM TRAIN INOPERABILITY
Extended Range Nuclear Instrumentation channel NI-46 was inoperable from April 6, 2007 at 1900 until April 14, 2007 at 2310, which exceeds the 7-day Allowed Outage Time by 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> 10 minutes.
C. SAFETY CONSEQUENCES AND IMPLICATIONS
The event did not have an adverse affect on the health and safety of the public.
The Extended Range Nuclear Instrumentation channels (NI-45 and NI-46) do not provide any automatic protection signal, but provide indication and alarm functions only. The redundant Extended Range channel (NI-45) remained operable for the duration of the NI-46 inoperability. Additionally, all Technical Specification required channels of Power Range and Intermediate Range Nuclear Instrumentation were operable during the NI-46 inoperability time period. Furthermore, the period of time by which Channel NI-46 exceeded its 7-day Allowed Outage Time was only slightly greater than one additional day.
Therefore the safety significance and risk impact of the Channel NI-46 inoperability beyond its Allowed Outage Time is minimal.
This event resulted in no personnel injuries, no offsite radiological releases, and no damage to other safety-related equipment.
IV.0CAUSE OF THE EVENT
- The Extended Range Nuclear Instrumentation vendor (Gamma Metrics) made a change to the A2 and A4 circuit boards that removed the slot interchangeability design without notification to STPNOC. This resulted in lack of review by STPNOC which would have identified this change and properly documented and annotated the changes within STP process and programs.
- I&C personnel made the decision to use the A2 board instead of the A4 board based on outdated information from Training material, which indicated the parts were interchangeable, and the use of the stock code number for the A2 board when no stock code number for the A4 board could be found in the Master Parts List. The training material is not a controlled document. The stock code field that was used in the Master Parts List to assist in making this decision is a reference field only. The correct database information that should have been referred to was the manufacturer's part number, which is a controlled field, and was unique for each board.
V.�CORRECTIVE ACTIONS
- STPNOC replaced the incorrect board and restored Extended Range channel NI-46 to operability.
- A QC inspection hold point will be added to the Master Equipment Database / Master Parts List to confirm all incoming A2 and A4 boards received in the warehouse have only one key on each board (specific to its respective signal processing assembly slot).
- All A2 and A4 boards in the warehouse will be inspected and any double-keyed board will be disposed of.
- Training will be provided to l&C personnel regarding the use of Master Parts List information fields.
VI.�PREVIOUS SIMILAR EVENTS There have been no STPNOC Licensee Event Reports in the past three years regarding the installation of a wrong component. A review of the STP Corrective Actions Program identified two similar wrong parts related Condition Reports, both occurring in 2002:
- On May 1, 2002, an incorrectly size screen was installed on a Moisture Separator Drip Tank Pump motor.
On June 12, 2002, a 120 VAC coil was delivered to the field, whereas a 125 VDC coil was
- needed. Maintenance personnel identified the incorrect part before it was installed.
The corrective actions associated with these occurrences were specific to their respective issue and would not have precluded the incorrect Extended Range NI-46 board from being installed.
VII. ADDITIONAL INFORMATION
None.