IR 05000483/2018010
| ML18137A144 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/16/2018 |
| From: | Gerond George Division of Reactor Safety IV |
| To: | Diya F Union Electric Co |
| George G | |
| References | |
| IR 2018010 | |
| Download: ML18137A144 (20) | |
Text
SUBJECT:
CALLAWAY PLANT - NRC BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000483/2018010
Dear Mr. Diya:
On April 12, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at the Callaway Plant. The NRC inspection team discussed the results of this inspection with Mr. Tim Herrmann, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
The team reviewed the stations corrective action program and the stations implementation of the program. The team assessed the programs effectiveness in identifying, prioritizing, evaluating, and correcting problems, and whether the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team evaluated the stations processes for use of industry and NRC operating experience.
The team also evaluated the effectiveness of the stations audits and self-assessments program. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Gerond A. George, Team Leader Inspection Programs and Assessment Team Division of Reactor Safety Docket No. 50-483 License No. NPF-30 Enclosure:
Inspection Report 05000483/2018010 w/ Attachments:
1. Information Request dated January 23, 2018 2. Document Request dated April 4, 2018
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number: 05000483 License Number: NPF-30 Report Number: 05000483/2018010 Enterprise Identifier: I-2018-010-0054 Licensee: Union Electric Company Facility: Callaway Plant Location: Steedman, Missouri Inspection Dates: March 26, 2018, to April 12, 2018 Inspectors: H. Freeman, Senior Reactor Inspector D. Bradley, Senior Resident Inspector S. Alferink, PhD, Reactor Inspector C. Stott, Reactor Inspector Approved By: Gerond A. George, Team Leader Inspection Programs and Assessment Team Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at the Callaway Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified during the inspection.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - BASELINE
71152Problem Identification and Resolution Biennial Inspection
The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety-conscious work environment. The assessment is documented below.
- (1) Corrective Action Program Effectiveness: Problem Identification, Prioritization, Evaluation, and Corrective Actions - The inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards.
The sample included approximately 220 condition reports and 50 jobs (work orders).
This included an in-depth 5-year review of condition reports associated with the essential service water and ultimate heat sink systems.
- (2) Operating Experience, Self-Assessments, and Audits - The team evaluated the stations processes for use of industry and NRC operating experience. The team also evaluated the effectiveness of the stations audits and self-assessments program. The sample included 26 industry operating experience communications and associated site evaluations.
- (3) Safety-Conscious Work Environment - The team evaluated the stations safety-conscious work environment. The team interviewed station personnel and the employee concerns program manager. The team reviewed selected case files from the employee concerns program and sampled condition reports that had been anonymously submitted.
The sample included focus group interviews with approximately 40 individuals from 5 different working groups (engineering, fix-it-now, operations, mechanical maintenance, nuclear oversight, and security) and a review of the most recent safety culture survey.
Corrective Action Program Effectiveness Observation 71152Problem Identification and Resolution Effectiveness of Problem Identification: Overall, the team found that the licensee was identifying and documenting problems at an appropriately low threshold. During the 2-year assessment period, the licensee initiated slightly more than 14,000 condition reports.
However, the team did identify a few performance deficiencies that were administrative in nature that were not more-than-minor associated with problem identification. Specifically, during a review of 50 work orders, the team identified two examples where the licensee had documented issues in the work orders that were not captured in condition reports. In a third example, the team noted the licensee identified a condition that should have also been documented in a condition report, but failed to generate a condition report in a timely manner.
Each of these issues had been adequately addressed prior to the teams identification through the work order process. The team did not consider these examples to be indicative of a programmatic issue within the area of problem identification.
Effectiveness of Prioritization and Evaluation of Issues: Overall, the team found that the licensee was appropriately classifying and prioritizing conditions in accordance with established procedures. Of the 14,000 condition reports written during the assessment period, approximately 40 percent were classified as adverse conditions and handled accordingly. The team found that, where the corrective action procedure would have allowed a condition to be classified or prioritized at a lower level, the licensee typically classified issues at the higher level and took more conservative actions in developing cause evaluations. While most of the condition reports that the team reviewed were appropriately characterized as Adverse, the team identified a few examples where the condition reports were not classified correctly. For example, the team identified an example where the licensee had failed to classify a condition report associated with an NRC non-cited violation for a simulator fidelity issue as an adverse condition in accordance with their procedure. This error appeared to be caused by the timing of the finding because the issue was initially raised as a question which was appropriately documented as an Other Issue condition report and the licensee failed to upgrade or write a new condition report when it became clear that the issue represented a performance deficiency. In another example, the team found that the licensee had inappropriately classified a condition report as Other Issue to document the failure to implement an alternate method of shutting the equipment hatch because of an interference issue. Since the action to implement an alternate method of shutting the hatch was a corrective action for an adverse condition report, the condition report documenting the failure should have also been an adverse condition report. The handling of these condition reports as Other Issues did not adversely affect the corrective actions nor timeliness.
Effectiveness of Corrective Actions: Overall, the team concluded that the licensee identified effective corrective actions for the problems evaluated in the corrective action program. The licensee implemented these corrective actions in a timely manner, commensurate with their safety significance, and reviewed the effectiveness of the corrective actions appropriately.
However, a Notice of Violation issued during the assessment period indicates that continued diligence by the licensee was necessary in the area of corrective actions. This Notice of Violation was issued for the licensees failure to develop and implement adequate corrective actions associated for a failure previously identified by the NRC in 2014 to test engineered safety feature transformers load tap changer response times (05000483/2017007-01).
Corrective Action Program Assessment: Based on the samples reviewed, the team determined the licensees corrective action program complied with regulatory requirements and self-imposed standards, and the licensees implementation of the corrective action program adequately supported nuclear safety. The team found that managements oversight of the corrective action program process was effective. Corrective action program meetings (screening, leadership, and corrective action review board) thoroughly reviewed each condition report, and demonstrated that the members were properly prepared and engaged with the process.
Operating Experience, Self-Assessments, and Audits Observation 71152Problem Identification and Resolution Based on the samples reviewed, the team determined the licensee appropriately evaluated industry operating experience for its relevance to the facility. Operating experience information was incorporated into plant procedures and processes as appropriate.
The team further determined the licensee appropriately evaluated industry-operating experience when performing root cause analysis and apparent cause evaluations. The licensee appropriately incorporated both internal and external operating experience into lessons learned for training and pre-job briefs.
The team found that one of the strengths of the licensees corrective action program was associated with their willingness to be self-critical as evidenced in the thorough nature of their self-assessments and audits. The team found numerous examples of findings identified by the licensee and documented in the corrective action program including: overdue action items, trend for untimely updates to calculations, failure to perform a Part 21 evaluation for an Allen Bradley relay failure, and control building heating ventilation and air conditioning system pressure controllers being placed in manual without declaring the system to be inoperable.
The NRC reviewed these issues and determined them to be not more-than-minor in significance.
Safety-Conscious Work Environment Observation 71152Problem Identification and Resolution Based on interviews with plant staff and reviews of the latest safety culture survey results to assess the safety-conscious work environment, the team determined the licensee had established and maintained a healthy safety-conscious work environment. Employees appeared willing to raise nuclear safety concerns through at least one of the several means available. All of those interviewed had an adequate knowledge of the corrective action program process and would initiate a condition report, or work with someone who would do so on their behalf, if they knew of a safety concern.
A potential vulnerability was identified during the interviews associated with the licensees corrective action program system database interface. The licensee had replaced their in-house developed system with an externally developed system in September 2016 which was the subject of many focus group interviews. The new system did not perform all of the functions of the in-house developed system and was generally disliked by front-line individuals. Most individuals expressed difficulty in searching the database. Some members of one work group indicated that they believed they were expected to search the database prior to initiating a condition report, making it difficult to initiate a condition report. These individuals indicated they had raised safety concerns, and would continue to do so, either through the condition reporting process or through their chain-of-command. The team found that while the expressed difficulties with the user interface did not appear to have impacted the safety-conscious work environment, it represented an area where continued licensee management attention was warranted.
All plant personnel were aware of the Employee Concerns Program and most were willing to use it as an alternate avenue to raise concerns if required.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 12, 2018, the inspectors presented the biennial problem identification and resolution inspection results to Mr. T. Herrmann, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
71152Problem Identification and Resolution Biennial
Work Orders
16001349.915 17505255 11509170 14510038
13509339
Miscellaneous Documents Revision
Number Title Or Date
Health Report Executive Summary - Cooling Water February 6,
Systems 2018
System Health Report - Cooling Water Systems
2004-01120 Essential Service Water Hydraulic Model
AP17004 Nuclear Oversight Audit of Access Authorization June 26,
2017
EF-123 Ultimate Heat Sink Thermal Performance Analysis 2
Using Gothic
EF-126 Drift Limit for Ultimate Heat Sink Cooling Tower Drift 0
Eliminators
MP 17-0012 Bypass Ultimate Heat Sink Fan Motor High Speed 0
Thermal Overloads
P170.0026 Maintenance Rule Walkdown Report - Essential July 31,
Service Water Pumphouse 2013
PM 0825838
Procedures
(Number) Title Revision
APA-ZZ-00107 Review of Current Industry Operating Experience 021
APA-ZZ-00500 Corrective Action Program 068
APA-ZZ-00500 Appendix 2 Non-Conforming Materials Report 021
APA-ZZ-00500 Appendix 10 Trending Program
APA-ZZ-00500 Appendix 11 Degraded and Non-conforming Condition Resolution 009
APA-ZZ-00500 Appendix 12 Significant Adverse Condition - ADCN-1 029
APA-ZZ-00500 Appendix 13 Adverse Condition - ADCN-2 030
Procedures
(Number) Title Revision
APA-ZZ-00500 Appendix 14 Adverse Condition - ADCN-3 031
APA-ZZ-00500 Appendix 15 Adverse Condition - ADCN-4 025
APA-ZZ-00500 Appendix 16 Other Issue - OI-A 018
APA-ZZ-00500 Appendix 17 Screening Process Guidelines 035
APA-ZZ-00500 Appendix 19 Common Cause Evaluation 006
APA-ZZ-00500 Appendix 21 Other Issues - OI-B 024
APA-ZZ-00500 Appendix 22 Corrective Action Program Definitions 017
APA-ZZ-01400 Appendix A Callaway Self-Assessment and Benchmarking 027
Program
APA-ZZ-01400 Appendix E Operating Experience 021
EDP-ZZ-04026 10 CFR Part 21 Evaluations 012
EDP-ZZ-06000 Vendor Equipment Technical Information Review 018
Program
FDP-ZZ-02001 Distribution, Review, and Processing of NRC 015
Generic Letters, Bulletins, Regulatory Issue
Summaries, and License Renewal Interim Staff
Guidance
LDP-ZZ-00500 Corrective Action Review Board 031
MTM-ZZ-QE001 Room Cooler Leak Location and Repair 006
ODP-ZZ-00001 Operator Burdens and Workarounds 009
Addendum 12
Condition Reports
201300989 201602427 201603473 201604936
201407444 201602454 201603522 201605178
201408380 201602455 201603581 201605289
201408399 201602456 201603598 201605488
201503391 201602475 201603640 201605499
201503621 201602658 201603819 201605506
201507752 201602811 201603844 201605517
201600287 201602825 201603910 201605592
201600448 201602855 201604242 201605700
201601916 201603297 201604282 201605725
201601918 201603312 201604299 201605917
201601936 201603321 201604301 201606075
201602417 201603472 201604473 201606132
Condition Reports
201606547 201700886 201704151 201706378
201606777 201700929 201704163 201706385
201606840 201700939 201704176 201706449
201606865 201700977 201704268 201706536
201606908 201701102 201704455 201706623
201606939 201701299 201704508 201706830
201607028 201701415 201704529 201706832
201607047 201701513 201704531 201706900
201607085 201701537 201704699 201707058
201607528 201701571 201704838 201707137
201607689 201701830 201704918 201707659
201607718 201701959 201704953 201707677
201607872 201702005 201705096 201800100
201607944 201702009 201705187 201800374
201608027 201702019 201705236 201800390
201608050 201702050 201705302 201800411
201608055 201702079 201705312 201800495
201608162 201702136 201705483 201800496
201608165 201702257 201705509 201800521
201608219 201702280 201705513 201800679
201608268 201702343 201705575 201800817
201608304 201702374 201705665 201800855
201608361 201702418 201705685 201800955
201608387 201702501 201705715 201801002
201608399 201702709 201705787 201801153
201608404 201702772 201705836 201801193
201608452 201702995 201705841 201801370
201608650 201703205 201705851 201801439
201608791 201703400 201705931 201801559
201608792 201703433 201705949 201801610*
201608838 201703472 201705956 201801631
201608883 201703566 201706020 201801640
201609035 201703572 201706052 201801740
201609187 201703582 201706093 201801837*
201609393 201703592 201706132 201801838*
201700095 201703700 201706233 201801847
201700108 201703962 201706244
201700681 201703981 201706269
201700855 201704049 201706354
- Issued as a result of inspection activities
Information Request
Biennial Problem Identification and Resolution Inspection Callaway Plant
January 23, 2018
Inspection Report: 05000483/2018010
On-site Inspection Dates: Weeks of March 26 and April 9, 2018
Assessment Period: March 25, 2016, through April 13, 2018
This inspection will cover the period from March 25, 2016, through the end of the onsite
inspection. The scope of this request is information associated with activities during this
inspection period unless otherwise specified. To the extent possible, the requested information
should be provided electronically in word-searchable Adobe PDF (preferred) or Microsoft Office
format. Any sensitive information should be provided in hard copy during the teams first week
on site; do not provide any sensitive or proprietary information electronically.
Lists of documents (summary lists) should be provided in Microsoft Excel or a similar sortable
format. Please be prepared to provide any significant updates to this information during the
teams first week of on-site inspection. As used in this request, corrective action documents
refers to condition reports, notifications, action requests, cause evaluations, and/or other similar
documents.
Please provide the following information no later than March 5, 2018:
1. Document Lists
Note: For these summary lists, please include the document/reference number, the
document title, initiation date, current status, and long-text description of the issue.
a. Summary list of all corrective action documents related to significant conditions
adverse to quality that were opened, closed, or evaluated during the period
b. Summary list of all corrective action documents related to conditions adverse to
quality that were opened or closed during the period
c. Summary lists of all corrective action documents that were upgraded or
downgraded in priority/significance during the period (these may be limited to
those downgraded from, or upgraded to, apparent-cause level or higher)
d. Summary list of all corrective action documents initiated during the period that
roll up multiple similar or related issues, or that identify a trend
e. Summary lists of operator workarounds, operator burdens, temporary
modifications, and control room deficiencies (1) currently open and (2) that were
evaluated and/or closed during the period
f. Summary list of safety system deficiencies that required prompt operability
determinations (or other engineering evaluations) to provide reasonable
assurance of operability
g. Summary list of plant safety issues raised or addressed by the Employee
Concerns Program (or equivalent) (sensitive information should be made
available during the teams first week on sitedo not provide electronically)
2. Full Documents with Attachments
Note: Please include a summary list or index if document titles are not descriptive.
a. Root Cause Evaluations completed during the period; include a list of any
planned or in progress
b. Apparent Cause Evaluations completed during the period
c. Quality Assurance audits performed during the period
d. Audits/surveillances performed during the period on the Corrective Action
Program, of individual corrective actions, or of cause evaluations
e. Functional area self-assessments and non-NRC third-party assessments (e.g.,
peer assessments performed as part of routine or focused station self- and
independent assessment activities; do not include INPO assessments) that
were performed or completed during the period; include a list of those that are
currently in progress
f. Any assessments of the safety-conscious work environment
g. Corrective action documents generated during the period associated with the
following:
i. NRC findings and/or violations
ii. Licensee Event Reports issued by Callaway Plant
h. Corrective action documents generated for the following, if they were
determined to be applicable to Callaway Plant (for those that were evaluated
but determined not to be applicable, provide a summary list):
i. NRC Information Notices, Bulletins, and Generic Letters issued or
evaluated during the period
ii. Part 21 reports issued or evaluated during the period
iii. Vendor safety information letters (or equivalent) issued or evaluated
during the period
iv. Other external events and/or Operating Experience evaluated for
applicability during the period
i. Corrective action documents generated for the following:
i. Emergency planning drills and tabletop exercises performed during the
period
ii. Maintenance preventable functional failures that occurred or were
evaluated during the period
iii. Action items generated or addressed by offsite review committees
during the period
iv. Findings, violations, and comments/observations documented in the
2015 NRC PI&R inspection report
3. Logs and Reports
a. Corrective action performance trending/tracking information generated during
the period and broken down by functional organization (if this information is fully
included in item 3.b, it need not be provided separately)
b. Current system health reports, Management Review Meeting package, or
similar information; provide past reports as necessary to include 12 months of
metric/trending data
c. Radiation protection event logs during the period
d. Security event logs and security incidents during the period (sensitive
information should be made available during the teams first week on sitedo
not provide electronically)
e. List of training deficiencies, requests for training improvements, and simulator
deficiencies for the period
Note: For items 3.c and 3.d, if there is no log or report maintained separate from the
corrective action program, please provide a summary list of corrective action program
items for the category described.
4. Procedures
Note: For these procedures, please include all revisions that were in effect at any time
during the period.
a. Corrective action program procedures, to include initiation and evaluation
procedures, operability determination procedures, apparent and root cause
evaluation/determination procedures, and any other procedures that implement
the corrective action program
b. Quality Assurance program procedures (specific audit procedures are not
necessary)
c. Employee Concerns Program (or equivalent) procedures
d. Procedures that implement/maintain a Safety-Conscious Work Environment
e. Conduct of Operations procedure (or equivalent) and any other procedures or
policies governing control room conduct, operator burdens and workarounds,
etc.
f. Operating Experience (OE) program procedures and any other procedures or
guidance documents that describe the sites use of OE information
5. Other
a. List of risk-significant components and systems, ranked by risk worth
b. List of structures, systems, and components and/or functions that were in
maintenance rule (a)(1) status at any time during the inspection period; include
dates and results of expert panel reviews and dates of status changes
c. Organization charts for plant staff and long-term/permanent contractors
d. Electronic copies of the UFSAR (or equivalent), technical specifications, and
technical specification bases, if available
e. Table showing the number of corrective action documents (or equivalent)
initiated during each month of the inspection period, by screened significance
f. For each day the team is on site,
i. Planned work/maintenance schedule for the station
ii. Schedule of management or corrective action review meetings (e.g.
operations focus meetings, condition report screening meetings, CARBs,
MRMs, challenge meetings for cause evaluations, etc.)
iii. Agendas for these meetings
Note: The items listed in 5.f may be provided on a weekly or daily basis after the
team arrives on site.
All requested documents should be provided electronically where possible. Regardless of
whether they are uploaded to an internet-based file library (e.g., Certrecs IMS), please provide
copies on CD or DVD. One copy of the CD or DVD should be provided to the resident inspector
at Callaway Plant; and one additional copy should be provided to the team lead, to arrive no
later than March 5, 2018:
U.S. NRC Region IV
Attn: Harry Freeman
1600 E. Lamar
Arlington, TX 76011
PAPERWORK REDUCTION ACT STATEMENT
This request does not contain new or amended information collection requirements subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by
the Office of Management and Budget, control number 3150-0011.
Document Request
April 4, 2018
JOB COMPONENT
SYSTEM JOB TASK JOB DESCRIPTION
TYPE ID
REPLACE NMD CARD DURING PERFORMANCE
BB 16002347 550 CC BBLY1311C
OF ISL-BB-L1311
BB 10007881 500 DC BBHV8157A Replace Valve BBHV8157A
BB 14006280 500 DC BB8949D REPAIR CHECK VALVE (BB8949D)
BB 16001493 500 DC BBZS0455B INVESTIGATE LIMIT SWITCH BBZS0455B
BB 16001542 500 DC BBHIS8002A INVESTIGATE no closed indication on
BBHIS8002A for BBHV8002A
PERFORM N-1 WALKDOWNS OF STUCK
BB 16003335 500 OA RBB01 REACTOR STUD #18
Location:
BB 16004835 500 OA BBFT0029HI BBFT0029HI, QC AGING MANAGEMENT VT-3
INSPECTION
BBPI0001I, QC AGING MANAGEMENT VT-3
BB 16004843 500 OA BBPI0001I
INSPECTION
BB 18001328 500 OA TBB03 PERFORM RCS LEAKRATE PER OSP-BB-00009
Perform thermal fatigue inspections in accordance
BB 15005089 500 OM BB-004-BCA
with MRP-1
DISASSEMBLE, INSPECT AND REASSEMBLE
BB 05515129 500 PM BBPCV0455A
VALVE
Replace NR RCS Temperature Loop BBT0411
BB 10502588 500 PM BBT0411
Printed Circuit Card
BB 10506356 500 PM BBHV8031 Replace Elastomeric Parts in BBHV8031
INSPECT/SERVICE LIMITORQUE OPERATOR
BB 10507447 500 PM BBHV8351CO
BBHV8351C
PERFORM MOV DIAGNOSTIC TEST ON
BB 10507454 500 PM BBHV8351CO
BBHV8351C
PERFORM MOV DIAGNOSTIC TEST ON
BB 10507549 500 PM BBHV8000AO
BBHV8000AO
BB 14512862 500 PM BB8010A REPLACE BB8010A WITH PRETESTED SPARE
PERFORM UPPER INTERNALS INSPECTION -
BB 14513786 500 PM EBB01D
EBB01D
STROKE TEST BBHS8000C USING LOCAL
BB 15512294 500 PM BBHS8000C
HANDSWITCH
LIMITORQUE GREASE INSPECTIONS Rx BLDG
BB 15512354 500 PM BBHV0013O
A TRAIN
JOB
SYSTEM JOB TASK COMPONENT ID JOB DESCRIPTION
TYPE
INVESTIGATE Open Circuit Trouble Alarm for Zone
KC 16001817 500 CC KCXSH0405
405 1:ZN33
INVESTIGATE KC274 INVERTER for FAILURE
KC 16002304 500 DC KC274
TROUBLE
INVESTIGATE KC273 INVERTER for FAILURE
KC 16004471 500 DC KC273
ALARM on KC008
KC 18000090 500 DC KCXSH0219 REPLACE DUCT DETECTORS for ZONE
KCXSH0219
PERFORM AGING MANAGEMENT PROGRAM
KC 16005163 500 OA TKC1003BV1 EXAMINATION OF TKC1003BV1
KC 14006468 500 OM KCV0057 CLEAN / REWORK VALVE TO CORRECT SEAT
LEAKAGE PROBLEM
KC 16507705 500 PM KC008 INSPECT & CLEAN INVERTER KC008
KC 16512498 500 PM KC INSPECT FIRE EXTINGUISHERS
OPERATE EMERGENCY EQUIPMENT VEHICLE
KC 18502118 500 PM KC AND FIRE PUMPER TRUCK
KC 17513591 500 RMT KC CONTROL ROOM EVACUATION EQUIPMENT
CHECK
NF 16001549 500 DC NF039C REPLACE RELAY K1167
Replace DV Transducers UV Power Supplies & all
NF 14005287 500 OB NF039A
circuit cards
NF 15005150 500 OR NF039BPSA1B REPLACE & TEST 5VDC ATI POWER SUPPLY
(SHOP WORK)
REPLACE UV POWER SUPPLY: NFUQ5002A
NF 12502664 500 PM NFUQ5002A LSELS Channel 3 PANEL NF0
REPLACE UV POWER SUPPLY: NFUQ5002B
NF 12502665 500 PM NFUQ5002B LSELS Channel 3 PANEL NF0
REPLACE LSELS CHANNEL 4 UV POWER
NF 12502666 500 PM NFUQ5003A SUPPLY: NFUQ5003A IN NF039A
REPLACE UV POWER SUPPLY NFUQ5000B
NF 13504946 500 PM NFUQ5000B LSELS CHANNEL 1 PANEL NF03
REPLACE UV POWER SUPPLY NFUQ5000A
NF 13505448 500 PM NFUQ5000A LSELS CHANNEL 1 PANEL NF03
REPLACE UV POWER SUPPLY NFUQ5001A
NF 13513995 500 PM NFUQ5001A LSELS CHANNEL 2 PANEL NF03
NF 16503067 500 PM NF039B SORENSEN POWER SUPPLY RIPPLE VOLTAGE
MEASUREMENT.
JOB COMPONENT
SYSTEM JOB TASK JOB DESCRIPTION
TYPE ID
RETURN GTRE0060 TO SERVICE AFTER
SP 16001881 500 CC SP056A MONITOR DATABASE UNKNOWN IN
SP 17001940 500 CC SP056A SP056A LOSS OF RM11 SCREEN - IFIN
INVESTIGATION
SP 16002085 500 DC SP056A RM-11 COMMUNICATION LOOP
TROUBLESHOOTING
INVESTIGATION OF COMMUNICATION ISSUES
BETWEEN RM11 AND PLANT
SP 16001897 500 DL SP056A Investigate and repair RM-11C.
RM-11 COMMUNICATION LOOP
SP 17001223 500 OA SP056A
TROUBLESHOOTING
SP 17003162 500 OR SP160B REPAIR COMMUNICATION ISOLATION BOARD
COMPONENT REPLACEMENT AND TESTING FOR
SP01
SP 15500479 500 PM SP01 CLEAN/INSPECT INVERTER SP01
SP 16510532 500 PM SP01 CLEAN/INSPECT INVERTER SP01
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002
By: HAF Yes No Publicly Available Sensitive
OFFICE SRI:IPAT SRI:PBB RI:EB1 RI:EB2 C:PBB ATL:IPAT
NAME HFreeman DBradley CStott SAlferink NTaylor GGeorge
SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/
DATE 05/07/18 05/07/18 05/09/18 05/08/18 05/16/18 05/16/18