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
May 16, 2018
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
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000483
License Number:
Report Number:
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
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
Number
Title
Revision
Or Date
Health Report Executive Summary - Cooling Water
Systems
February 6,
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
Using Gothic
EF-126
Drift Limit for Ultimate Heat Sink Cooling Tower Drift
Eliminators
MP 17-0012
Bypass Ultimate Heat Sink Fan Motor High Speed
Thermal Overloads
P170.0026
Maintenance Rule Walkdown Report - Essential
Service Water Pumphouse
July 31,
2013
PM 0825838
Procedures
(Number)
Title
Revision
APA-ZZ-00107
Review of Current Industry Operating Experience
21
APA-ZZ-00500
Corrective Action Program
068
APA-ZZ-00500 Appendix 2
Non-Conforming Materials Report
21
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
29
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
25
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
24
APA-ZZ-00500 Appendix 22 Corrective Action Program Definitions
017
APA-ZZ-01400 Appendix A
Callaway Self-Assessment and Benchmarking
Program
27
APA-ZZ-01400 Appendix E
Operating Experience
21
EDP-ZZ-04026
CFR Part 21 Evaluations
2
EDP-ZZ-06000
Vendor Equipment Technical Information Review
Program
018
FDP-ZZ-02001
Distribution, Review, and Processing of NRC
Generic Letters, Bulletins, Regulatory Issue
Summaries, and License Renewal Interim Staff
Guidance
015
LDP-ZZ-00500
Corrective Action Review Board
031
MTM-ZZ-QE001
Room Cooler Leak Location and Repair
006
ODP-ZZ-00001
Addendum 12
Operator Burdens and Workarounds
009
Condition Reports
201300989
201407444
201408380
201408399
201503391
201503621
201507752
201600287
201600448
201601916
201601918
201601936
201602417
201602427
201602454
201602455
201602456
201602475
201602658
201602811
201602825
201602855
201603297
201603312
201603321
201603472
201603473
201603522
201603581
201603598
201603640
201603819
201603844
201603910
201604242
201604282
201604299
201604301
201604473
201604936
201605178
201605289
201605488
201605499
201605506
201605517
201605592
201605700
201605725
201605917
201606075
201606132
Condition Reports
201606547
201606777
201606840
201606865
201606908
201606939
201607028
201607047
201607085
201607528
201607689
201607718
201607872
201607944
201608027
201608050
201608055
201608162
201608165
201608219
201608268
201608304
201608361
201608387
201608399
201608404
201608452
201608650
201608791
201608792
201608838
201608883
201609035
201609187
201609393
201700095
201700108
201700681
201700855
201700886
201700929
201700939
201700977
201701102
201701299
201701415
201701513
201701537
201701571
201701830
201701959
201702005
201702009
201702019
201702050
201702079
201702136
201702257
201702280
201702343
201702374
201702418
201702501
201702709
201702772
201702995
201703205
201703400
201703433
201703472
201703566
201703572
201703582
201703592
201703700
201703962
201703981
201704049
201704151
201704163
201704176
201704268
201704455
201704508
201704529
201704531
201704699
201704838
201704918
201704953
201705096
201705187
201705236
201705302
201705312
201705483
201705509
201705513
201705575
201705665
201705685
201705715
201705787
201705836
201705841
201705851
201705931
201705949
201705956
201706020
201706052
201706093
201706132
201706233
201706244
201706269
201706354
201706378
201706385
201706449
201706536
201706623
201706830
201706832
201706900
201707058
201707137
201707659
201707677
201800100
201800374
201800390
201800411
201800495
201800496
201800521
201800679
201800817
201800855
201800955
201801002
201801153
201801193
201801370
201801439
201801559
201801610*
201801631
201801640
201801740
201801837*
201801838*
201801847
- Issued as a result of inspection activities
Information Request
Biennial Problem Identification and Resolution Inspection Callaway Plant
January 23, 2018
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
SYSTEM
JOB
TASK
JOB
TYPE
COMPONENT
ID
JOB DESCRIPTION
BB
16002347
550
BBLY1311C
REPLACE NMD CARD DURING PERFORMANCE
OF ISL-BB-L1311
BB
10007881
500
BBHV8157A
Replace Valve BBHV8157A
BB
14006280
500
BB8949D
REPAIR CHECK VALVE (BB8949D)
BB
16001493
500
BBZS0455B
INVESTIGATE LIMIT SWITCH BBZS0455B
BB
16001542
500
BBHIS8002A INVESTIGATE no closed indication on
BBHIS8002A for BBHV8002A
BB
16003335
500
OA
RBB01
PERFORM N-1 WALKDOWNS OF STUCK
REACTOR STUD #18
Location:
BB
16004835
500
OA
BBFT0029HI BBFT0029HI, QC AGING MANAGEMENT VT-3
INSPECTION
BB
16004843
500
OA
BBPI0001I
BBPI0001I, QC AGING MANAGEMENT VT-3
INSPECTION
BB
18001328
500
OA
TBB03
PERFORM RCS LEAKRATE PER OSP-BB-00009
BB
15005089
500
BB-004-BCA Perform thermal fatigue inspections in accordance
with MRP-1
BB
05515129
500
BBPCV0455A DISASSEMBLE, INSPECT AND REASSEMBLE
VALVE
BB
10502588
500
BBT0411
Replace NR RCS Temperature Loop BBT0411
Printed Circuit Card
BB
10506356
500
BBHV8031
Replace Elastomeric Parts in BBHV8031
BB
10507447
500
BBHV8351CO INSPECT/SERVICE LIMITORQUE OPERATOR
BBHV8351C
BB
10507454
500
BBHV8351CO PERFORM MOV DIAGNOSTIC TEST ON
BBHV8351C
BB
10507549
500
BBHV8000AO PERFORM MOV DIAGNOSTIC TEST ON
BBHV8000AO
BB
14512862
500
BB8010A
REPLACE BB8010A WITH PRETESTED SPARE
BB
14513786
500
EBB01D
PERFORM UPPER INTERNALS INSPECTION -
EBB01D
BB
15512294
500
BBHS8000C
STROKE TEST BBHS8000C USING LOCAL
HANDSWITCH
BB
15512354
500
BBHV0013O LIMITORQUE GREASE INSPECTIONS Rx BLDG
A TRAIN
SYSTEM
JOB
TASK
JOB
TYPE
COMPONENT ID
JOB DESCRIPTION
KC
16001817
500
KCXSH0405
INVESTIGATE Open Circuit Trouble Alarm for Zone
405 1:ZN33
KC
16002304
500
KC274
INVESTIGATE KC274 INVERTER for FAILURE
TROUBLE
KC
16004471
500
KC273
INVESTIGATE KC273 INVERTER for FAILURE
ALARM on KC008
KC
18000090
500
KCXSH0219
REPLACE DUCT DETECTORS for ZONE
KCXSH0219
KC
16005163
500
OA
TKC1003BV1
PERFORM AGING MANAGEMENT PROGRAM
EXAMINATION OF TKC1003BV1
KC
14006468
500
KCV0057
CLEAN / REWORK VALVE TO CORRECT SEAT
LEAKAGE PROBLEM
KC
16507705
500
KC008
INSPECT & CLEAN INVERTER KC008
KC
16512498
500
KC
INSPECT FIRE EXTINGUISHERS
KC
18502118
500
KC
OPERATE EMERGENCY EQUIPMENT VEHICLE
AND FIRE PUMPER TRUCK
KC
17513591
500
RMT
KC
CONTROL ROOM EVACUATION EQUIPMENT
CHECK
NF
16001549
500
NF039C
REPLACE RELAY K1167
NF
14005287
500
OB
NF039A
Replace DV Transducers UV Power Supplies & all
circuit cards
NF
15005150
500
NF039BPSA1B
REPLACE & TEST 5VDC ATI POWER SUPPLY
(SHOP WORK)
NF
2502664
500
NFUQ5002A
REPLACE UV POWER SUPPLY: NFUQ5002A
LSELS Channel 3 PANEL NF0
NF
2502665
500
NFUQ5002B
REPLACE UV POWER SUPPLY: NFUQ5002B
LSELS Channel 3 PANEL NF0
NF
2502666
500
NFUQ5003A
REPLACE LSELS CHANNEL 4 UV POWER
SUPPLY: NFUQ5003A IN NF039A
NF
13504946
500
NFUQ5000B
REPLACE UV POWER SUPPLY NFUQ5000B
LSELS CHANNEL 1 PANEL NF03
NF
13505448
500
NFUQ5000A
REPLACE UV POWER SUPPLY NFUQ5000A
LSELS CHANNEL 1 PANEL NF03
NF
13513995
500
NFUQ5001A
REPLACE UV POWER SUPPLY NFUQ5001A
LSELS CHANNEL 2 PANEL NF03
NF
16503067
500
NF039B
SORENSEN POWER SUPPLY RIPPLE VOLTAGE
MEASUREMENT.
SYSTEM
JOB
TASK
JOB
TYPE
COMPONENT
ID
JOB DESCRIPTION
16001881
500
SP056A
RETURN GTRE0060 TO SERVICE AFTER
MONITOR DATABASE UNKNOWN IN
17001940
500
SP056A
SP056A LOSS OF RM11 SCREEN - IFIN
INVESTIGATION
16002085
500
SP056A
RM-11 COMMUNICATION LOOP
TROUBLESHOOTING
16004143
500
SP056A
INVESTIGATION OF COMMUNICATION ISSUES
BETWEEN RM11 AND PLANT
16001897
500
DL
SP056A
Investigate and repair RM-11C.
17001223
500
OA
SP056A
RM-11 COMMUNICATION LOOP
TROUBLESHOOTING
17003162
500
SP160B
REPAIR COMMUNICATION ISOLATION BOARD
13504662
500
SP01
COMPONENT REPLACEMENT AND TESTING FOR
SP01
15500479
500
SP01
CLEAN/INSPECT INVERTER SP01
16510532
500
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