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NRC Integrated Inspection Report 05000482/2017001
	ML17132A257
Person / Time
Site:	Wolf Creek
Issue date:	05/12/2017
From:	Dixon J L; NRC/RGN-IV/DRP/RPB-B
To:	Heflin A C; Wolf Creek
	JOHN DIXON
References
	IR 2017001
	Download: ML17132A257 (37)
	v • d • e

May 12, 2017

Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839

SUBJECT: WOLF CREEK GENERATING STATION

- NRC INTEGRATED INSPECTION REPORT 05000482/2017 00 1

Dear Mr. Heflin:

On March 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Wolf Creek Generating Station

. On May 2, 2017

, the NRC inspectors discussed the results of this inspection with M r. Stephen Smith, Plant Manager

, and other members of your staff. The results of this inspection are documented in the enclosed report.

NRC inspectors documented one finding of very low safety significance (Green) in this report. This finding involved a violation of NRC requirements

. The NRC is treating th is violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of th e NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555

-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC resident inspector at the Wolf Creek Generating Station

. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555

-0001; with copies to the Regional Administrator, Region IV; and the NRC resident inspector at the Wolf Creek Generating Station

. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011

-4511 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/

John L. Dixon, Branch Chief Project Branch B Division of Reactor Projects Docket No.

50-482 License No

.: NPF-42

Enclosure:

Inspection Report 05000 482/2017001 w/

Attachment:

Supplemental Information

SUNSI Review By: JDixon ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE SRI/DRP/B ASRI/DRP/B RI/DRP/B C:DRS/EB1 C:DRS/EB2 C:DRS/OB NAME DDodson MLangelier FThomas TFarnholtz GWerner VGaddy SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 5/3/2017 5/8/2017 05/03/2017 05/04/2017 05/04/2017 5/3/2017 OFFICE C:DRS/PSB2 TL:DRS/IPAT SRI/DRP/C SPE:DRP/B BC:DRP/B NAME HGepford THipschman PVoss DProulx JDixon SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ DATE 05/04/2017 5/4/2017 5/9/2017 5/4/2017 5/12/2017 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000 482 License: NPF-42 Report: 05000 482/20 17 0 01 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: 1550 Oxen Lane NE Burlington, KS 66839 Dates: January 1, 2017

, through March 31, 2017 Inspectors:

D. Dodson, Senior Resident Inspector M. Langelier, P.E., Acting Senior Resident Inspector F. Thomas, Resident Inspector J. Drake, Senior Reactor Engineer P. Elkmann, Senior Emergency Preparedness Inspector D. Proulx, Senior Project Engineer P. Voss, Senior Resident Inspector, Coop er Approved By: John L. Dixon Chief, Project Branch B Division of Reactor Projects

2

SUMMARY

IR 05000 482/20 17 0 01; 01/0 1/20 17 - 03/31/20 17; Wolf Creek Generating Station

Maintenance Effectiveness The inspection activities described in this report were performed between January 1 and March 31, 2017 , by the resident inspectors at Wolf Creek Generating Station and inspectors from the NRC's Region IV office. One finding of very low safety significance (Green)is documented in this report. This finding involved a violation of NRC requirements

. The significance of inspection findings is indicated by their color (i.e., Green , greater than Green, White, Yellow, or Red), determined using Inspection Manual Chapter 0609, "Significance Determination Process," dated April 29, 2015. Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects within the Cross-Cutting Areas," dated December 4, 2014. Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy.

The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG

-1649, "Reactor Oversight Proce ss ," dated July 2016.

Cornerstone: Mitigating Systems

Green.

The inspectors reviewed a Green, self-revealed non-cited violation of Technical Specification 5.4.1.a and Regulatory Guide 1.33 for the licensee's failure to provide adequate work instructions for preventive maintenance on safety-related equipment. Specifically, work instructions to inspect and clean the condensate drain lines on the class 1E air conditioner air handling units lacked guidance for adequately cleaning the drain line. This caused the unit to become non-functional. The licensee took the immediate corrective action to clear the clogged condensate drain line on SGK05B, and entered the issue in the corrective action program as Condition Report 106416. The failure to provide adequate work instructions for preventive maintenance on safety-related equipment is a performance deficiency.

This performance deficiency is more than minor, and therefore a finding, because it is associated with the procedure quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). In accordance with NRC Inspection Manual Chapter 0609, Appendix A, Exhibit 2, "Mitigating Systems Screening Questions," the inspectors determined this finding screened to Green

. The inspectors determined that the finding has a problem identification and resolution cross-cutting aspect of resolution because the organization did not take effective corrective actions to address issues in a timely manner commensurate with their safety significance. This issue is indicative of current performance because neither the preventive maintenance change process was substantively changed nor were human performance errors associated with the preventive maintenance change corrected, and the same resolution inadequacies that resulted in the inadequate preventive maintenance instructions would be expected to occur

[P.3]. (Section 1R1 2)3

PLANT STATUS

Wolf Creek Generating Station began the inspection period operating at full power. On February 9, 2017, operators reduced power to approximately 82 percent to complete planned main turbine valve cycle testing. Plant power was restored to approximately full power on February 10, 2017, and the plant operated at

, or near , full power for the rest of the period.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1 R 01 Adverse Weather Protection (71111.01) Summer Readiness for Offsite and Alternate A C Power Systems

a. Inspection Scope

On March 10, 2017, the inspectors completed an inspection of the station's off

-site and alternate-alternating current (AC) power systems.

The inspectors inspected the material condition of these systems, including transformers and other switchyard equipment to verify that plant features and procedures were appropriate for operation and continued availability of off

-site and alternate

-AC power systems. The inspectors reviewed outstanding and open condition reports for these systems

. The inspectors walked down the switchyard to observe the material condition of equipment providing off-site power sources.

The inspectors verified that the licensee's procedures included appropriate measures to monitor and maintain availability and reliability of the off

-site and alternate

-AC power systems. These activities constitute d one sample of summer readiness of off-site and alternate

-AC power systems , as defined in Inspection Procedure 71111.01.

b. Findings

No findings were identified. 1 R 04 Equipment Alignment (71111.04)

.1 Partial Walk

-Down

a. Inspection Scope

The inspectors performed partial system walk

-downs of the following risk

-significant systems: January 24, 2017 , safety injection pump B February 22, 2017, emergency diesel generator B

The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the trains were correctly aligned for the existing plant configuration. These activities constitute d two partial system walk

-down sample s as defined i n Inspection Procedure 71111.04.

b. Findings

No findings were identified.

.2 Complete Walk

-Down

a. Inspection Scope

On January 24, 2017, the inspectors performed a complete system walk-down inspection of the residual heat removal pump B. The inspectors reviewed the licensee's procedures and system design information to determine the correct system lineup for the existing plant configuration. The inspectors also reviewed outstanding, open condition reports, temporary modifications

, and other open items tracked by the licensee's operations and engineering departments.

The inspectors then visually verified that the system was correctly aligned for the existing plant configuration.

These activities constitute d one complete system walk

-down sample , as defined in Inspection Procedure 71111.04.

b. Findings

No findings were identified.

1 R 05 Fire Protection (71111.05) Quarterly Inspection

a. Inspection Scope

The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on seven plant areas important to safety

January 23, 2017 , fire areas A

-21 and A-22, control room air

-conditionin g and filtration units, elevation 2

, 047 fee t February 2 4, 2017, fire areas ESWA and ESWB, essential service water pump house, elevation 2

,000 feet February 28, 2017, fire area A

-33, auxiliary feedwater piping, valves, and instrumentation room

, elevation 1 , 98 9 feet March 6 , 2017, circulating water screen house floor area, elevation 2,000 feet March 9 , 2017, station blackout diesel generator enclosure floor area, elevation 2,000 feet March 15, 2017, fire areas A-17 and A-18, electrical penetration rooms A and B , elevation 2 , 026 feet March 29, 2017, fire area A

-23, main steam and feedwater valve compartment, elevation 2,047 feet For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions.

These activities constitute d seven quarterly inspection sample s , as defined in Inspection Procedure 71111.05.

b. Findings

No findings were identified.

1 R 07 Heat Sink Performance (71111.07)

a. Inspection Scope

On January 25, 2017 , and February 22, 2017, respectively, the inspectors completed an inspection of the readiness and availability of risk

-significant heat exchangers. The inspectors observed performance tests, reviewed the data from the performance test s , verified the licensee used the industry standard periodic maintenance method outlined in EPRI NP-7552, and verified the material condition for the train A spent fuel pool pump room cooler and train A emergency diesel generator jacket water heat exchanger.

The inspectors also verified that both the train A spent fuel pool pump room cooler and train A emergency diesel generator jacket water heat exchangers were correctly categorized under the Maintenance Rule and were receiving the required maintenance.

These activities constitute d completion of two heat sink performance annual review sample s , as defined in Inspection Procedure 71111.07.

b. Findings

No findings were identified.

1 R 11 Licensed Operator Requalification Program and Licensed Operator Performance (71111.11)

.1 Review of Licensed Operator Requalification

a. Inspection Scope

On March 1, 2017, the inspectors observed an evaluated simulator scenario performed by an operating crew. The inspectors assessed the performance of the operators and the evaluators' critique of their performance. The inspectors also assessed the modeling and performance of the simulator during the evaluated simulator scenario

. These activities constitute d completion of one quarterly licensed operator requalification program sample , as defi ned in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

.2 Review of Licensed Operator Performance

a. Inspection Scope

On March 20, 2017, the inspectors observed the performance of on

-shift licensed operators in the plant's main control room. At the time of the observations, the plant was in a period of heightened risk due to chemical and volume control system inservice check valve testing and associated reactivity manipulations

.

In addition, the inspectors assessed the operators' adherence to plant procedures, including AP 21-001, "Conduct of Operations," Revision 79, and other operations department policies.

These activities constitute d completion of one quarterly licensed operator performance sample , a s defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

1 R 12 Maintenance Effectiveness (71111.12) Routine Maintenance Effectiveness

a. Inspection Scope

The inspectors reviewed two instances of degraded performance or condition of safety-significant structures, systems, and components (SSCs):

January 3 0, 2017 , NF039B load shedding and emergency load sequencing cabinet, undervoltage power supplies found out of tolerance on ripple voltage checks February 1, 2017, containment cooler fan D motor control circuit, failed contactor The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensee's corrective actions. The inspectors reviewed the licensee's work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensee's characterization of the degradation in accordance with 10 CFR 50.65 (the Maintenance Rule), and verified that the licensee was appropriately tracking degraded performance and conditions in accordance with the Maintenance Rule.

These activities constituted completion of two maintenance effectiveness sample s, as defined in Inspection Procedure 71111.12.

b. Findings

Introduction.

The inspectors reviewed a Green, self-revealed non-cited violation of Technical Specification 5.4.1.a and Regulatory Guide 1.33 for the licensee's failure to provide adequate work instructions for preventive maintenance on safety

-related equipment. Specifically, work instructions to inspect and clean the condensate drain line on the train B class 1E air conditioner air handling unit lacked adequate guidance to clean the drain line. This resulted in the train B class 1E air conditioning unit becoming non-functional

.

Description.

On August 15, 2016, at 4:33 a.m., the train B class 1E air conditioning unit (SGK05B) was declared non

-functional when an operator discovered water on the floor near the air handling unit where one would not normally expect such a condition. This water was determined to be from condensate that had accumulated within the air handling unit and was leaking out of an access door seal. The condensate within the air handling unit had accumulated enough to wet the bottom of the fan motor within the unit. The direct cause of the accumulation of condensation in this air handling unit was determined to be a clogged condensate drain line. This line was cleared using pressurized water, the station started the unit for post maintenance testing on August 15, 2016, at 10:59 p.m., and the unit was declared functional at 11:35 a.m., on August 16, 2016. Prior to this occurrence, on August 7, 2016, at 3:52 a.m., the train A control room air conditioning unit (SGK04A) was declared inoperable due to the discovery of condensation accumulating inside the air handling unit for this air conditioner. This issue was initially found by the operator on rounds when the operator noted the absence of water dripping from the condensate drain line as it normally does during operation. The condensation within the air handling unit had accumulated enough to wet the bottom of the fan motor. The direct cause of the accumulation of condensate within the air handling unit was determined to be a partially clogged condensate drain line. During

operation, a small vacuum is created within the air handling unit and this vacuum, coincident with a partially clogged drain line, prevented condensate from draining from the unit. This line was partially cleared using pressurized water and the unit was de clared operable at 5:50 p.m. on August 7, 2016. Inspectors challenged the licensee on their assessment that the unit was operable and not degraded due to only partially clearing the drain line. The licensee agreed, and revised their operability determination to operable but degraded.

As part of a basic cause evaluation completed in September 2016, the licensee determined that the condensate drain lines had clogged on these units several times in the past and had also occurred on the train B control room air conditioning unit (SGK04B). A total of twelve incidents since 1998 were reported.

Initial corrective actions in 1998, implemented a preventive maintenance strategy for the control room air conditioning units and the class 1E air conditioning units for their condensate drain lines. This preventive maintenance activity did not initially provide guidance to check the drain lines for obstructions. In July 2000, after the train A control room air conditioning unit experienced a clogged condensate drain line, the preventive maintenance instructions were updated to request maintenance personnel to pour one gallon of water down the drain line to verify adequate drainage flow. However, these instructions did not include guidance on what was an acceptable flow rate.

In 2008, after continuing to have issues with clogging condensate drain lines, the preventive maintenance instructions were updated to require disassembly of the drain lines by maintenance personnel to inspect and thoroughly clean the drain lines.

The ability to disassemble the condensate drain line was only possible on SGK05A due to a threaded union being present in the drain line. The other three units; SGK05B, SGK04A, and SGK04B, did not have a threaded union in the drain line. Because of this, a recommendation was made in 2012 to change the preventive maintenance instructions. The preventive maintenance instructions for the other three units were subsequently essentially reverted to the previous instructions that utilized the flushing water technique and did not require the lines to always be cleaned, even though the preventive maintenance tasks had previously been changed in 2008 to resolve ongoing issues. The licensee's basic cause evaluation determined that the most probable cause of the collection of debris in the condensate drain lines was lack of guidance in the preventive maintenance work instructions to adequately clean the drain lines to determine if blockage s exist and to remove them. The inspectors questioned whether any substantive changes to the preventive maintenance change process had occurred subsequent to 2012 or if any new actions were planned, and the inspectors questioned whether any corrective actions had been taken or were planned related to any human performance issues associated with the inadequate preventive maintenance change in 2012. The licensee confirmed that neither previous nor planned actions addressed the programmatic or human performance issues that resulted in inadequate resolution of the inadequate preventiv e maintenance task issue. As a result, the issue is indicative of current performance, and the licensee documented Condition Report 112754 to address the inspectors' concerns.

The licensee entered this issue into its corrective action program as Condition Reports 106262 , 106416, and 112754. Condition Report 106416 documented completion of actions to improve the preventive maintenance work instructions to require the use of pressure (air and/or water) to clean/purge the condensate drain lines.

Analysis.

The failure to provide adequate work instructions for preventive maintenance on safety-related equipment is a performance deficiency. Th is performance deficiency is more than minor, and therefore a finding, because it is associated with the procedure quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage).

Specifically, work instructions for preventive maintenance on the condensate drain line for SGK05B were inadequate

, and as a result, SGK05B condensate drain lines became clogged and SGK05B was declared non

-functional

. The inspectors evaluated the finding using Exhibit 2, "Mitigating Systems Screening Questions," of Inspection Manual Chapter 0609, Appendix A, "Significance Determination Process (SDP) for Findings At

-Power," issued June 19, 2012, and determined this finding is not a deficiency affecting the design or qualification of a mitigating SSC that maintained its operability or functionality; the finding does not represent a loss of system and/or function; the finding does not represent an actual loss of function of at least a single train for greater than its technical specification

-allowed outage time; and the finding does not represent an actual loss of function of one or more non-technical specification trains of equipment designated as high safety

-significant for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, the inspectors determined the finding was of very low safety significance (Green).

The inspectors determined that the finding has a problem identification and resolution cross-cutting aspect in the area of resolution because the organization did not take effective corrective actions to address issues in a timely manner commensurate with their safety significance. Specifically, in 2012 the preventive maintenance instructions for the SGK05B, SGK04A, and SGK04B units, which were created in 2008 to address continuing condensate drain line clogging issues, were essentially reverted back to the previous inadequate instructions. This issue is indicative of current performance because neither the preventive maintenance change process was substantively changed

nor were human performance errors associated with the preventive maintenance change corrected, and the same resolution inadequacies that resulted in the inadequate preventive maintenance instructions would be expected to occur

[P.3].

Enforcement.

Technical Specification 5.4.1.a requires, in part, that procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

Section 9.a of Appendix A to Regulatory Guide 1

.33 , Revision 2, requires, in part, that "maintenance that can affect the performance of safety

-related equipment should be properly pre-planned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the ci rcumstances."

The licensee established Procedure AP 1 6B-003, "Planning and Scheduling Preventive Maintenance," which provides direction for implementing the preventive maintenance program to meet the Regulatory Guide 1.33 requirement. Section 6.2 of Procedure AP 16B

-003 requires, in part, that preventive maintenance activities be developed by considering, in part, equipment history, operating experience, and component functional importance. Contrary to the above, until December 15, 2016, preventive maintenance activities were not developed by adequately considering equipment history, operating experience, and component functional importance. Specifically, preventive maintenance activity 28380 for cleaning and inspecting the drain line on SGK05B, an activit y affecting quality, was not appropriate to the circumstance s. As a result, the train B class 1E air conditioning unit (SGK05B) was declared non

-functional on August 15, 2016. The licensee took the immediate corrective action to clear the clogged condensate drain line on SGK05B and has completed corrective action s to improve the preventive maintenance instructions. The licensee entered this issue into the corrective action program as Condition Reports 106262 , 106416 , and 112754. This violation is being treated as an NCV, consistent with Section 2.3.2.a of the Enforcement Policy

NCV 05000482/201 7 00 1-01, "Failure to Provide Adequate Work Instructions for Preventive Maintenance

."

1 R 13 Maintenance Risk Assessments and Emergent Work Control (71111.13)

a. Inspection Scope

The inspectors reviewed three risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:

January 23, 2017 , planned maintenance for train A control room air

-conditioning unit and train A safety injection pump January 31

, 2017, planned maintenance for train B essential service water pump and train B emergency diesel generator February 21 and 22, 2017, planned 7-day maintenance window f or train A emergency diesel generator The inspectors verified that these risk assessment s were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessment s and verified that the licensee implemented appropriate risk management actions based on the result of the assessment s. Additionally, on January 17, 2017, the inspectors also observed portions of steam generator atmospheric relief valve A controller replacement emergent work activities that had the potential to affect the functional capability of mitigating systems

. The inspectors verified that the licensee appropriately developed and followed a work plan for these activities. The inspectors verified that the licensee took precautions to minimize the impact of the work activities on unaffected SSCs.

These activities constitute d completion of four maintenance risk assessments and emergent work control inspection sample s , as defined in Inspection Procedure 71111.13.

b. Findings

No findings were identified.

1 R 15 Operability Determinations and Functionality Assessments (71111.15)

a. Inspection Scope

The inspectors reviewed five operability determinations and evaluations that the licensee performed for degraded or nonconforming SSCs:

December 22, 2016, evaluation of train A hydrogen analyzer containment isolation valves in an abnormal line

-up January 11, 2017, evaluation of unit vent planned maintenance February 27, 2017, operability determination of increased reactor coolant system xenon ratio and total noble gas activity February 27, 2017, operability determination of B motor

-driven auxiliary feedwater pump inboard bearing oil sample results with increased phosphorus March 14 , 2017, operability determination of postulated tornado generated missile impact on A and B train emergency diesel generator truck connections The inspectors reviewed the timeliness and technical adequacy of the licensee's evaluations.

Where the licensee determined the degraded SSC to be operable, t he inspectors verified that the licensee's compensatory measures were appropriate to provide reasonable assurance of operability. The inspectors verified that the licensee had considered the effect of other degraded conditions on the operability of the degraded SSC

. These activities constitute d completion of five operability and functionality review sample s , as defined in Inspection Procedure 71111.15.

b. Finding s No findings were identified. 1 R 19 Post-Maintenance Testing (71111.19)

a. Inspection Scope

The inspectors reviewed six post-maintenance testing activities that affected risk

-significant SSCs:

January 23, 2017 , train A control room air conditioning unit planned maintenance February 2, 2017, train B containment cooler fan D motor contactor replacement February 7, 2017, train B motor-driven auxiliary feedwater pump planned maintenance February 22, 2017 , train B emergency diesel generator planned maintenance February 28, 2017, turbine-driven auxiliary feedwater pump planned maintenance March 28, 2017, train A motor-driven auxiliary feedwater pump and valve planned maintenance The inspectors reviewed licensing- and design

-basis documents for the SSCs and the maintenance and pos t-maintenance test procedures.

The inspectors observed the performance of the post

-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs.

These activities constitute d completion of six post-maintenance testing inspection sample s , as defined in Inspection Procedure 71111.19.

b. Findings

No findings were identified.

1 R 22 Surveillance Testing (71111.22)

a. Inspection Scope

The inspectors observed seven risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the SSCs were capable of performing their safety functions:

In-service test s: January 19, 2 017 , STS MT-079, "A [Essential Service Water] Vacuum Breaker Valve Inservice Test

," Revision February 16, 2017, STS EF

-100A, "[Essential Service Water]

System Inservice Pump A & [Essential Service Water]

A Check Valve Test," Revision 46B March 27, 2017, STS EN-101A, "Containment Spray Pump A Comprehensive Pump Test," Revision 14 Other surveillance tests:

February 10, 2017

, STS AC-001, "Main Turbine Cycle Test

," Revision 53 February 15, 2017, STS IC

-530D, "Wide Range Temperature and Wide Range Pressure Instrumentation Protection Set 1 Channel Calibration," Revision February 24, 2017, STS JE

-001A, "Emergency Diesel Generator Fuel Oil System Train A Test," Revision 12 March 16, 2017, STS EN

-101B, "Containment Spray Pump B Comprehensive Pump Test," Revision 14 The inspectors verified that these test s met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the test satisfied appropriate acceptance criteria. The inspectors verified that the licensee restored the operability of the affected SSCs following testing.

These activities constitute d completion of seven surveillance testing inspection sample s , as defined in Inspection Procedure 71111.22.

b. Findings

No findings were identified.

Cornerstone:

Emergency Preparedness 1 EP 4 Emergency Action Level and Emergency Plan Changes (71114.04)

a. Inspection Scope

The inspector performed an in

-office review of AP 002, "Radiological Emergency Response Plan," Revision 18A, implemented November 29 , 2016. This revision:

Revised the definitions and descriptions of radiation dosimetry throughout the Plan Corrected minor typographical and administrative errors This revision was compared to its previous revision, to the criteria of NUREG

-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Revision 1, and to the standards in 10 CFR 50.47(b) to determine if the revision adequately implemented the requirements of 10 CFR 50.54(q)(3) and 50.54(q)(4). The inspector verified that the revision did not decrease the effectiveness of the emergency plan. This review was not documented in a safety evaluation report and did not constitute approval of licensee-generated changes; therefore, this revision is subject to future inspection.

These activities constitute completion of one emergency action level and emergency plan changes sample as defined in Inspection Procedure 71114.04.

b. Findings

No findings were identified.

1 EP 6 Drill Evaluation (71114.06)

Training Evolution Observation

a. Inspection Scope

On March 1 and 9, 2017 , the inspectors observed simulator

-based licensed operator requalification training that included implementation of the licensee's emergency plan. The inspectors verified that the licensee's emergency classifications, off

-site notifications, and protective action recommendations were appropriate and timely. The inspectors verified that any emergency preparedness weaknesses were appropriately identified by the evaluators and entered into the corrective action program for resolution.

These activities constitute d completion of one training observation sample , as defined in Inspection Procedure 71114.06.

b. Findings

No findings were identified.

OTHER ACTIVITIES

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security 4OA 1 Performance Indicator Verification (71151)

.1 Unplanned Scrams per 7000 Critical Hours (IE01)

a. Inspection Scope

The inspectors reviewed licensee event reports (LERs) for the period of January 1, 2016, through December 31, 2016, to determine the number of scrams that occurred. The inspectors compared the number of scrams reported in these LERs to the number reported for the performance indicator. Additionally, the inspectors sampled operating logs to verify the number of critical hours during the period.

The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the data reported.

These activities constituted verification of the unplanned scrams per 7000 critical hour s performance indicator

, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.2 Unplanned Power Changes per 7000 Critical Hours (IE03)

a. Inspection Scope

The inspectors reviewed operating logs and corrective action program records for the period of January 1, 2016, through December 31, 2016, to determine the number of unplanned power changes that occurred. The inspectors compared the number of unplanned power changes documented to the number reported for the performance indicator. Additionally, the inspectors sampled operating logs to verify the number of critical hours during the period. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the data reported.

These activities constituted verification of the unplanned power changes per 7000 critical hours performance indicator, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.3 Unplanned Scrams with Complications (IE04)

a. Inspection Scope

The inspectors reviewed the licensee's basis for including or excluding in this performance indicator each scram that occurred between January 1, 2016, through December 31, 2016. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the data reported.

These activities constitute d verification of the unplanned scrams with complications performance indicator

, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

4OA 2 Problem Identification and Resolution (71152) Routine Review

a. Inspection Scope

Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's condition report screening meetings. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with t he significance of the problems identified.

The inspectors also reviewed the licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.

b. Findings

No findings were identified.

4OA 5 Other Activities Temporary Instruction 2515/192, "Inspection of the Licensee's Interim Compensatory Measures Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems

."

a. Inspection Scope

The objective of this performance based Temporary Instruction was to verify implementation of interim compensatory measures associated with an open phase condition design vulnerability in electric power systems for operating reactors. The inspectors conducted an inspection to determine if the licensee implemented the following interim compensatory measures. These compensatory measures are to remain in place until permanent automatic detection and protection schemes are installed and declared operable for the open phase condition design vulnerability. The inspectors verified the following:

The licensee identified and discussed with plant staff the lessons

-learned from the open phase condition events at the U.S. operating plants including the Byron Station open phase condition and its consequences. This included conducting operator training for promptly diagnosing, recognizing consequences, and responding to an open phase condition.

The licensee updated plant operating procedures to help operators promptly diagnose and respond to open phase conditions on off

-site power sources credited for safe shutdown of the plant.

The licensee established and implemented periodic walkdown activities to inspect switchyard equipment such as insulators, disconnect switches, and transmission line and transformer connections associated with the off

-site power circuits to detect a visible open phase condition.

The licensee ensured that routine maintenance and testing activities on switchyard components have been implemented and maintained.

As part of the maintenance and testing activities, the licensee assessed and managed plant risk in accordance with 10 CFR 50.65(a)(4) requirements.

b. Findings

No findings were identified.

4OA 6 Meetings, Including Exit

Exit Meeting Summary

On March 22, 2017, the inspector conducted a telephonic exit meeting to present the results of the in-office inspection of changes to the licensee's emergency plan to Mr. T. East, Superintendent, Emergency Planning, and other members of the licensee staff. The licensee acknowledged the issues presented.

On March 23, 2017, the inspectors presented the final inspection results to Mr. C. Reasoner, Site Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. No proprietary information was identified.

On May 2, 2017 , the inspectors presented the inspection results to M r. S. Smith , Plant Manager , and other members of the licensee staff. The licensee acknowledged the issues presented.

The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

J. Ashley, Supervisor, System Engineering

R. Audano, Superintendent, Maintenance

R. Ayers, Supervisor, Radiation Protection

T. Baban, Manager, System Engineering

W. Brandt, Shift Manager

J. Cuffe, Supervisor, Radiation Protection

T. East, Superintendent, Emergency Planning

J. Edwards, Manager, Operations

R. Fincher, Manager, Quality

R. French, Supervisor, Radiation Protection

J. Fritton, Oversight

G. Fugate, Director, Plant Support

N. Good, Licensing Engineer

C. Gross, Manager, Chemistry

C. Hafenstine, Manager, Regulatory Affairs

D. Hall, Manager, Strategic Projects

A. Heflin, President and Chief Executive

Officer

P. Herrman, Manager, Design Engineering

R. Hobby, Licensing Engineer

J. Isch, Superintendent, Operations Work Controls

J. Knust, Licensing

Engineer

R. Lane, Manager, Corrective Action Program

B. Lee, Licensed Supervising Instructor

D. Mand, Manager, System Engineering

J. McCoy, Vice President, Engineering

W. Muilenburg, Supervisor Licensing

L. Ratzlaff, Manager, Maintenance

C. Reasoner, Site Vice President

M. Skiles, Manager, Security

T. Slenker, Supervisor, Operations Support

S. Smith, Plant Manag

er

L. Stone, Licensing Engineer

A. Stull, Vice President and Chief Administrative Officer

J. Suter, Supervisor, Fire Protection

M. Tate, Superintendent, Security Operations

J. Yunk, Manager, Training

NRC Personnel

D. Loveless, Senior Reactor Analyst

C. Smith, Reactor Inspector, Engineering Branch 1

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

05000 482/2017001-01 NCV Failure to Provide Adequate Work Instructions for Preventive Maintenance

(Section 1R12) Closed 2515/192 TI Inspection of the Licensee's Interim Compensatory Measures Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems

(Section 4OA5)

LIST OF DOCUMENTS REVIEWED

Section 1 R 01:

Adverse Weather Protection

Procedures

Number Title Revision

OFN

AF-025 Unit Limitations

SYS

SY-120 Sharpe Diesel Operation and Alignment to Site

Drawings

Number Title Revision

KD-7496 One Line Diagram

SK7458_AC05

Wolf Creek 345KV Substation No. 7 Transformer Diff. [Differential] Currents Diagram 0

Condition Reports

46940

102586

108547

109469

111538

111636

Miscellaneous

Number Title Date 2017-005 Wolf Creek Substation Work Authorization; TX

OPD [Open Phase Detection] PMT [Post Maintenance Test] Troubleshooting (energized)

March 9 , 2017 2017-007 Wolf Creek Substation Work Authorization; OPD [Open Phase Detection] A/C [Air

-Conditioner] replacement March 9 , 2017 2017-008 Wolf Creek Substation Work Authorization; OPD [Open Phase Detection]

Data Recorder March 9 , 2017

Miscellaneous

Number Title Date 2017-0111 Control Room Risk Assessment Log/Work Schedule; Risk Assessment Dates

- March 6, 2017, through March 12, 2017 February 13, 2017

Section 1R04: Equipment Alignment

Procedures

Number Title Revision

AI 16 F-001 Evaluation of Boric Acid Leakage

AI 16F-002 Boric Acid Leakage Management

CKL

EM-120 Safety Injection System Lineup Check Lists

CKL

JE-120 Emergency Fuel Oil System Lineup

CKL

KJ-121 Diesel Generator NE

and

NE 02 Valve Checklist

STS

EJ-100 A RHR [Residual Heat Removal] System Inservice Pump A Test 52 STS

PE-007 Periodic Verification of Motor Operated Valves

STS

VT-001 Verification of OMN

-1, MOV Exercise Requirements

SYS

EJ-320 Placing RHR System in Safety Injection Standby Condition

Drawings

Number Title Revision

EID-0 018 P&ID System Composite System BG, BN, EM, EJ, EP

M-12

EJ 01 Piping and Instrumentation Diagram Residual Heat Removal System

M-12EM01 Piping & Instrumentation Diagram High Pressure Coolant Injection System

M-12

JE 01 Piping & Instrumentation Diagram Emergency Fuel Oil System 19 M-12

KJ 04 Piping & Instrumentation Diagram Standby Diesel Generator "B" Cooling Water System, Sheet

18 M-12

KJ 05 Piping & Instrumentation Diagram Standby Diesel Generator "B" Intake Exhaust, F.O. & Start Air Sys.

M-12KJ06 Piping & Instrumentation Diagram Standby Diesel Generator "B" Lube Oil System

Condition Reports

57026 97111 99337

103970

109541

111208

111237

111357

Miscellaneous

Number Title Date

AIF 16 F-001 Boric Acid Leakage Screening/Evaluation

- PEJ0 1 B November 14 , 2009

APF 25 A-700-01 Temporary Shielding Request (TSR#

13-086) January 14 , 2013

APF 25 A-700-01 Temporary Shielding Request (TSR#

14-086) February 19 , 2014

APF 25 A-700-01 Temporary Shielding Request (TSR#

15-086) February 10 , 2015

APF 25A-700-01 Temporary Shielding Request (TSR#

16-086) September

, 2016 EJ System Health Report, Residual Heat Removal July 1, 2016

, through December 31, 2016

Section 1R05: Fire Protection

Procedures

Number Title Revision

AP 10-102 Control of Combustible Materials

AP 10-103 Fire Protection Impairment Control

AP 10-106 Fire PrePlans

AP 14A-003 Scaffold Construction and Use

Drawings

Number Title Revision

E-1F9905 Fire Hazards Analysis

Condition Reports

71910

111332

111427

111489

111539

111546

111693

111708

Miscellaneous

Number Title Revision/Date 2017-008 Transient Combustible Materials Permit February 23, 2017

APF 10-103-01 Fire Protection Impairment Control Permit

APF 10-103-04 Hourly Fire Watch Permit Log; February

23, 2017 through March 6, 2017

XX-X-004 Calculation Number

XX-X-004 Engineering Evaluation Section 1R0

7:

Heat Sink Performance

Procedures

Number Title Revision

STS

EF-100A ESW System In service Pump A and ESW A Check Valve Test 46B SYS

EF-200 Operation of the ESW System

Drawings

Number Title Revision

M-12KJ01 Piping & Instrumentation Diagram Standby Diesel Generator "A" Cooling Water System

M-612C-00025 Aerofin Maintenance Instructions for Aerofin Coils

W02 M-612C-00028 Type "R" Coil, 13 Tube Face

- Carrier Replacement, 6 Row

- 4 Pass, Left Hand

W03

Condition Reports

110613

Work Orders

16-412518-000 16-413219-007

Miscellaneous

Number Title Date

Balance of Plant Eddy Current Examination

- EKJ06A February 21, 2017 EPRI

NP-7552 Heat Exchanger Performance Monitoring Guidelines December 1991

Miscellaneous

Number Title Date

GG-01 Maintenance Rule Final Scope Evaluation, Fuel Building HVAC System

- GG-01

Section 1R11: Licensed Operator Requalification Program

Procedures

Number Title Revision

AP 21-001 Conduct of Operations

SYS

BG-201 Shifting Charging Pumps

A STS

BG-210 CVCS Inservice Check Valve Test

Condition Reports

110940

111365 111764

Section 1R12: Maintenance Effectiveness

Procedures

Number Title Revision

AI 28A-023 Evaluation of Maintenance Rule Functional Failure CRs

AP 16 B-003 Planning and Scheduling Preventive Maintenance

STS

IC-208B 4KV Loss of Voltage & Degraded Voltage TADOT NB02 BUS - SEP GRP 4 4E

Condition Reports

106262

106416

111360

112754

Work Orde rs 16-415474-00 0

Miscellaneous

Number Title Date

GN-01 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-01

GN-02 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-02

Miscellaneous

Number Title Date

GN-03 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-03

GN-04 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-04

GN-05 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-05

GN-06 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-06

GN-07 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-07

GN-08 Maintenance Rule Final Scope Evaluation, Containment Cooling System

-

GN-0 8

NF System Health Report , Load Shedding

& Emergency Load Sequencing July 1, 2016

, through December 31, 2016

NF-01 Maintenance Rule Final Scope Evaluation, Load Shedding & Emergency Load Sequencing System

-

NF-01

NF-02 Maintenance Rule Final Scope Evaluation, Load Shedding & Emergency Load Sequencing System

-

NF-02

NF-03 Maintenance Rule Final Scope Evaluation, Load Shedding & Emergency Load Sequencing System

-

NF-03

PIR 77552 Functional Failure Determination Checklist January 15 , 2014

PIR 77555 Functional Failure Determination Checklist February 25, 2014

PIR 77901 Functional Failure Determination Checklist February 26 , 2014

PIR 80710 Functional Failure Determination Checklist May 13 , 2014

PIR 80711 Functional Failure Determination Checklist May 13 , 2014

PIR 80746 Functional Failure Determination Checklist May 13 , 2014

PIR 81809 Functional Failure Determination Checklist November 6 , 2014

PIR 82231 Functional Failure Determination Checklist May 15 , 2014

PIR 82989 Functional Failure Determination Checklist May 14 , 2014

Miscellaneous

Number Title Date

PIR 89850 Functional Failure Determination Checklist January 7 , 2015

PIR 91851 Functional Failure Determination Checklist March 21 , 2015

PIR 94058 Functional Failure Determination Checklist May 1 , 2015

PIR 95765 Functional Failure Determination Checklist May 19, 2015

PIR 95845 Functional Failure Determination Checklist May 4 , 2015

PIR 110725 Functional Failure Determination Checklist March 9 , 2017

Section 1R13: Maintenance Risk Assessment and Emergent Work Controls

Procedures

Number Title Revision

AI 22C-013 Protected Equipment Program

AI 22 C-014 TSEO [Technical Specification Equipment Outage] Management

AP 10-106 Fire Preplans

AP 14 A-003 Scaffold Construction and Use

AP 22C-003 On-Line Nuclear Safety and Generation Risk Assessment

AP 22C-007 Risk Management and Contingency Planning

AP 22 C-008 Qualitative Risk Management

STS

IC-616A Slave Relay Test K616 Train A Safety Injection

STS

IC-616B Slave Relay Test K616 Train B Safety Injection

STS

NB-005 Breaker Alignment Verification

SYS

SY-120 Sharpe Diesel Operation and Alignment To Site

Drawings

Number Title Revision

M-12EF01 Piping & Instrumentation Diagram Essential SVC [Service]

Water System

M-12EF02 Piping & Instrumentation Diagram Essential Service Water System 42

Drawings

Number Title Revision

M-12

EG 01 Piping & Instrumentation Diagram Component Cooling Water System

M-12

EG 02 Piping & Instrumentation Diagram Component Cooling Water System

M-12KJ04 Piping & Instrumentation Diagram Standby Diesel Generator "B" Cooling Water System

Condition Reports

110469

110470

111205

111234

111235

Miscellaneous

Number Title Date 13-S 0041 WCGS Scaffolding Request February 28 , 2013 2017-0104 On-Line Nuclear Safety and Generation Risk Assessment

Risk Assessment Dates

- January 16, 2017, through January 22, 2017

January 17, 2017 2017-0105 On-Line Nuclear Safety and Generation Risk Assessment

Risk Assessment Dates

- January 23, 2017, through January 29, 2017

January 5, 2017 2017-0106 On-Line Nuclear Safety and Generation Risk Assessment

Risk Assessment Dates

- January 30, 2017, through February 5, 2017

December 20, 2016 2017-0109 On-Line Nuclear Safety and Generation Risk Assessment; Risk Assessment Dates

- February 20 to February

, 2017 January 31 , 2017

Section 1R15:

Operability Evaluati ons Procedures Number Title Revision

AI 26 C-004 Technical Specification Application for Containment Isolation Valves 6 C

AP 16-003 Master Lubrication List and Control of Lubricants

AP 19 B-001 Failed Fuel Action Plan

AP 26 C-004 Operability Determination and Functionality Assessment

Procedures

Number Title Revision

AP 28-001 Operability Evaluations

I-ENG-004 Lubricating Oil Analysis

STS

AL-212 MD AFP Comprehensive Pump Testing, Flow Path Verification & CV Testing

STS

GG-001 A Emergency Exhaust Filtration System Train A Operability Test 23 STS

GS-201 A Containment H

System Train A Inservice Valve Test

A STS

GS-201 B Containment H

System Train B Inservice Valve Test

STS

GS-202 Containment H

Syste m Position Indication Test

SYS

GG-200 Fuel Building Emergency Exhaust Operations

Drawings

Number Title Revision

J-02GS03(Q) Control Logic Diagram Hydrogen Analyzer Containment Isolation Valves

M-12

GG 01 Piping and Instrumentation Diagram Fuel Building HVAC

M-12

GS 01 Piping and Instrumentation Diagram Containment Hydrogen Control System

M-12

JE 01 Piping & Instrumentation Diagram Emergency Fuel Oil System 19

Condition Reports

PIR 00-0804

PIR 01-0683

PIR 05-0063

PIR 99-1978

111233

111259

111261

111366

111419

111624

111625

111795

111974

112131

Work Orders

11-346333-000 15-402258-000 16-410322-000 16-411630-000

Miscellaneous

Number Title Revision/Date

PAL 01B Vibe Data

11-28-16 and 2-7-17.txt November 28 , 2016, to March 6 , 2017 2 017-02 Condition Report

00111419 ODM Documentation Form March 7, 2017 7052 Fyrquel EHC Safety Data Sheet

C21 D-GT-N-007 Clearance Order for Outside Air Inlet Tornado Damper

C21 D-GT-N-008 Clearance Order for Containment Purge HVAC System

C22 D-GS-B-002 Clearance Order for Hydrogen Analyzer

C22 D-GS-B-002 A Clearance Order for Hydrogen Analyzer

CGD 002-E0011 Fyrquel EHC Electro

-Hydraulic Control Fluid

CGD 002-P 0041 Exxon Mobil DTE

2 Lubricating Oil Excel File Weekly Trends Cycle

2.xlsx Various Dates

PAL 01 B Aux Feedwater Pump

-B Outboard Predictive Maintenance Lab Report August 24 , 2016

UIN 012 AD 8 A Aux Feedwater Pump B

-Out Tribology Report February 21 , 2017

UIN 039 D 50 C New Oil Baseline for Mobil DTE

March 7 , 2017

UIN 03 F 220 F

SHC 824 New Oil August 26 , 2014

UIN 05 B 7 B 75 New Oil Fryquel March 2 , 2017

Section 1R19:

Post

-Maintenance Testing

Procedures

Number Title Revision/Date

AI-23D-003 MOV Trending and Periodic Verification Program

MPE

NE-003 Governor Adjustments for

Emergency Diesel Generator NE01 13 STN

AL-201 Auxiliary Feedwater System Valve Test

STS

AL-101 MDAFW Pump A Inservice Pump Test

A

Procedures

Number Title Revision/Date

AI-23D-003 MOV Trending and Periodic Verification Program

STS

GK-002A Control Room A/C [Air-Conditioning] Unit Operability Test

STS

GN-001 Containment Cooling Fans Operability Test

STS

PE-007 Periodic Verification of MOVs (ALHV0011) December 30 , 2013 STS

PE-007 Periodic Verification of MOVs (ALHV0011) July 29 , 2015 STS

PE-007 Periodic Verification of MOVs (ALHV0011) March 28 , 2017 STS

PE-007 Periodic Verification of MOVs (ALHV003

1) March 28 , 2017 SYS

GN-120 Containment Cooling System Operation

SYS

KJ-123 Post Maintenance Run of Emergency Diesel Generator A

SYS

KJ-125 EDG Starting Air Compressor Operation

Drawings

Number Title Revision

E-13

GN 02 Schematic Diagrams Containment Cooler Fans A & C

E-13

GN 02 A Schematic Diagrams Containment Cooler Fans B & D

E-018-00852 SZ. 5 2SP

- 1WD Schematic MCC Cubicles:

NG02TAF1, NG04TAF1 W12 E-018-00853 Wiring Diagram 2SP 1WD (Size 5) MCC Cubicles NG02TAF1, NG04TAF1

W13 M-1H1521 Heating, Ventilating, & Air Cond. Auxiliary Building EL.

2047'-6" AREA 2 9 M-12AL01 P&ID Auxiliary Feedwater System

M-12

GK 01 Piping & Instrumentation Diagram Control Building H.V.A.C [Heating, Ventilation, and Air

-Conditioning]

M-12

GK 02 Piping & Instrumentation Diagram Control Building HVAC

M-12

GK 03 Piping & Instrumentation Diagram Control Building H.V.A.C

M-13

GK 01 Small Piping Isometric Room Coolers and Compressors Vents and Drains

- Aux. [Auxiliary] Bldg. [Building]

Condition Reports

106416

107185

110725

110763

110885

Condition Reports

110927

111173

111956

112026

Work Orders

15-405362-000 15-405970-000 15-409029-007 16-411723-020 16-414721-000 16-418029-001 16-418068-001 16-418068-002 17-422333-000 17-422333-002 17-422333-003

Miscellaneous

Number Title Revision/Date

Online Nuclear Safety and Generation Risk Assessment Protected Equipment List

- Motor Driven Auxiliary Feedwater Pump A TSEO

March 28, 2017

AL-M-007 Thrust/Torque Calculation for Valves ALHV0005, ALHV0007, ALHV0009, and ALHV00011

SYS

KJ-123 Post Maintenance Run of Emergency Diesel Generator A

Completed on February 22, 2017

Section 1R22: Surveillance Testing

Procedures

Number Title Revision

ALR 00-089 C DG

NE 01 Day TK LEV LO

AP 15 C-004 Preparation, Review and Approval of Procedures, Instructions and Forms

AP 21-001 Conduct of Operations

STN

AP-102 NSAFP Full Flow Test

STN

IC-467 A Channel Calibration Emergency Fuel Oil Day Tank, TJE

2A, Level Loop JE LPL

-0001 2 A STS

AC-001 Main Turbine Valve Cycle Test 53 STS

EF-100A EWS System Inservice Pump A & ESW A Check Valve Test

46B STS

EN-101 A Containment Spray Pump A Comprehensive Pump

STS

EN-101 B Containment Spray Pump B Comprehensive Pump Test

STS

IC-447 Channel Calibration Nuclear Instrumentation System Power Range Incore

-Excore 42 STS

IC-530 D Channel Calibration Wide Range Temperature and Wide Range Pressure Instrumentation Protection Set One

Procedures

Number Title Revision

STS

IC-530 D Wide Range Temperature and Wide Range Pressure Instrumentation Protection Set 1 Channel Calibration

STS

JE 001 A Emergency Diesel Generator fuel Oil System Train A Test

STS

JE-003 A Diesel Generator NE

Day Tank Water Removal

A STS

JE-004 A Emergency Fuel Oil Storage Tank Water Check/Removal

STS

MT-079 ESW System Water Hammer Inservice Check Valve Test

SYS

OMT-001 Operations Monthly Tasks

Drawings

Number Title Revision

10466-M-761-2025-04 Interconnecting Wiring Diagram Cabinet 01 SNUPPS Nuclear Power Plant Controls

W04 10466-M-761-2026 Interconnecting Wiring Diagram Cabinet 01 SNUPPS Nuclear Power Plant Controls

W 06 10466-M-761-2275 Interconnecting Wiring Diagram Cab. 01 SNUPPS Nuclear Power Plant Controls

W05 M-12

JE 01 Piping & Instrumentation Diagram Emergency Fuel Oil System 19 M-12JE01 Piping & Instrumentation Diagram Standby Diesel Generator "A" Intake Exhaust. F. O. & Start. Air Sys.

M-761-02322

Interconnection Wiring Diagram Cab 01 SNUPPS Nuclear Power Plant Controls

W02 M-761-02029 Interconnecting Wiring Diagram Cabinet 01 SNUPPS Nuclear Power Plant Controls W 07

Condition Reports

101760

101943

110568

111000

111044

111045

111168

Work Orders

15-407404-000 15-407404-008 16-414579-000 16-415563-000 16-415563-001 16-415907-000

Miscellaneous

Number Title Revision/Date

OPS Archive Log February 14, 2017 , through February 16, 2017

APF 05-013-01 M-223F-00003 Crispin Model VR

-41 Relief Check Valve Flanged Ends Size Fig. 150-VR December 29, 2016

APF 05-024-01 Minor Change Package

- ESW Water Hammer Vacuum Breaker Valves Spring Replacement

APF 15 C-004-09 Administrative Correction

- Wide Range Temperature and Wide Range Pressure Instrumentation Protection Set Channel Calibration February 16 , 2017

APF 21-001-02 On-Coming CRS/WC SRO/RO/BOP Review February 9, 2017

APF 22 C-008-01 Qualitative Risk Screening

- STS

IC-447 December 28 , 2016

APF 22 C-008-01 Qualitative Risk Screening

- STS

IC-530 D December 29 , 2016