IR 05000483/2016001

Callaway Plant - NRC Integrated Inspection Report 05000483/2016001

ML16130A822
Person / Time
Site:	Callaway
Issue date:	05/09/2016
From:	Taylor N H NRC/RGN-IV/DRP/RPB-B
To:	Diya F Union Electric Co
Taylor N H
References
IR 2016001
Download: ML16130A822 (38)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511 May 9, 2016 Mr. Fadi Diya, Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251

SUBJECT: CALLAWAY PLANT

- NRC INTEGRATED INSPECTION REPORT 05000483/2016001

Dear Mr. Diya,

O n March 31 , 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Callaway Plant. On April 6, 2016 , the NRC inspectors discussed the results of this inspection with Mr. Tim E. Herrmann, Site Vice President, and other members of your staff.

Inspectors documented the results of this inspection in the enclosed inspection 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 this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the NRC Enforcement Policy.

If you contest the violation or significance of this 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, U.S. Nuclear Regulatory Commission, Washington, DC 20555

-0001; and the NRC resident inspector at the Callaway Plant

. If you disagree with the cross-cutting aspect assignment, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC resident inspector at the Callaway Plant

.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC

's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Document s Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Nicholas H. Taylor , Chief Project Branch B Division of Reactor Projects Docket No. 50

-483 License No. NPF

-30

Enclosure:

Inspection Report 05000483/2016001 w/

Attachment:

Supplemental Information

ML16130A82 2 SUNSI Review By: NHT ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE SRI/DRP/B RI/DRP/B C:DRS/PSB1 C:DRS/PSB2 C:DRS/EB1 C:DRS/EB2 NAME THartman MLangelier MHaire HGepford TFarnholtz GWerner SIGNATURE /RA-E/ /RA-E/ /RA/ /RA/ /RA/ /RA/ DATE 5/2/16 5/2/16 4/25/16 4/25/16 4/25/16 4/25/16 OFFICE RI/DRS/EB2 RI/DRP/A PE/DRP/B PE/DRP/D SPE/DRP/B SRI/DRS/EB1 NAME SAlferink DBradley SJanicki JMelfi DProulx WSifre SIGNATURE /RA-E/ /RA-E/ /RA-E/ /RA/ /RA/ /RA-E/ DATE 4/26/16 4/26/16 4/26/16 4/25/16 5/2/16 4/26/16 OFFICE TL:IPAT C:DRS/OB C:DRP/B NAME THipschman VGaddy NTaylor SIGNATURE /RA/ /RA/ /RA/ DATE 4/25/16 4/25/16 5/9/16 Letter to Fadi Diya from Nicholas H. Taylor dated May 9, 2016

SUBJECT: CALLAWAY PLANT

- NRC INTEGRATED INSPECTION REPORT 05000483/2016001 DISTRIBUTION

Regional Administrator (Marc.Dapas@nrc.gov)

Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)

DRP Deputy Director (Ryan.Lantz@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Thomas.Hartman@nrc.gov) Resident Inspector (Michael.Langelier@nrc.gov) Branch Chief, DRP/B (Nick.Taylor@nrc.gov) Senior Project Engineer, DRP/B (David.Proulx@nrc.gov

) Project Engineer, DRP/B (Shawn.Money@nrc.gov)

Project Engineer, DRP/B (Steven.Janicki@nrc.gov)

CWY Administrative Assistant (Dawn.Yancey@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov

) Project Manager (John.Klos@nrc.gov) Team Leader, DRS/IPAT (Thomas.Hipschman@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov

) ACES (R4Enforcement.Resource@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov

) Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)

RIV/ETA: OEDO (Jeremy.Bowen@nrc.gov) ROPreports.Resource@nrc.gov ROPassessment.Resource@nrc.gov Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000483 License: NPF-30 Report: 05000483/2016001 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Steedman, MO Dates: January 1 through March 31, 2016 Inspectors:

T. Hartman, Senior Resident Inspector M. Langelier, P.E., Resident Inspector S. Alferink, Reactor Inspector D. Bradley, Resident Inspector , Columbia Generating Station P. Elkmann, Senior Emergency Preparedness Inspector S. Janicki, Project Engineer J. Melfi, Project Engineer D. Proulx, Senior Project Engineer W. Sifre, Senior Reactor Inspector Approved By:

Nicholas H. Taylor Chief, Project Branch B Division of Reactor Projects

SUMMARY

IR 05000483/2016001; 01/01/2016

- 03/31/2016; Callaway Plant , Flood Protection Measures The inspection activities described in this report were performed between January and March 31, 2016, by the resident inspectors at the Callaway Plant 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 (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609, "Significance Determination Process." Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects within the Cross-Cutting Areas." 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 Process."

Cornerstone: Mitigating Systems

Green.

The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," for the licensee's failure to perform an adequate operability determination for safety related components located in the 1988 foot auxiliary building train B piping penetration room (room 1203) based on degraded internal flooding drain capability. Specifically, the immediate operability determination included incorrect assumptions that were not verified to support th e operability determination as required by Procedure ODP-ZZ-00001, Addendum 15, "Operability and Functionality Determinations

," Revision 8. The immediate corrective action was to implement a compensatory measure to support operability of the equipment in room 1203. The issue was place d in the corrective action program as Callaway Action Request 201601412.

The licensee's failure to verify assumptions used in the immediate operability determination and ensure a sound basis for operability exists per plant procedures was a performance deficiency. The performance deficiency is more than minor, and therefore a finding, because it is similar to examples 3.j and 3.k in Inspection Manual Chapter 0612, Appendix E, "Examples of Minor Issues," and if left uncorrected, it has the potential to lead to a more significant safety concern. Specifically, failure to perform adequate operability evaluations by verifying assumptions and ensuring a sound basis for operability exists may result in the failure to enter the appropriate limiting conditions of operation for technical specification equipment.

Using Inspection Manual Chapter 0609, Appendix A, Exhibit 2, "Mitigating Systems Screening Questions," the finding involved the degradation of equipment specifically designed to mitigate a flooding initiating event, therefore, Exhibit 4, "External Events Screening Questions," was used to complete the screening. The finding was determined to need a detailed risk evaluation because if the equipment (i.e.

, floor drain lines) is assumed to be completely failed or unavailable, it would degrade one or more trains of a system that supports a risk significant system or function. In consultation with the Senior Reactor Analyst, the finding was determined to be of very low safety significance because, based on the actual condition of the drains and the extent of the clogging in room 1203, an evaluation by the licensee showed that the maximum internal flooding water level in the room would not challenge the operability of any equipment needed for safe shutdown or to mitigate an accident. This finding has a team work cross-cutting aspect in the human performance cross-cutting area because individuals and work groups did not communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained.

Specifically, inadequate communication between engineering and operations personnel led to the belief that a passageway existed between rooms 1203 and 1204 when it did not

[H.4]. (Section 1R06)

PLANT STATUS

Callaway began the inspection period at 100 percent power. On March 8, 2016, the licensee began coasting down at the end of the operating cycle. Callaway completed the inspection period at 86 percent power.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

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: February 26, 2016, train B component cooling water system March 14, 2016, train B spent fuel pool cooling and cleanup system 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 constituted two partial system walk

-down sampl e s as defined in Inspection Procedure 71111.04.

b. Findings

No findings were identified.

.2 Complete Walk

-Down

a. Inspection Scope

The inspectors performed complete system walk

-down s of the following risk

-significant systems: February 4, 2016, control room emergency ventilation system February 6, 2016 , turbine-driven auxiliary feedwater pump system 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 work orders, open condition reports, 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 constituted two complete system walk

-down samp le s, as defined in Inspection Procedure 71111.04.

b. Findings

No findings were identified.

1 R 05 Fire Protection (71111.05)

.1 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 five plant areas important to safety:

January 6, 2016 , train A spent fuel pool heat exchanger room (room 6105) and electrical equipment room (room 6202) in fuel building fire area (FB

-1) January 27, 2016 , train B essential service water pump room (USPH)

January 27, 2016 , upper cable spreading room (C

-22) January 27, 2016 , lower cable spreading room (C

-21) March 22, 2016, train B class 1E air conditioning equipment room (C

-13) 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 constituted fi ve quarterly inspection samples, as defined in Inspection Procedure 71111.05.

b. Findings

Introduction.

The inspectors identified an unresolved item associated with the National Fire Protection Association (NFPA) Standard 805, "Performance

-Based Standard for Fire Protection for Light

-Water Reactor Electric Generating Plants," non-power operations assessment. Specifically, the inspectors developed an issue of concern in that the licensee screened the potential loss of spent fuel pool cooling from further consideration for any fire event based on adequate procedural guidance and time when the procedures would not maintain the fuel in a safe and stable condition.

Description.

On January 13, 2014, the licensee transitioned their fire protection program to a risk-informed, performance

-based program based on NFPA Standard 805, "Performance

-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants

."

Paragraph 1.3.1 of NFPA Standard 805 requires licensees to provide reasonable assurance that a fire during any operational mode and plant configuration will not prevent the plant from achieving and maintaining the fuel in a safe and stable condition.

Paragraph 1.5.1 of NFPA Standard 805 lists five nuclear safety performance criteria. These criteria provide requirements to demonstrate that fire protection features are capable of providing reasonable assurance that the plant is not placed in an unrecoverable condition in the event of a fire. For the decay heat removal nuclear safety performance criterion, the standard requires that decay heat removal shall be capable of removing sufficient heat from the reactor core or spent fuel such that fuel is maintained in a safe and stable condition.

Paragraph 1.6.56 of NFPA Standard 805 defines safe and stable conditions:

For fuel in the reactor vessel, head on and tensioned, safe and stable conditions are defined as the ability to maintain Keff <0.99, with a reactor coolant temperature at or below the requirements for hot shutdown for a boiling water reactor and hot standby for a pressurized water reactor. For all other configurations, safe and stable conditions are defined as maintaining Keff <0.99 and fuel coolant temperature below boiling.

The licensee described how they satisfied the nuclear safety performance criteria in Calculation KC-26, "Nuclear Safety Capability Assessment," Revision 1. The Nuclear Safety Capability Assessment applied to both power and non

-power operations.

For non-power operations, the licensee evaluated the spent fuel pool decay heat removal key safety function and determined that t he spent fuel pool decay heat removal key safety function did not require a detailed review since adequate time was available, and procedural guidance was provided, for operators to respond to and mitigate a loss of s pen t f uel pool decay heat removal, even under full hot core offload conditions.

The licensee stated that the shortest time to boil, under worst case conditions for a normal plant shutdown, was two hours. In addition, the licensee stated that all of the analyses to address a loss of spent fuel pool decay heat removal utilized a success criterion of no boiling.

The licensee implemented the process outlined in Frequently Asked Question (FAQ) 07-0040, "Non

-Power Operations Clarifications," Revision 4, for the non-power operations assessment.

This FAQ stated that licensees should conservatively assume the entire contents of a fire area are lost and document the loss of success paths. This FAQ also stated that licensees should specifically identify those areas (pinch points)that cause the loss of all success paths for a key safety function.

The inspectors noted that the licensee did not perform these actions for the spent fuel pool decay heat removal key safety function because this key safety function was screened out from further consideration. If the licensee had evaluated the spent fuel pool decay heat removal key safety function using the process outlined in this FAQ, then the licensee would have assumed that both trains of spent fuel pool cooling are lost during a fire in the fuel handling building because both trains are located within the same fire area and were unprotected.

This FAQ also stated that fire modeling may be used to determine if postulated fires in a fire area are expected to damage equipment (and cabling), thereby eliminating a pinch point. However, the licensee stated that no fire modeling was used to eliminate the identification of pinch point fire areas as part of the non

-power operations assessment performed using the process in FAQ 07-0040.

In the event that a fire in the fuel handling building disabled both trains of spent fuel pool cooling, operators were expected to enter Procedure OTO-EC-00002, "Spent Fuel Pool High Temperature," Revision 9, due to the increasing temperature of the spent fuel pool.

This procedure provided directions for operators to restore one or both trains of spent fuel pool cooling. Since both trains of spent fuel pool cooling were assumed lost due to the fire, the operators would be unable to restore spent fuel pool cooling using this procedure.

After a period of time, the spent fuel pool would begin boiling and the level would begin lowering. At this time, operators were expected to enter Procedure OTO-EC-00001, "Loss of SPF/Refuel Pool Level," Revision 13. Procedure OTO-EC-00001 directed the operators to open two normally locked essential service water valves to restore and maintain spent fuel pool level.

The licensee's procedures allowed the spent fuel pool to reach boiling conditions prior to restoring and maintaining level. Since NFPA Standard 805 defined safe and stable conditions, in part, as fuel coolant temperature below boiling, the procedures did not maintain the fuel in a safe and stable condition. The inspectors identified an issue of concern in that the licensee screened the potential loss of spent fuel pool cooling from further consideration for any fire event based on adequate procedural guidance and time when the procedures would not maintain the fuel in a safe and stable condition.

The inspectors determined that additional information is required to determine if a performance deficiency exists. Specifically, the inspectors need to determine if this scenario should have been addressed as part of the current FAQ 07-0040 guidance, or if new guidance is needed to address this type of scenario where the full core has been offloaded to the spent fuel pool.

On March 31, 2016, additional guidance was requested from the Office of Nuclear Reactor Regulation via a request to review and update FAQ 07-0040. This memorandum is documented in ADAMS as Accession Number ML16091A152.

The licensee entered this issue of concern into the corrective action program as Callaway Action Request 201600726. This issue of concern is being treated as Unresolved Item 05000483/2016001-01 , "Possible Incorrect Screening of the Spent Fuel Pool Decay Heat Removal Key Safety Function.

"

.2 Annual Inspection

a. Inspection Scope

On March 2, 2016, the inspectors completed their annual evaluation of the licensee's fire brigade performance. This evaluation included observation of an announced fire drill for a fire in the laundry decontamination facility.

During this drill, the inspectors evaluated the capability of the fire brigade members, the leadership ability of the brigade leader, the brigade's use of turnout gear and fire

-fighting equipment, and the effectiveness of the fire brigade's team operation. The inspectors also reviewed whether the licensee's fire brigade met NRC requirements for training, dedicated size and membership, and equipment.

These activities constituted one annual inspection sample, as defined in Inspection Procedure 71111.05.

b. Findings

No findings were identified.

1R0 6 Flood Protection Measures (71111.06)

a. Inspection Scope

On February 18, 2016 , the inspectors completed an inspection of the station's ability to mitigate flooding due to internal causes. After reviewing the licensee's flooding analysis, the inspectors chose the auxiliary building 1988 foot elevation containing risk

-significant structures, systems, and components that were susceptible to flooding.

The inspectors reviewed plant design features and licensee procedures for coping with internal flooding. The inspectors walked down the selected areas to inspect the design features, including the material condition of seals, drains, and flood barriers. The inspectors evaluated whether operator actions credited for flood mitigation could be successfully accomplished.

These activities constitute d completion of one flood protection measures sample, as defined in Inspection Procedure 71111.06.

b. Findings

Introduction

. The inspectors identified a Green, non

-cited violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," for the licensee's failure to perform an adequate operability determination for safety related components located in the 1988 foot auxiliary building train B piping penetration room (room 1203) based on degraded internal flooding drain capability. Specifically, the immediate operability determination (IOD) included incorrect assumptions that were not verified to support the operability determination as required by licensee Procedure ODP-ZZ-00001, Addendum 15, "Operability and Functionality Determinations

," Revision 8. Description

. On July 2, 2014, during a planned maintenance inspection of 6 of the 12 floor drain lines in room 1203, one floor drain line was found to be approximately 50 percent clogged. Drain lines in room 1203 are credited in Calculation M-FL-03, "Flooding of Individual Aux Building Rooms," to provide sufficient water removal capability during an internal flooding event. An IOD was completed which credited a 2-foot wide passage between room 1203 and the 1988 foot elevation auxiliary building train A piping penetration room (room 1204). With a passage between the rooms, any water from an internal flooding event in room 1203 would flow to room 1204 where the drain lines in that room would be able to make up for the flow loss from the clogged drain line in room 1203. On August 21, 2014, four additional floor drains of the remaining six drain lines in room 1203 were discovered to be partially blocked.

One of these drains was able to be cleared during the inspection.

The three additional clogged drain lines further reduced the ability for water to drain out of room 1203 during an internal flooding event. These clogged drains were documented in two separate Callaway action requests and two new IODs were performed. The IODs determined that the equipment in room 1203 remained operable based on a 2-foot 8-inch opening in the wall connecting rooms 1203 and 1204. With this opening present, the seven drain lines in room 1204 were credited to remove water. On October 12, 2015, one of clogged drains in room 1203 was cleared during maintenance.

Upon review by inspectors on February 18, 2016, a visual inspection showed that the 2-foot 8-inch opening was not actually present in the wall between rooms 1203 and 1204. A fourth IOD was conducted at that time and a compensatory measure was implemented to open the access door to room 1203 to allow a drainage path for water out of the room during an internal flooding event.

Subsequent analysis of past operability was conducted and determined that an internal flooding event in room 1203 would not affect the operability of safety related components within or outside the room.

Architectural drawing A-2305, "Auxiliary and Reactor Building Floor Plans, El.

1988'-0" & El. 2013'-6"," shows the 2-foot 8-inch opening between rooms 1203 and 1204. This drawing was referenced in the initial IOD. The initial IOD states that the 2-foot wide passage between rooms 1203 and 1204 was confirmed by operations walk

-down. The licensee's causal analysis determined that a walk

-down was completed in the rooms, however, operations believed that a 13-inch piping penetration hole between the rooms was the opening that was being referred to.

This was due to a communications error between engineering and operations.

Drawing C-2C11231, "Auxiliary Building Concrete Neat Lines Plan Floor El.

1988'-0"," shows the 2-foot 8-inch opening as an "optional opening." This drawing is referenced in the subsequent IODs.

Walk-downs were not completed during the subsequent IODs based on the statement in the original IOD that this opening was verified at that time.

Procedure ODP-ZZ-00001, Addendum 15, states that "The SM should ENSURE an appropriate level of questioning and challenging of assumptions occurs to ensure that a sound basis for operability exists throughout the OD process."

In this case, because the wall opening between rooms 1203 and 1204 was credited in the IODs conducted for the degraded drain capability in room 1203 and did not actually exist, a sound basis for operability did not exist throughout the operability determination process.

Analysis.

The licensee's failure to verify assumptions used in the IOD and ensure a sound basis for operability exists per plant procedures was a performance deficiency.

The performance deficiency is more than minor, and therefore a finding, because it is similar to examples 3.j and 3.k in Inspection Manual Chapter 0612, Appendix E, "Examples of Minor Issues," and if left uncorrected, it has the potential to lead to a more significant safety concern. Specifically, failure to perform adequate operability evaluations by verifying assumptions and ensuring a sound basis for operability exists may result in the failure to enter the appropriate limiting conditions of operation for technical specification equipment.

Using Inspection Manual Chapter 0609, Appendix A, Exhibit 2, "Mitigating Systems Screening Questions," the finding involved the degradation of equipment specifically designed to mitigate a flooding initiating event, therefore, Exhibit 4, "External Events Screening Questions," was used to complete the screening. The finding was determined to need a detailed risk evaluation because if the equipment (i.e.

, floor drain lines) were assumed to be completely failed or unavailable, it would degrade one or more trains of a system that supports a risk significant system or function. In consultation with the Senior Reactor Analyst, the finding was determined to be of very low safety significance because, based on the actual condition of the drains and the extent of the clogging in room 1203, an evaluation by the licensee showed that the maximum internal flooding water level in the room would not challenge the operability of any equipment needed for safe shutdown or to mitigate an accident. This finding has a teamwork cross-cutting aspect in the human performance cross

-cutting area because individuals and work groups did not communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained.

Specifically , inadequate communication between engineering and operations personnel led to the belief that a passageway existed between rooms 1203 and 1204 when it did not

[H.4].

Enforcement

. Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," requires, in part, that activities affecting quality shall be accomplished in accordance with instructions, procedures, or drawings of a type appropriate to the circumstances.

Callaway Procedure ODP-ZZ-0000 1 , Addendum 15, "Operability and Functionality Determinations

," an Appendix B quality related procedure, provides instructions for performing operability determinations.

Procedure ODP-ZZ-00001, Addendum 15, step 3.2.2 states, in part

, "The SM should ENSURE an appropriate level of questioning and challenging of assumptions occurs to ensure that a sound basis for operability exists throughout the OD process." Contrary to the above, on July 2 and August 21, 2014, the licensee failed to ensure an appropriate level of questioning and challenging of assumptions occurred to ensure that a sound basis for operability existed throughout the operability determination process.

Specifically, the licensee credited, in an operability determination, an opening in the wall between rooms 1203 and 1204 that did not exist. The immediate corrective action was to implement a compensatory measure to support operability of the equipment in room 1203. This violation is being treated as a non-cited violation, consistent with Section 2.3.2.a of the Enforcement Policy. The violation was entered into the licensee's corrective action program as Callaway Action Request 201601412: NCV 05000483/2016001

-02, "Inadequate Operability Evaluation for Degraded Flood Mitigation Capability in Piping Penetration Room."

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

.1 Review of Licensed Operator Requalification

a. Inspection Scope

On January 28, 2016, the inspectors observed simulator training for an operating crew. The inspectors assessed the performance of the operators and the evaluators' critique of their performance.

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

b. Findings

No findings were identified.

.2 Review of Licensed Operator Performance

a. Inspection Scope

During the period, 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 activity due to the activities listed below.

The inspectors observed the operators' performance of the following activities:

February 17, 2016 , reactor coolant pump undervoltage and underfrequency relay testing and train B centrifugal charging pump in

-service testing February 19, 2016, control room turnover In addition, the inspectors assessed the operators' adherence to plant procedures, including Procedure ODP-ZZ-00001, "Operations Department

- Code of Conduct,"

Revision 97, and other operations department policies.

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

b. Findings

No findings were identified.

1 R 12 Maintenance Effectiveness (71111.12)

a. Inspection Scope

The inspectors reviewed two instances of degraded performance or condition of safety-related structures, systems, and components

February 12, 2016 , reactor coolant system 10 CFR 50.65(a)(1) evaluation February 26, 2016, component cooling water The inspectors reviewed the extent of condition of possible common cause structure, system, or component 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 structures, systems, or com p onents. 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

No findings were identified.

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

a. Inspection Scope

The inspectors reviewed two 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 26, 2016 , train A motor-driven auxiliary feedwater pump planned maintenance March 3, 2016, train B air compressor and service water pump planned maintenance The inspectors verified that these risk assessment were performed timely and in accordance with the requirements of 1 0 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments. The inspectors also observed portions of three emergent work activities that had the potential to cause an initiating event, to affect the functional capability of mitigating systems, or to impact barrier integrity:

March 2, 2016, train B component cooling water isolation valve to rad waste stroke time test failure and repair March 9, 2016, train B emergency diesel generator digital reference unit issue March 21 , 2016, loop 4 over temperature delta

-T spiking low 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 structures, systems, and components

.

These activities constitute d completion of five maintenance risk assessments and emergent work control inspection samples, 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 six operability determinations that the licensee performed for degraded or nonconforming structures, systems, or components

January 2, 2016, steam generator blowdown sample isolation valv e failure (BMHV0019), Callaway Action Request 201600018 January 13, 2016, containment pressure transmitter spike high, Callaway Action Request 201600336 January 27, 2016, operability determination of train A emergency diesel generator with noise and vibration present on engine-driven lube oil pump , Callaway Action Request 201600694 February 11, 2016, functionality assessment of reactor coolant system loop 4 low TAVG bistable card failure, Callaway Action Request 201601028 March 2 , 2016, operability determination of component cooling water supply isolation valve to rad waste (EGHV0070A), Callaway Action Request 201601852 March 18, 2016, operability determination of containment air coolers beyond design fouling, Callaway Action Request 201602305 The inspectors reviewed the timeliness and technical adequacy of the licensee's evaluations. Where the licensee determined the degraded structures, systems, or components to be operable, the 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 degrade d conditions on the operability of the degraded structures, systems, or components. These activities constitute d completion of six operability and functionality review samples as defined in Inspection Procedure 71111.15.

b. Findings

No findings were identified.

Plant Modifications (71111.18)

Temporary Modifications

a. Inspection Scope

On March 24, 2016, the inspectors reviewed a temporary modification to the safety related SB041 cabinet where the licensee installed a temporary recorder.

The inspectors verified that the licensee had installed this temporary modification in accordance with technically adequate design documents. The inspectors verified that

th is modification did not adversely impact the operability or availability of affected structures, systems, or components. The inspectors reviewed design documentatio n and plant procedures affected by the modification to verify the licensee maintained configuration control.

These activities constitute d completion of one sample of temporary modifications, as defined in Inspection Procedure 71111.18.

b. Findings

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 structures, systems, or components

January 27, 2016 , train A motor-driven auxiliary feedwater pump planned maintenance, multiple jobs January 29, 2016 , train A emergency diesel generator engine

-driven lube oil pump suction and discharge couplings, Job 16000420 February 13, 2016, steam generator A blowdown sampling secondary system isolation valve position indication failure, Job 16000006 February 26, 2016, com ponent cooling water pump A oil change, Job 145068 5 8 March 3, 2016, train B compressed air system air compressor, multiple jobs March 10, 2016, train B emergency diesel generator digital reference unit issue, Job 1600 1083 The inspectors reviewed licensing

- and design-basis documents for the structures, systems, and components and the maintenance and post

-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 structures, systems and component s. These activities constitute d completion of s ix post-maintenance testing inspection samples, as defined in Inspection Procedure 71111.19.

b. Findings

No findings were identified.

1 R 20 Refueling and Other Outage Activities (71111.20)

a. Inspection Scope

The inspectors reviewed the Callaway outage schedule and staffing plans for Refueling Outage 21, scheduled to commence April 2, 2016, to confirm that the licensee had appropriately considered risk, industry experience, and previous site

-specific problems in developing and implementing a plan that assured maintenance of defense

-in-depth. In addition, the inspectors reviewed the new fuel receipt process for the upcoming outage.

These inspection efforts constituted elements of a refueling outage sample as defined i n Inspection Procedure 71111.20

-05, which will be counted at the conclusion of Refueling Outage 21.

b. Findings

No findings were identified.

1 R 22 Surveillance Testing (71111.22)

a. Inspection Scope

The inspectors observed six risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the structures, systems, and components were capable of performing their safety functions:

In-service tests:

January 5, 2016 , train B residual heat removal pump in-service test Other surveillance tests:

January 8 , 2016, train B solid state protection system functional test February 3, 2016 , train B centrifugal charging pump in

-service test February 3, 2016, train B solid state protection system slave relay K624, K626, K604, K711, & K743 test February 10, 2016, pressurized reactor coolant system sample March 18, 2016 , train A emergency diesel generator 24-hour run The inspectors verified that these tests 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 structures, systems, and component s following testing.

These activities constitute d completion of six surveillance testing inspection samples, 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 inspectors performed an in

-office review of Radiological Emergency Response Plan, Revision 47, Procedure EIP-ZZ-00101, "Classification of Emergencies," Revision 52, and Procedure EIP-ZZ-00101, Addendum 2, "Emergency Action Level Technical Basis Document," Revision 10. Th e s e revision s: clarify the intent of the Emergency Director judgment emergency action levels HU 7.1 through HG 7.1 added references to the event close

-out procedure for exiting an emergency action level implemented the NEI 99-01 , Revision 6 , emergency action level scheme as approved in NRC License Amendment 212, dated October 7, 2015 (ADAMS Accession Number ML15251A493)made other minor corrections and administrative changes in the documents

Th e s e revisions were compared to their previous revision s, 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, to Nuclear Energy Institute Report 99-01, "Emergency Action Level Methodology," Revision 6, and to the standards in 10 CFR 50.47(b) to determine if the revisions adequately implemented the requirements of 10 CFR 50.54(q)(3) and 50.54(q)(4). The inspectors also compared the emergency action level basis document to the version submitted for review of August 31, 2015 (ADAMS Accession Number ML15244B 274). The inspectors verified that the revisions did not decrease the effectiveness of the emergency plan. These reviews were not documented in a safety evaluation report and did not constitute approval of licensee

-generated changes; therefore, these revisions are subject to future inspection.

These activities constitute d completion of three emergency action level and emergency plan change samples as defined in Inspection Procedure 71114.04.

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 Mitigating Systems Performance Index:

Emergency AC Power Systems (MS06)and Cooling Water Support Systems (MS10)

a. Inspection Scope

The inspectors reviewed the licensee's mitigating system performance index data for the period of first quarter 2015 through fourth quarter 2015 to verify the accuracy and completeness of the reported data. 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 reported data. These activities constituted verification of the mitigating system performance index for emergency ac power systems and the mitigating system performance index for cooling water support systems as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.2 Reactor Coolant System Specific Activity (BI01)

a. Inspection Scope

The inspectors reviewed the licensee's reactor coolant system chemistry sample analyses for the period of first quarter 2015 through fourth quarter 2015 to verify the accuracy and completeness of the reported data. The inspectors observed a chemistry technician obtain and analyze a reactor coolant system sample on February 10, 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 reported data.

These activities constituted verification of the reactor coolant system specific activity performance indicator, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

4OA 2 Problem Identification and Resolution (71152)

.1 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 the 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.

.2 Annual Follow

-up of Selected Issues

a. Inspection Scope

The inspectors selected two issues for an in

-depth follow

-up: On February 3, 2016, the inspectors selected Callaway action requests associated with two fires within the protected area at the hardened condensate storage tank project

and an arc flash event in a non

-safety related transformer within the protected area for in

-depth follow

-up. These issues are documented in Callaway Action Requests 201508995, 201509059, 201509008, and 201600248

. The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate t o correct the conditions

.

On March 15, 2016, the inspectors selected Callaway Action Request 201600739 associated with loose bolts found on the train A emergency diesel generator engine-driven lube oil pump suction and discharge couplings for an in-depth follow-up.

The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition

.

These activities constitute d completion of two annual follow

-up samples as defined in Inspection Procedure 71152.

b. Findings

No findings were identified.

4OA 3 Follow-up of Events and Notices of Enforcement Discretion (71153)1. (Closed) Licensee Event Report 2015-003-0 0 and 2015-003-01, Reactor Trip Caused by Transmission Line Fault On August 11, 2015, the reactor tripped from 10 0 percent power due to an incorrect, automatic response to a transmission line fault on the Montgomery

-Callaway 8 line by transformer bus differential relaying. This resulted in reactor protection system and auxi liary feedwater system actuations. The plant response was as expected except for problems with auxiliary feedwater system flow control valve (ALHV007) subsequent to the plant trip. The problems with ALHV007 were the subject of a special inspection and were dispositioned in NRC Inspection Report 05000 483/2015009 (ADAMS Accession Number ML16013A021

). This event was caused by the inadvertent inclusion of jumpers in the current transformer circuits of the main transformers that were installed as part of a plant modification during Refueling Outage 19. Following the event, the licensee corrected the condition by removing the errantly installed current transformer jumper s and then restarted the plant.

The licensee determined the root cause of the incorrect main transformer current transformer wiring was that a drawing, which originally depicted the installation of the jumpers, was not revised when converted from a vendor drawing to a licensee controlled drawing in 1983. Given that this error occurred prior to the Callaway Plant receiving an operating license, the inspectors determined that a performance deficiency reasonably within the licensee's control to prevent did not exist.

Additional corrective actions included additional design, testing, and job reviews, as well as reviews of similar vendor generated drawings to determine the extent of cause and condition.

No violation of NRC requirements were identified. This licensee event report is closed.

2. (Closed) Licensee Event Report 2015-004-00, Auxiliary Feedwater Flow Control Valve Inoperable due to Faulty Electronic Positioner Card On August 11, 2015, the licensee determined that a latent problem in the auxiliary feedwater system led to a condition prohibited by technical specifications and could have prevented the fulfillment of a safety function. Specifically, the condition was a flawed card used in the flow control valve for motor-driven auxiliary feedwater pum p B combined with planned work outages for redundant trains of auxiliary feedwater. The licensee believed t hese condition s existed for short durations between November 18 and December 3, 2014. This issue was the subject of a special inspection

, and all related findings were dispositioned in NRC Inspection Report 05000 483/2015009 (ADAMS Accession Number ML16013A021

). This licensee event report is closed.

These activities constitute d completion of t wo event follow

-up samples, as defined in Inspection Procedure 71153.

4OA 6 Meetings, Including Exit

Exit Meeting Summary

On March 22, 2016, regional inspectors conducted an on

-site exit meeting to present the results of the in-office inspection of changes to the licensee's emergency plan and emergency action levels to Mr.

G. Rauch, Manager, Emergency Preparedness, and other members of the licensee staff. The licensee acknowledged the issues presented.

On April 6, 2016, the resident inspectors presented the inspection results t o Mr. Tim E. Herrmann, Site Vice President, 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

F. Bianco, Director, Nuclear Operations

B. Cox, Senior Director, Nuclear Operations

M. Fletcher, Engineer, Fire Protection

M. Hoehn, Supervisor, Engineering Programs

G. Jurisic, Emergency Planner

S. Petzel, Engineer, Regulatory Affairs

G. Rauch, Manager, Emergency Preparedness

K. Tipton, Supervisor, Engineering Systems

T. Witt, Engineer, Regulatory Affairs

NRC Personnel

D. Loveless, Senior Reactor Analyst

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

05000483-2016 001-02 NCV Inadequate Operability Evaluation for Degraded Flood Mitigation Capability in Piping Penetration Room

(Section 1R06)

Opened

05000483/2016001

-01 URI Possible Incorrect Screening of the Spent Fuel Pool Decay Heat Removal Key Safety Function

(Section 1R05.1)

Closed

05000483/2015

-003-

05000483/LER-2015-003-01 LER Reactor Trip Caused by Transmission Line Fault

(Section 4OA3.1)

05000483-2015-004-00 LER Auxiliary Feedwater Flow Control Valve Inoperable due to Faulty Electronic Positioner Card

(Section 4OA3.2)

LIST OF DOCUMENTS REVIEWED

Section 1R04

Equipment Alignment

Procedures

Number Title Revision

EDP-ZZ-01012

Control Room Envelope Habitability Program 3

OSP-GK-0001B

B Train Control Room Filtration and Pressurization System Monthly Operability Verification

Attachment

Procedures

Number Title Revision

OSP-GK-0002A Train A Control Room Ventilation and Pressure Test

OSP-GK-0002B Train B Control Room Ventilation and Pressure Test

OTN-AL-00001 Auxiliary Feedwater System

OTN-AL-00001 Checklist 1

Auxiliary Feedwater System Valve Alignment

OTN-AL-00001 Checklist 3

TD-AFP Switch Alignment

OTN-EC-00001 Fuel Pool Cooling and Cleanup System

OTN-EC-00001 Checklist 1

Fuel Pool Cooling and Cleanup System Valve Lineup (Outside Containment)

OTN-EC-00001 Checklist 3

Electrical and Control Handswitch Alignment

OTN-GK-00001 Control Building HVAC System

OTN-GK-00001 Checklist 4

Control Building HVAC System CRVIS Lineup

- Train A 13

OTN-GK-00001 Checklist 6

Control Building HVAC System CREVS Flow Balance Damper and Register Lineup

- Train A 13

Drawing s Number Title Revision A-2909 Door Schedule

C-2021 Power Block Column Grid System

C-2C6111(Q) Fuel Building Concrete Neat Lines Plan Ground Floor El. 2000'0" 2 C-2C7221 Radwaste Building Area 2 Concrete Neat Line Plan El. 2000'0" 1 J-104-00176 Logic Block Diagram ESFAS

J-104-00042 ESF Actuation System

- Channel 4 Actuation Output/Status Indications

J-104-00034 ESF Actuation System

- Channel 1 Actuation Output/Status Indications

M-22EG01(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22EG02(Q) Piping and Instrumentation Diagram Component Cooling Water System

Attachment Drawing s Number Title Revision M-22EG0 3(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22GK01(Q) Control Building HVAC Piping and Instrumentation Diagram

M-22GK02(Q) Control Building HVAC Piping and Instrumentation Diagram

M-22GK03(Q) Control Building HVAC Piping and Instrumentation Diagram

M-22AL01(Q) Auxiliary Feedwater System Piping and Instrumentation Diagram 44

Callaway Action Requests

200701174

201400767

201401457

201401584

201404353

201405508

201405777

201405778

201405912

201406097

201408127

201408221

201408448

201408449

201408543

201408579

201408580

201408594

201408957

201501866

201503543

201504520

201506284

201507235

201601462

Job s

15001334

Miscellaneou

s Number Title Revision/ Date

Surveillance Tracking Manual

M-082-00039 Instruction Manual for Component Cooling Water Pumps

NEI 99-03 Control Room Habitability Assessment Guidance June 2001 Regulatory Guide 1.197

Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors May 2003

Section 1R05

Fire Protection Procedures Number Title Revision

OTO-EC-00001 Loss of SFP/Refuel Pool Level

OTO-EC-00002 Spent Fuel Pool High Temperature

OTO-KC-00001 Fire Response

Attachment

Procedures

Number Title Revision

OTO-KC-00001 , Addendum FB

-01 Fuel Handling Building 2000', 2026', 2047'

- All Elevations Callaway Action Requests

201600524

201600726

Miscellaneou

s Number Title Revision/Date

Fire Preplan Manual

17671-FRE-FB-1 Fire Evaluation of Delta Risk for Fire Area FB

-1 0 EC Sup. Guide Emergency Coordinator Supplemental Guideline

KC-26 Nuclear Safety Capability Assessment

KC-124 Fire Safety Analysis for Fire Area C

-13 1

KC-132 Fire Safety Analysis for Fire Area C

-21 1

KC-133 Fire Safety Analysis for Fire Area C

-22 1

KC-151 Fire Safety Analysis for Fire Area FB

-1 1

KC-160 Fire Safety Analysis for Fire Area USPH

1st Quarter 2016

Drill Planning and Authorization March 2, 2016

Section 1R06

Flood Protection Measures

Procedures

Number Title Revision

APA-ZZ-00750 Hazard Barrier Program Drawing s Number Title Revision A-2305 Auxiliary and Reactor Building Floor Plans, El. 1988'

-0" & El. 2013'-6" 0 C-2C1231 Auxiliary Building Area 3 Concrete Neat Lines Plan Floor El.1988'-0" 0 M-23KC17 Piping Isometric Fire Protection Auxiliary Building

M-22KC02(Q) Fire Protection System Piping and Instrumentation Diagram

Attachment Callaway Action Requests

200610048

201201033

201404450

201405518

201405555

201601412

201601881

201600764

Job s

12504329

14002927

14003803

14003804

Miscellaneou

s Number Title Revision M-FL-01 Flooding of the Aux Building

M-FL-03 Flooding of Individual Auxiliary Building Rooms 2 RFR 201201033

Provide Basis for HELB Program Section 1R11

Licensed Operator Requalification Program

Procedures

Number Title Revision

ODP-ZZ-00001 Operations Department

- Code of Conduct

ODP-ZZ-00001 , Addendum 1

Annunciator Response

ODP-ZZ-00001 , Addendum 11

Control Room Decorum Miscellaneou

s Number Title Date T61.0810 8

Licensed Operator Continuing Training

- BOL Reactor and Plant Startup

- Scenario S

-4 December 11, 2015

Section 1R12

Maintenance Effectiveness

Procedures

Number Title Revision

APA-ZZ-00315 Configuration Risk Management Program

APA-ZZ-00500 Appendix 5

Maintenance Rule

EDP-ZZ-01128 Maintenance Rule Program

Attachment

Procedures

Number Title Revision

EDP-ZZ-01128 Appendix 1

SSCs in the Scope of the Maintenance Rule at Callaway

EDP-ZZ-01128 Appendix 2

Summary of SSC Performance Criteria

EDP-ZZ-01128 Appendix 3

Maintenance Rule Shutdown Performance Criteria

EDP-ZZ-01128 Appendix 4

Maintenance Rule System Functions

EDP-ZZ-01129 Callaway Energy Center Risk Assessment

OSP-EG-P01AC CCW Train A Pump and Valve Inservi ce Test - Group A 32

Drawing s Number Title Revision M-22EG01(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22EG02(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22EG03(Q) Piping and Instrumentation Diagram Component Cooling Water System Callaway Action Requests

201306459

201404550

201505308

201507718

201507752

Job s

14506858

Miscellaneou

s Title

Oil Sample Results CCW motor and Pump Callaway CCW system Health Report Fourth Quarter 2015

Attachment Section 1R13

Maintenance Risk Assessment and Emergent Work Controls

Procedures

Number Title Revision

APA-ZZ-00315 Configuration Risk Management Program

EDP-ZZ-01129 Callaway Energy Center Risk Assessment

ODP-ZZ-00002 Appendix 1

Protected Equipment Program

ODP-ZZ-00002 Appendix 1, Checklist 3

Placing Train B Protected Equipment Barriers, Mode 1

-4 1

ODP-ZZ-00002 Appendix 2

Risk Management Actions for Planned Risk Significant Activities Callaway Action Requests

201601852

201602074

201602324

Job s

15504506

15512533

16001083

16001268

Section 1R15

Operability Evaluations

Procedures

Number Title Revision

APA-ZZ-00500 , Appendix 1

Operability and Functionality Determinations

ISL-BB-0T441 Loop- 89

ODP-ZZ-00001, Addendum 15

Operability and Functionality Determinations

OSP-EG-V001B CCW Train B Valve Inservice Test

OSP-SA-2413B Train B Diesel Generator and Sequencer Testing

OSP-SA-0017B Train B SIS

-CSAS Slave Relay Test

OTA-RK-00024, Addendum 108E

Steam Generator Setpoint High Containment Pressure

Attachment Drawing s Number Title Revision M-22BM01(Q) Steam Generator Blowdown System Piping and Instrumentation Drawing

M-22KJ03(Q) Standby Diesel Generator "A" Lube Oil System

M-18-00912 Coupling, 5" Nom. Pipe Size

M-18-00913 Coupling - 6" Nom. Pipe

FSAR Figure 7.2-1 Sheet 5 Primary Coolant System Trip Signals

FSAR Figure 7.2-1 Sheet 5A

Primary Coolant System Trip Signals

7250D64 S013

Feedwater Control and Isolation Functional Diagram

M22-EG03 (Q) Component Cooling Water Piping and Instrumentation Diagram 24 M-23KC17 Piping Isometric Fire Protection Auxiliary Building

M-22KC02 (Q)

Fire Protection System Piping and Instrumentation Diagram Callaway Action Requests

200700759

200904273

201106600

201300359

201309485

201404450

201405518

201405555

201407075

201508633

201600018

201600694

201600336

201600739

201601028

201601852

201602305

Job s

10502119

11004514

12504329

15508579

15512533

16000006

16000197

16000420

Section 1R18

Plant Modifications

Procedures

Number Title Revision

APA-ZZ-00605 Temporary System Modifications Drawing s Number Title Revision 7250D64 S005

Functional Diagram

- Primary Coolant System Trip Signals

Attachment Drawing s Number Title Revision 8756D37 S010

Process Control Block Diagram

- Loop 4 T/TAVG Protection Set

IV 11 M-22BB01 Piping and Instrumentation Diagram

- Reactor Coolant System 31

Callaway Action Requests

201602324

Job s

16001268

Miscellaneou

s Number Title Revision

TM 16-0004 Recorder in SB041 for Monitoring Temperature Loop 4

Section 1R19

Post-Maintenance Testing Procedures Number Title Revision

APA-ZZ-00100 Written Instructions Use and Adherence

APA-ZZ-00320 Work Execution

APA-ZZ-00322 Appendix E

Post-Maintenance Test Program

OSP-AL-P001A Motor Driven Aux. Feedwater Pump A Inservice Test - Group A 63

OSP-AL-V001A Train A Auxiliary Feedwater Valve Inservice Test

OSP-BM-V0001 Steam Generator Sample Line Isolation Valve Inservice Test

OSP-EF-V001B ESW Train B Valve Operability

OSP-EG-P01AC CCW Train A Pump and Valve Inservice Test

- Group A 32

OSP-SA-0007B Train B AFAS Slave Relay Test

OTN-NE-0001A Standby Diesel Generation System

- Train A 48

OTS-NE-ST01B B Emergency Diesel Generator Governor Tuning Post Maintenance Test Procedure

Attachment Drawing s Number Title Revision M-22EG01(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22EG02(Q) Piping and Instrumentation Diagram Component Cooling Water System

M-22EG03(Q) Piping and Instrumentation Diagram Component Cooling Water System Callaway Action Requests

201602074

201602279

Job s

08004474

10514753

10514754

10514755

10514760

11507326

13502894

13511612

14504449

14506858

14506866

14506868

14509210

14509217

14509219

14509262

15504506

15511211

15512619

16000006

16000420

16000663

16001083

Miscellaneou

s Number Title Revision M-082-00039 Instruction Manual for Component Cooling Water Pumps Section 1R20

Refueling and Other Outage Activities

Procedures

Number Title Revision

ETP-ZZ-00003 Inspection of New Fuel

OTS-KE-00003 Unloading and Storage of New Fuel Assemblies and Inserts Callaway Action Requests

201600506

201600608

Miscellaneou

s Title Date Callaway Refueling Outage 21

- Overview March 7, 2016

Attachment Miscellaneou

s Title Date Refuel 21 Major Scope Summary February 8, 2016

Refuel 21, Revision O, Entire Project Start to Finish March 2, 2016

Section 1R22

Surveillance Testing

Procedures

Number Title Revision

APA-ZZ-00356 Pump and Valve Inservice Test Program

APA-ZZ-00356, Appendix 2

IST Pumps Design Flow Rates

CSP-ZZ-07600 RCS Activity Determinations

ISF-SB-00A32 SSPS Train B Functional Test

ISF-SB-0A33A SSPS Train B Slave Relay K624, K626, K604, K711, & K743 Test 36

OSP-BG-P005B Centrifugal Charging Pump B Inservice Test

- Group B 52

OSP-EJ-P001B RHR Train B Inservice Test

- Group A 58

OSP-NE-0024A Standby Diesel Generator A 24 Hour Run and Hot Restart Test 50

Callaway Action Requests

199701249

Job s

14510503

15507589

15510482

15511596

15511644

Miscellaneou

s Title Revision Surveillance Tracking Manual In-service Testing Program

Attachment

Section 4OA1: Performance Indicator Verification

Miscellaneou

s

Title Revision/ Date Reactor Coolant System Dose Equivalent I

-131 Activity Data January 1, 2015 to December 31, 2015

Mitigating Systems Performance Index (MSPI) Basis Document Mitigating Systems Performance Index (MSPI) Basis Document

MSPI Derivation Report, MSPI Emergency AC Power System, Unavailability Index (UAI)

March 2015

MSPI Derivation Report, MSPI Emergency AC Power System, Unreliability Index (URI)

March 2015

MSPI Derivation Report, MSPI Emergency AC Power System, Unavailability Index (UAI)

June 2015 MSPI Derivation Report, MSPI Emergency AC Power System, Unreliability Index (URI)

June 2015 MSPI Derivation Report, MSPI Emergency AC Power System, Unavailability Index (UAI)

October 2015

MSPI Derivation Report, MSPI Emergency AC Power System, Unreliability Index (URI)

October 2015

MSPI Derivation Report, MSPI Emergency AC Power System, Unavailability Index (UAI)

December 2015 MSPI Derivation Report, MSPI Emergency AC Power System, Unreliability Index (URI)

December 2015 MSPI Derivation Report, MSPI Cooling Water System, Unavailability Index (UAI) March 2015

MSPI Derivation Report, MSPI Cooling Water System, Unreliability Index (URI)

March 2015

MSPI Derivation Report, MSPI Cooling Water System, Unavailability Index (UAI) June 2015 MSPI Derivation Report, MSPI Cooling Water System, Unreliability Index (URI)

June 2015 MSPI Derivation Report, MSPI Cooling Water System, Unavailability Index (UAI) October 2015

MSPI Derivation Report, MSPI Cooling Water System, Unreliability Index (URI)

October 2015

MSPI Derivation Report, MSPI Cooling Water System, Unavailability Index (UAI) December 2015 MSPI Derivation Report, MSPI Cooling Water System, Unreliability Index (URI)

December 2015

Attachment Miscellaneou

s

Title Revision/ Date NRC Performance Indicator Transmittal Report, First Quarter 2015, Mitigating Systems Cornerstone April 16, 2015 NRC Performance Indicator Transmittal Report, Second Quarter 2015, Mitigating Systems Cornerstone July 9, 2015

NRC Performance Indicator Transmittal Report, Third Quarter 2015, Mitigating Systems Cornerstone October 12, 2015 NRC Performance Indicator Transmittal Report, Fourth Quarter 2015, Mitigating Systems Cornerstone January 11, 2016

Section 4OA2: Identification and Resolution of Problems

Procedures

Number Title Revision

APA-ZZ-00700 Fire Protection Program

EIP-ZZ-00226 Fire Response Procedure for Callaway Plant

OTO-KC-00001 Fire Response Drawing s Number Title Revision M-018-00912 Coupling, 5" Nom. Pipe Size

M-018-00913 Coupling - 6" Nom. Pipe Callaway Action Requests

200709998

200800930

200904273

201106600

201508995

201509008

201509059

201600248

201600694

201600739

201601189

Job s

09003636

09003640

11004514

16000420

Attachment

Section 4OA3:

Event Follow

-Up Miscellaneou

s Number Title Date

LTR-TA-15-110 Preliminary Sensitivity Study Results for Callaway Feedline Break Event with Reduced AFW Capability September 21, 2015