IR 05000483/2018003

NRC Integrated Inspection Report 05000483/2018003 and Independent Spent Fuel Storage Installation Inspection Report 07201045/2018001

ML18295A010
Person / Time
Site:	Callaway
Issue date:	10/19/2018
From:	Nick Taylor NRC/RGN-IV/DRP/RPB-B
To:	Diya F Ameren Missouri
Taylor N
References
IR 2018001, IR 2018003
Download: ML18295A010 (31)

Text

October 19, 2018

SUBJECT:

CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2018003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07201045/2018001

Dear Mr. Diya:

On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Callaway Plant. On October 3, 2018, the NRC inspectors discussed the results of this inspection with Mr. T. Herrmann, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

Inspectors documented a licensee-identified violation, which was determined to be of very low safety significance. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or significance of the 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 Callaway Plant. 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/

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

Docket Nos. 50-483, 72-1045 License No. NPF-30

Enclosures:

Inspection Report 05000483/2018003 and 07201045/2018001

w/Attachments

1: Documents Reviewed

2: Request for Information Quarterly

Baseline Inspection

Inspection Report

Docket Numbers:

05000483 and 07201045

License Number:

NPF-30

Report Numbers:

05000483/2018003 and 07201045/2018001

Enterprise Identifiers: I-2018-003-006 and I-2018-001-0135

Licensee:

Union Electric Company

Facility:

Callaway Plant and Independent Spent Fuel Storage Installation

Location:

8315 County Road 459

Steedman, Missouri 65077

Inspection Dates:

July 1, 2018 to September 30, 2018

Inspectors:

D. Bradley, Senior Resident Inspector

S. Janicki, Resident Inspector

S. Alferink, PhD, Reactor Inspector

J. Drake, Senior Reactor Inspector

L. Brookhart, Senior ISFSI Inspector, FCDB

P. Elkmann, Senior Emergency Preparedness Inspector

N. Hernandez, Operations Engineer

C. Newport, Senior Resident Inspector

E. Simpson, CHP, Health Physicist, FCDB

C. Stott, Reactor Inspector

Approved By:

N. Taylor

Chief, Project Branch B

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at the Callaway Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC-identified and self-revealed findings, violations, and additional items are summarized in the tables below. A licensee-identified non-cited violation is documented in the Inspection Results at the end of this report.

List of Findings and Violations

None.

Additional Tracking Items

Type Issue number Title Inspection Procedure Status URI 05000483/2018003-01 Failure to perform 10 CFR 50.59 evaluation for compensatory measures associated with stagnant, inactive loop 71111.17T Open

Type Issue number Title Inspection Procedure Status LER 05000483/2018-002-00 Inadequate Emergency Operating Procedure Guidance for Asymmetric Natural Circulation Cooldown on May 7, 2018 71153 Closed

PLANT STATUS

Callaway Plant began the inspection period at full power and remained at this power level through the end of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515 Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.01Adverse Weather Protection External Flooding

The inspectors evaluated readiness to cope with external flooding on July 16, 2018.

71111.04Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Remote shutdown panel on July 12, 2018

(2) Component cooling water emergency makeup valves on August 7, 2018

(3) Fire water storage tanks on August 24, 2018

(4) Emergency exhaust system train B on August 25, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the component cooling water system train A on September 10, 2018.

71111.05AQFire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Load center and motor generator room, fire area A-27, on July 20, 2018

(2) Component cooling water train A, fire area A-16N, on September 5, 2018

(3) Component cooling water train B and remote shutdown panel, fire areas A-16S, A-28, and A-33, on September 19, 2018

(4) Spent fuel pool cooling train A, fire area FB-1, on September 20, 2018

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on July 23 and August 20, 2018.

71111.06Flood Protection Measures Cables

The inspectors evaluated cable submergence protection in safety-related manhole MH01B on August 16, 2018.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated licensed operator continuing training in the simulator on July 27, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated control room staff in the following evolutions:

(1) Crew turnover on September 7, 2018

(2) Pressurizer backup heaters capacity test and post maintenance test on September 21, 2018

Operator Exams (1 Sample)

The inspectors reviewed and evaluated requalification examination results on August 22, 2018.

71111.12Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Emergency diesel generator including temperature switches on July 11, 2018

(2) Component cooling water including gas voiding on September 21, 2018

71111.13Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Elevated risk actions due to emergent work on the solid state protection system input relay K334 on July 9, 2018

(2) Elevated risk actions due to planned residual heat removal train A pump and valve inservice testing on July 20, 2018

(3) Elevated risk actions due to planned containment isolation signal train B relay testing on August 16, 2018

(4) Elevated risk actions due to planned control room filtration train A surveillance testing on August 28, 2018

(5) Elevated risk actions due to planned switchyard breaker replacements on September 14, 2018

71111.15Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Component cooling water piping penetration degradation on August 15, 2018

(2) Engineered safety features actuation system surveillance results on August 16, 2018

(3) Emergency diesel generator fuel oil filtration on August 24, 2018

71111.17TEvaluations of Changes, Tests and Experiments

The inspectors evaluated the following from August 6-10, 2018:

10 CFR 50.59 Evaluations

(1) CA2512-16-05, modification package 13-0033, hardened condensate storage tank

(2) CA2512 Final Safety Analysis Report change to increase the maximum design bases accident temperature for class 1E equipment rooms

(3) CA2512 16-09 - procedure change (ODP-ZZ-00002) regarding when emergency diesel generator room ventilation supply fans are required

(4) CA2512 17-02 - LDCN 17-0003, volume control tank explosive atmosphere (forced oxidation)

10 CFR 50.59 Screening/Applicability Determinations

(1) CA2511-01160, modification package 17-0012, bypass (jumper) A ultimate heat sink fan motor high speed thermal overloads

(2) CA2511/OTN-AP-00003/002, hardened condensate storage tank

(3) CA2511/compensatory measures additions to OTO-ZZ-00012

(4) CA2511/OTN-GK-00001/050, control building heating, ventilation, air conditioning system

(5) CA2511/OTN-GK-00001/051, control building heating ventilation, air conditioning system

(6) CA2511/OTN-NG-00001/017, class 1E 480 heating ventilation, air conditioning electrical system

(7) CA2511-01088, MP 16-0036/201606214-modification of essential service water drains both component cooling water heat exchangers

(8) CA2511-01090, replacement of under frequency relay for reactor coolant pump motor

(9) CA2511/MP18-0045, NK battery replacement

(10) CA2511/OTN-EF-00001/073, essential service water system

(11) CA2511/EOPADD42/002, revise procedure to make the motor-driven auxiliary feedwater pumps available when the hardened condensate storage tank is aligned to auxiliary feedwater suction

(12) CA2511/OTS-PA-00001/022 - operation and testing of alternate power source

(13) CA2511/OTN-EP-00001 ADD3/009 - initial fill and vent of safety injection accumulators

(14) CA2511/17000810 - cycle KJHS0180 to maintain jacket water temp in proper temperature band

(15) CA2511/OTN-EB-00001 ADD1/007 - component cooling water equipment rotation and controlling temperature

(16) CA2511/night order and immediate operability determination compensatory measures for Condition Report 201802284

(17) CA2511/OTN-NG-00001/017, class 1E 480 heating ventilation, air conditioning electrical system

(18) CA2511/EOPADD42/002, make the motor-driven auxiliary feedwater pumps available when the hardened condensate storage tank is aligned to auxiliary feedwater suction

71111.18Plant Modifications

The inspectors evaluated modification package MP 07-0069, replace 480V load center circuit breakers with new Square D breakers.

71111.19Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) Battery charger NK22 after equipment outage on July 18, 2018

(2) Emergency exhaust system train A after equipment outage on August 8, 2018

(3) SGK04B modification after equipment outage on August 13, 2018

(4) Site 200 series electrical distribution after equipment outage on September 9, 2018

(5) Pressurizer backup heaters after equipment outage on September 21, 2018

===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:

Routine===

(1) Containment isolation signal slave relay train A test on August 2, 2018

(2) Ultimate heat sink cooling tower fan, trains A and B, test on August 22, 2018

In-service (2 Samples)

(1) Emergency service water pump train A in-service test on July 11, 2018

(2) Emergency diesel generator fuel oil system train B in-service test on July 25, 2018

71114.04Emergency Action Level and Emergency Plan Changes

The inspectors evaluated Procedure EIP-ZZ-00101, Classification of Emergencies, Revision 55 on September 13, 2018. This evaluation does not constitute NRC approval.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

(1) IE01: Unplanned Scrams per 7000 Critical Hours Sample (07/01/2017 - 06/30/2018)

(2) IE03: Unplanned Power Changes per 7000 Critical Hours Sample (07/01/2017 - 06/30/2018)

(3) IE04: Unplanned Scrams with Complications Sample (07/01/2017 - 06/30/2018)

71152Problem Identification and Resolution Annual Follow-up of Selected Issues

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Essential service water system thermal performance evaluation including inventory losses under Condition Report 201803313 on August 9, 2018

(2) Switchyard breaker trip, MDV52-2, under Condition Report 201803237 on July 28, 2018

71153Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports

The inspectors evaluated Licensee Event Report 2018-002-00, Inadequate Emergency Operating Procedure Guidance for Asymmetric Natural Circulation Cooldown on May 7, 2018, which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855Operation of an Independent Spent Fuel Storage Installation and 60857Review of 10 CFR 72.48 Evaluations The inspectors evaluated the licensees operation of the Independent Spent Fuel Storage Installation (ISFSI) from August 11-17, 2018, on-site at the Callaway Plant and conducted an in-office review of additional documentation, including quality assurance audit reports, condition reports, and documents related to the licensees maintenance of their ISFSI and related equipment.

The Callaway ISFSI is a 10 CFR Part 72 general licensed ISFSI and utilized the Holtec HI-STORM UMAX Storage System, approved under Certificate of Compliance 1040, License Amendment 0, UMAX Final Safety Analysis Report Revision 2, and HI-STORM FW Final Safety Analysis Report Revision 3. This storage system utilizes the multi-purpose canister (MPC-37)that stores 37 pressurized water reactor fuel assemblies in a below grade vertical ventilated module. Callaway had constructed the UMAX ISFSI to hold 48 MPC-37 canisters within the vertical ventilated modules at the site. The top ISFSI pad dimensions are 108.5 feet by 157.5 feet, configured in six rows of eight canisters. During the routine ISFSI inspection, Callaway was in the middle of their second loading campaign. Inspectors were onsite to observe the loading activities associated with canister number 4 out of 12 planned for the dry fuel storage campaign. By the end of the loading campaign, the licensee was expected to have a total of 18 canisters stored in the UMAX ISFSI.

The ISFSI activities specifically reviewed during the on-site inspection and the subsequent in-office review included:

(1) Evaluated and observed fuel selection and fuel loading operations associated with the 4th canister of the campaign (the 10th cask placed at the ISFSI)

(2) Evaluated and observed welding of the canister, non-destructive testing of the welds, pressure testing, forced helium drying, helium backfill, and heavy load movements from the spent fuel pool to the sites vertical cask transporter and into the vertical ventilated module

(3) Reviewed the licensee's loading, processing, and heavy load procedures associated with their current dry fuel storage campaign

(4) Reviewed the licensees corrective action program implementation for ISFSI operations since the last routine ISFSI inspection which was completed in January 2017

(5) Reviewed quality assurance program implementation, including recent quality assurance audits, surveillances, and quality control activities

(6) Reviewed documentation for compliance with Technical Specifications related to operational surveillance activities and Final Safety Analysis Report required annual maintenance activities

(7) Reviewed the licensees radiological monitoring data for the calendar years 2016 and 2017 to verify compliance with 10 CFR 72.104 requirements

(8) Reviewed spent fuel documentation for the canisters loaded since the last routine ISFSI inspection to verify the fuel met all technical specification requirements for storage (canisters 7-10)

(9) Reviewed annual maintenance activities for heavy lifting components which included special lifting devices and the sites cask handling crane

(10) Reviewed all 10 CFR72.48 safety evaluations/screenings performed by the licensee for changes made to the ISFSI program since the last routine ISFSI inspection in accordance with NRC Inspection Procedure 60857

(11) Reviewed all changes made to the licensees 10 CFR 72.212 report under the licensees 10 CFR 72.48 program (Reviewed changes from Revision 2 and Revision 3)

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71153Follow-up of Events and Notices of Enforcement Discretion This violation of very low safety significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. Section 6 of Appendix A to Regulatory Guide 1.33, Revision 2, requires procedures for combating emergencies and other significant events. The licensee established Emergency Operating Procedure (EOP) ES-0.2, Natural Circulation Cooldown, Revision 9, in part, to meet the regulatory requirement. Figure 1 of ES-0.2 allowed cooldown rates that exceeded the values used in the license basis for radiological consequence analyses and exceeded the values used in the design of the nitrogen accumulators for atmospheric steam dumps and turbine-driven auxiliary feedwater system actuations. This issue was discussed in Licensee Event Report 2018-002-00, Inadequate EOP Guidance for Asymmetric Natural Circulation Cooldown.

Contrary to the above, from April 29, 2008 through May 7, 2018, the licensee failed to maintain procedures for combating emergencies and other significant events. Specifically, the licensee failed to maintain EOPs for natural circulation cooldown. This performance deficiency resulted in atmospheric steam dumps and turbine-driven auxiliary feedwater systems being rendered inoperable due to depletion of the safety-related actuation nitrogen.

Significance/Severity Level: This performance deficiency was more than minor, and therefore a finding, because it adversely affected the procedure quality attribute of the Mitigating Systems Cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. As a result, the licensee would not have been able to reach shutdown cooling conditions and the plant would have been placed in a condition of being unable to control decay heat removal via atmospheric steam dumps.

Using Inspection Manual Chapter 0609, Attachment 4, Initial Characterization of Findings, and Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, dated June 19, 2012, the inspectors determined that the finding required a detailed risk evaluation since the finding represented an actual loss of function of at least a single train for greater than its technical specification allowed outage time. Specifically, as reported in Licensee Event Report 2018-002-00, Inadequate EOP Guidance for Asymmetric Natural Circulation Cooldown, atmospheric steam dumps and the turbine-driven auxiliary feedwater system were rendered inoperable, due to the inadequate EOP revision, in April 2008. As a result, this exceeded the allowed outage time for the associated Technical Specifications 3.7.4 and 3.7.5, respectively.

The senior reactor analyst reviewed the issue and determined that the issue was of very low safety significance, or Green. The senior reactor analyst noted that the impact of the performance deficiency on plant safety was limited to a steam line break leading to a consequential loss of offsite power. The frequency of all such events was estimated to be approximately 3.5 x 10-5/year, using values available in the plant-specific SPAR model.

According to the licensee, the design basis time that the nitrogen backup accumulators would provide motive force to the atmospheric steam dumps and the turbine-driven auxiliary feedwater flow control valves was 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a maximum realistic time available of approximately 16.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Therefore, the analyst used an average probability of nonrecovery of offsite power over a 12-hour period (6.2 x 10-2). Additionally, the licensee has two air compressors supplied by the vital diesel generators that would eliminate the demand for the nitrogen accumulators. Therefore, the analyst applied a generic value for the failure of a multi-train system (3.0 x 10-3). Using these assumptions, the analyst calculated the frequency of a steam line break with unrecovered loss of offsite power and a failure of the remaining two air compressors. This bounded the value of the incremental conditional core damage frequency to less than 6.5 x 10-9/year.

Corrective Action Reference: Condition Report 201802284.

Unresolved Item (Open)

Failure to perform 10 CFR 50.59 evaluation for compensatory measures associated with stagnant, inactive loop.05000483/2018003-01 71111.17T Evaluations of Changes, Tests and Experiments

Description:

The inspectors identified an unresolved item related to implementation of 10 CFR 50.59, Evaluations Changes, Tests and Experiments, for the licensees failure to perform an adequate evaluation for compensatory measures for a stagnant, inactive loop.

The licensee enacted compensatory measures to support atmospheric dump valve/turbine-driven AFW pump operability due to an issue identified for natural circulation cooldown with a faulted steam generator (i.e., inactive loop). A reduction in the Technical Specification 3.4.16 dose equivalent iodine (DEI) limit (from 1Ci/gm to 0.4Ci/gm) was imposed without a 10 CFR 50.59 evaluation and/or license amendment. Specifically, the licensee did not consider the compensatory measure of reducing Technical Specification 3.4.16 limits on DEI-131 as a change to technical specifications.

The licensee considered this a temporary action that did not meet the intent of 10 CFR 50.90 for a technical specification change.

Planned Closure Action: There is currently an NEI paper under review by the NRC Headquarters Technical Specification Branch and a draft Regulatory Guide that addresses the issue of non-conservative technical specifications and timely submittal of license amendment requests associated with them. This issue will be resolved based on the results of the Technical Specifications Branchs final decision on the subject.

Licensee Action: The licensee has entered the issue into their corrective action program.

Corrective Action Reference: Condition Report

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On August 10, 2018, the inspectors presented the Evaluations of Changes, Tests and Experiments inspection results to Mr. T. Herrmann, Site Vice President, and other members of the licensee staff.

On August 16, 2018, the inspectors presented the routine ISFSI inspection results to Mr. B. Cox, Senior Director Nuclear Operations, and other members of the licensee staff.

On August 22, 2018, the inspectors presented the annual requalification inspection results to Mr. M. Otten, Operations Training Manager, and other members of the licensee staff.

On September 26, 2018, the emergency preparedness inspector presented the results of the review of changes to the licensees emergency plan to Mr. G. Rausch, Manager, Emergency Preparedness, and other members of the licensee staff.

On October 3, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. T. Herrmann, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Procedure 71111.01: Adverse Weather Protection

Condition Reports

201001813

201706008

201702791

Procedures

Number

Title

Revision

ODP-ZZ-00017, Appendix 2

Technical Specification Related Annunciators

OOA-EF-00001

Ultimate Heat Sink Setpoint Levels

OTA-RK-00020

Annunciator Response Procedure MCB Panel

RK020

OTN-EF-00001

Essential Service Water System

Miscellaneous Documents

Number

Title

Revision

U-29-03-F

Ultimate Heat Sink Retention Pond - PMF

Determination

RFR 22267A

Approve replacement for EFLIS0027/27A

Inspection Procedure 71111.04: Equipment Alignment

Condition Reports

200701435

200901558

201701338

201706207

201801283

201801316

201803443

201804144

201804154

201804197

201804204

201804251

Procedures

Number

Title

Revision

APA-ZZ-00356

Pump and Valve Inservice Test Program

EDP-ZZ-01114

Motor Operated Valve Program Guide

EDP-ZZ-04107

HVAC Pressure Boundary Control

OSP-EG-0001A

CCW Train A Valve Alignment Surveillance

OSP-GG-0005B

B Train Fuel Building Negative Pressure Test 8

OTN-KC-00001, Addendum 19 Filling and Draining Fire Water Storage

Tanks

Drawings

Number

Title

Revision

E-23EF02B

Schematic Diagram ESW to SW System Isolation Valve

Miscellaneous

Documents

Number

Title

Revision

Fire Preplan Manual

Various

EF-15 Add 7

Essential Service Water System Fault Tree Model

RFR 22556

Clarify Note 3 on E-23Al09 for Foxboro Contact

A

RFR 23186B

Evaluate Using MOV-Long-Life Grease on all MOVs

ULNRC-GG-001

Fuel Building Ventilation System

Inspection Procedure 71111.05AQ: Fire Protection Annual/Quarterly

Condition Reports

201801575

201802736

201803613

Procedures

Number

Title

Revision

APA-ZZ-00750

Hazard Barrier Program

EDP-ZZ-04107

HVAC Pressure Boundary Control

FPP-ZZ-00009

Fire Protection Training Program

MTT-ZZ-00252

Installation of Flexible Fire Seals

Miscellaneous Documents

Number

Title

Revision

Fire Preplan Manual

Various

T66-1000 S

Drill Planning and Authorization

Various

Inspection Procedure 71111.06: Flood Protection

Condition Reports

201309387

201403831

201605812

201704709

201804053

Drawings

Number

Title

Revision

C-U203

ESWS Units 1 & 2 Electrical Manholes Plans, Sections &

Detail

Miscellaneous Documents

Number

Title

MP 09-0049

Evaluate method of preventing water intrusion into manhole MH01

Inspection Procedure 71111.11: Licensed Operator Requalification Program and

Licensed Operator Performance

Condition Reports

200700956

200702502

200903732

201406048

201804776

201804779

Procedures

Number

Title

Revision

APA-ZZ-00395

Significant Operator Response Timing

MPE-ZZ-QY054

Inspection and Test of Protective Lockout Relays, General

Electric Type HEA

ODP-ZZ-00001

Operations Department - Code of Conduct

104

ODP-ZZ-00003

Shift Relief and Turnover

Miscellaneous Documents

Title

Date

Annual Requalification Results Summary

July 6, 2018

Operations Night Orders

Inspection Procedure 71111.12: Maintenance Effectiveness

Condition Reports

201104544

201104651

201206896

201403496

201608165

201801489

201802184

Work Orders

397333

Procedures

Number

Title

Revision

APA-ZZ-00296

Gas Intrusion Program

APA-ZZ-00500, Appendix 11 Degraded and Nonconforming Condition

Resolution

EDP-ZZ-01128

Maintenance Rule Program

EDP-ZZ-01128, Appendix 2

Summary of SSC Performance Criteria

EDP-ZZ-01128, Appendix 4

Maintenance Rule System Functions

Drawnings

Number

Title

M-22EG03

Piping and Instrument Diagram - Component Cooling Water

Miscellaneous Documents

Number

Title

EG-54

Allowable Gas Void Volume for Each Train of the Component Cooling

Water Suction Piping

EG-55

Water Hammer due to Voids in Component Cooling Water System Piping

MP 10-0042

Install New CCW/Radwaste Flow Restriction Device

Inspection Procedure 71111.13: Maintenance Risk Assessments and Emergent Work

Control

Condition Reports

200706552

201011290

201705555

201706032

201707194

201804887

Work Orders

18000637

18002661

18507861

Procedures

Number

Title

Revision

APA-ZZ-00322

Integrated Work Management Process Description

APA-ZZ-00322,

Appendix F

Online Work Integrated Risk Management

APA-ZZ-00356

Pump and Valve Insrvice Test Program

OSP-EJ-V001A

Train A RHR Valve Inservice Test

OSP-EJ-P001A

RHR Train A Inservice Test

OSP-GK-0001A

A Train Control Room Filtration and Pressurization

System Monthly Operability Verification

OSP-SA-0009B

Train B CISA Slave Relay Test

Drawings

Number

Title

Revision

8618-X-94080

One Line Diagram Metering and Relaying 345KV

Differential and 345KV Bus-A and B Pot. Devices

Miscellaneous Documents

Number

Title

RFR 019023A

Determine Retest Requirements for MDV41V511

Inspection Procedure 71111.15: Operability Determinations and Functionality

Assessments

Condition Reports

199400711

199701249

199901106

201010145

201801641

201804251

201804276

Work Orders

10002666

Procedures

Number

Title

Revision

OTS-JE-00002

Filtration of Emergency D/G Fuel Oil

Inspection Procedure 71111.17T: Evaluations of Changes, Tests and Experiments

Condition Reports

201403041

201601534

201603312

201608686

201700966

201702032

201703841

201704156

201707651

201802284

201803910

201803973

201804069

Calculations

Number

Title

Revision

81402-C-010

Design of Safety Related Pipe Supports for HCST Piping

81402-S-005

Pipe Stress and Support Load Evaluation of HCST Supply

Line to Safety-Related Auxiliary Feedwater System

Suction

GK-19, Addendum 3

2016 Auxiliary Building Battery and SWBD room GOTHIC

temperature analysis

GM-03

EDG Room Temperatures w/o HVAC

GM-03, Addendum 1 EDG Room Temperature Analysis With Both Air Supply

Fans Unavailable

GM-03, Addendum 2 Inputs

GM-320

Diesel/Generators Building HVAC

GM-320,

Addendum 2

Diesel Generator Building HVAC Update

M-FL-04,

Addendum 6

Impact of MP 13-0033 - Hardened Condensate Storage

Tank Refuel 21 Tie-Ins

NAI-1719-001

Callaway Control Building Loss of Class 1E A/C GOTHIC

Room Heat Up Analysis

NAI-1719-001,

Addendum 1

Control Building Temperature Analysis for Operability

Evaluation

NAI-1719-002

Callaway Control Building with Control Room Loss of

Class 1 E A/C GOTHIC Room Heat Up Analysis

NAI-1719-004

Callaway Control Building with Control Room Loss of

Class 1 E A/C GOTHIC Room Heat Up With Installed

Fans and Louvers

NG-12,

Addendum 27

NG MCC Setpoint Calculation

NG-22, Addendum 6 NG Load Center Setpoint Calculation

Procedures

Number

Title

Revision

APA-ZZ-00108

Primary Licensing Documents: Change/Revision Process

APA-ZZ-00143

CFR 50.59 and 10 CFR 72.48 Reviews

APA-ZZ-00600

Design Change Control

EDP-ZZ-04600

Engineering Change Control

ES-1.1

SI Termination

ES-1.1

SI Termination

ES-0.2

Natural Circulation Cooldown

ES-0.2

Natural Circulation Cooldown

ES-0.2

Natural Circulation Cooldown

ES-0.2

Natural Circulation Cooldown

FDP-ZZ-00103

License Document Change Process

IP-ENG-001

Standard Design Process

OTN-EF-0001

Essential Service Water System

OTN-EF-0001

Essential Service Water System

OTN-EF-0001

Essential Service Water System

ODP-ZZ-00002

Equipment Status Control

ODP-ZZ-00002

Equipment Status Control

ODP-ZZ-00002

Equipment Status Control

OTN-EB-00001,

Addendum 1

Closed Cooling Water System - Equipment Rotation and

Controlling Temperature

OTN-EP-00001,

Addendum 1

SI Accumulator Level Control

6, 7

OTN-EP-00001,

Addendum 3

Initial Fill and Vent of SI Accumulators

8, 9

OTN-GK-00001

Control Building HVAC System

OTS-PA-00001

Operation and Testing of the Alternate Emergency Power

Source

Drawings

Number

Title

Revision

8600-X-90422

Storeroom 2 Power Plan Receptacles

8600-X-90424

Storeroom 2 Lighting Plan

EA04-H006-332

Pipe Supports, Service Water System

Communication Corridor

EA04-H007-332

Pipe Supports, Service Water System

Communication Corridor

EA04-H011-332

Pipe Supports, Service Water System

Communication Corridor

E-009-00081

Metal-Clad Switchgear - Title Sheet Electrical

Diagram

E-009-00190

Metal-Clad Switchgear - Indoor

E-009-00250

IM 13.8 KV Class 1E Potential Transformer

Component

E-009-00252

Metal-Clad Switchgear - Interconnection

Diagram

E-009-00262

Metal-Clad Switchgear - Equipment Summary

E-009-00339

AZZ Qualification Report for Frequency Relay

ABB P/N 422C1276

E-018-00172

SZ 5 2SP-1WD Schematic

E-018-00223

Wiring Diagram 2SP-1WD (SIZE 5)

E-21NK01

Class 1E 125V DC System - Meter & Relay

Diagram

E-21NK02

Class 1E 125V DC System - Meter & Relay

Diagram

E-050-00006

Batteries - 60 Cell NCN-23 Layout ON-2-S07-

074530-816 Racks

E-050-00009

Layout For 60 Cell NCN-13 Battery ON-2-507-

074520-816 Racks 10'-0" LG

E-050-00032

Batteries - NCX-NAX Typical Termination

Assemblies

E-U1NG01

Low Voltage System - Class IE 480V Single

Line Meter And Relay Diagram

E-U3EF02A

Schematic Diagram - Ultimate Heat Sink

Cooling Tower Fans

GB01-H001-332

Pipe Supports, Central Chilled Water System

Pumps Suction & Discharge

GB02-H003-332

Pipe Supports, Central Chilled Water System

Pumps Suction & Discharge

M-22AL01(Q)

Piping and Instrumentation Diagram Auxiliary

Feedwater System

M-22EA01

Piping And Instrumentation Diagram Service

Water System FSAR Figure 9.2 -1 Sheet 1

M-22EG02

Piping & Instrumentation Diagram Component

Cooling Water System FSAR Figure 9.2-3

Sheet 2

M-22EG22

Small Piping Isometric Component Cooling

Water System Auxiliary Building Location 141

M-22GB01

Piping And Instrumentation Diagram Central

Chilled Water System FSAR Figure 9.4-10

M-23EA04

Piping Isometric - Service Water System

Comm. Corridor (Central Chillers)

M-23EG23

Small Piping Isometric Component Cooling

Water System Auxiliary Building Location 142

M-29EG22

Hanger Location Dwg Small Pipe Component

Cooling Water System Auxiliary Building

Location 141

M-29EG23

Hanger Location Dwg. Small Pipes Component

Cooling Water System Auxiliary Building

Location 142

Miscellaneous Documents

Number

Title

Revision or

Date

2005 ASHRAE Handbook Fundamentals

Callaway FSAR, Various Chapters

AABD 6.0

Callaway Energy Center Accident Analysis Basis

Document Feedwater System Pipe Break

6A

ANSI/IEEE C37.9-1979

Test Procedure for AC High-Voltage Circuit

Breakers Rated on a Symmetrical Current Basis

EDN-01

Engineering Design Notice, MP 13-0002

EDN-02

Engineering Design Notice, MP 13-0002

IB 7.4.1.7-5

ABB Circuit Shield Type 81 Series 422, Vendor

Manual

IEEE Std 323-1974

IEEE Standard for Qualifying Class 1E Equipment

for Nuclear Power Generating Stations

IEEE Std 450-1995

IEEE Recommended Practice for Maintenance,

Testing, and Replacement of Vented Lead-Acid

Batteries for Stationary Applications

LTR-LIS-18-182

1, Review of Mitigating Strategy for

Stagnant/Voided Loop as the Result of Asymmetric

Natural Circulation

NUREG-0830,

Supplement No. 3

Safety Evaluation Report Related To The Operation

Of Callaway Plant, Unit 1

RFR 15642

Formal Safety Evaluation

A, B

RFR 201104353

Class 1E Electrical Equipment Survivability

RFR 201403041

Class 1E Electrical Equipment Survivability

STARS-ENG-5001-8.1

Replace EDG Fans CGM01A & B

September 4,

2012

STARS-ENG-5001-8.1

Hardened Condensate Storage Tank Refuel 21

Tie-Ins

February 23,

2015

Inspection Procedure 71111.18: Plant Modifications

Condition Reports

201502453

201701626

201704103

201800905

201800917

201801692

201802679

Work Orders

11005902

11005918

15502053

17502428

Procedures

Number

Title

Revision

EDP-ZZ-04600

Engineering Change Control

Miscellaneous Documents

Number

Title

Revision

or Date

CA2883

Technical Task Job Brief Checklist

June 8, 2016

LD-351023928-1

Masterpact Breaker

MP 07-0069

Replace 480V Load Center Circuit Breakers

NG-12

NG MCC Setpoint Calculation

SVP-133

Standard Verification Plan

TB-12-007

Masterpact Breakers Fail to Close

Inspection Procedure 71111.19: Post Maintenance Testing

Condition Reports

200408234

201801437

201803246

201803541

Work Orders

2501352

2002857

2003896

2508243

15000794

15511559

17501719

17502428

Procedures

Number

Title

Revision

APA-ZZ-00322 App E

Post-Maintenance Test Program

MPE-NK-QB004

NK Class 1E Battery Charger Inspection

OSP-BB-00002

PZR Heater Capacity Test

OSP-SA-0009B

Train A CISA Slave Relay Test

OTN-BB-00005

Pressurizer and Pressure Control

OTN-NK-00001 Add 2

25VDC Bus NK03 and Distribution System

OTN-PG-00001

480 VAC Non-Class 1E Electrical System

OTO-ZZ-00012

Severe Weather

Drawings

Number

Title

Revision

E-23BB25

Pressurizer Heater Backup Group B Heater

Grouping

Miscellaneous Documents

Number

Title

ULNRC

Revise Ventilation System Surveillance Requirements to Operate for

Hours per Month

Inspection Procedure 71111.22: Surveillance Testing

Condition Reports

200600435

201001813

201206883

201804199

Work Orders

18003285

18504656

Procedures

Number

Title

Revision

APA-ZZ-00340

Surveillance Program Administration

ISL-EF-00T67

Loop-TMP: ESW A Cool Twr Inlet and Pump

Discharge Temperatures

OSP-EF-P001A

ESW Train A Inservice Test

OSP-JE-P001B

Train B Emergency Diesel Generator Fuel Oil

System In-service Tests

Miscellaneous Documents

Number

Title

Revision

AL-20

Evaluation of Tolerances for Fixed Parameters used in

IST Pump Surveillances

ULDBD-EF-001

Essential Service Water System

Inspection Procedure 71151: Performance Indicator Verification

Condition Reports

201501431

Miscellaneous Documents

Title

Revision

NRC Performance Indicator Transmittal Report

Various

Inspection Procedure 71152: Problem Identification and Resolution

Condition Reports

201705467

201705575

201800563

201800905

201801274

201801348

201801489

201801502

201801684

201801925

201802184

201802547

201803237

201803245

201803286

201803706

201803313

201803781

201803852

201804116

201804149

201804251

201804807

Work Orders

18002574

Miscellaneous Documents

Number

Title

Revision

RFR 180142

Add Splice inside MH 59-50 and remove splice inside pull

box between MH 59-50 and MH 59-51 to Cable CA-3618

Inspection Procedure 71153: Follow-up of Events and Notices of Enforcement Discretion

Condition Reports

201803580

Procedures

Number

Title

Revision

APA-ZZ-00102

EOP/OTO Writers Manual

E-3

Steam Generator Tube Rupture

ES-0.2

Natural Circulation Cooldown

ODP-ZZ-00025

EOP/OTO Users Guide

Inspection Procedure 60855: Operation of an Independent Spent Fuel Storage

Installation and Inspection Procedure 60857: Review of 10 CFR 72.48 Evaluations

Condition Reports

201605802

201700196

201700328

201700621

201700649

201700652

201702372

201702969

201703274

201703295

201704069

201704732

201800292

201800328

201800713

201800920

201801469

201801531

201802109

201803118

201803195

201803220

201803274

201803310

20180402

201803404

201803406

201803430

201803434

201803457

201803464

201803465

201803559

Work Orders

15506408-500

15506409-500

15506643-500

Procedures

Number

Title

Revision

MC-GTAW

Machine Gas Tungsten Arc Welding

APA-ZZ-00143

CFR 50.59 and 10 CFR 72.48 Reviews

APA-ZZ-00500

Corrective Action Program

APA-ZZ-01600

Dry Fuel Storage Program

ETP-ZZ-04020

Fuel Selection and Cask Loading for Dry Cask

Storage

ETP-ZZ-04021

ISFSI Loading Campaign Performance

ETP-ZZ-04022

Pre-Operation Inspection

ETP-ZZ-04023

MPC Loading

ETP-ZZ-04024

MPC Sealing, Drying, and Backfill Operations

ETP-ZZ-04025

MPC Transfer

ETP-ZZ-04026

MPC Unloading

ETP-ZZ-04027

Responding to Abnormal Conditions

FDP-ZZ-00105

CFR 72.212 Report Maintenance

GQP-9.2

Liquid Penetrant Exam

GQP-9.6

Visual Examination of Welds

MSLT-MPC

Helium Leak Test

Cal-1

MPM-KE-QH001

Cask Handling Crane Inspection

OSP-ZZ-00001

Control Room Shift and Daily Log Readings

and Channel Checks

PI-CNSTR-OP

Closure Welding MPC

Design Basis Documents

Number

Title

Revision

CoC 1040

Certificate of Compliance 1040 Holtec

HI-STORM UMAX Storage System

FSAR 1040

FSAR for Holtec HI-STORM UMAX Storage

System

FSAR 1032

FSAR for Holtec HI-STORM FW Storage

System

2.212

Callaway 10 CFR 72.212 Report

2.48 Applicability Determinations and 72.48 Screens

CA2510

CA3163

ECO-102-24

ECO-105-17

ECO-105-21

ECO-5018-75

ECO-5021-27

ECO-5021-29

ECO-5021-31

MP13-0009

MP 17-0007

1154R0

29R0

242R0

285R0

Miscellaneous

Documents

Number

Title

Revision or Date

180000747Close

Specific Radiation Work Permit

180000747Trans

Specific Radiation Work Permit

180000747Trans

Specific Radiation Work Permit

18001046

Calibration Test Report

July 25, 2018

18001047

Calibration Test Report

August 1, 2018

ALARA Plan

2018 -ISFSI Project ALARA Package

CA-M-20180430-2

Survey of ISFSI Pad Quarterly Q217

April 30, 2018

DOC-104-209-105

MPC FW Lift Cleat Assembly Leased

March 27, 2018

ETP-ZZ-0420

Fuel Characteristics for Canister #7-10

HSP-355

Periodic Inspection and Recertification of SLD

RWP-18DFS

General Radiation Work Permit

TLD Data

2016 and 2017 ISFSI Fence TLD Data

Initial Request for Information

Quarterly Baseline Inspection

Callaway Plant

Inspection Report: 05000483/2018003

Inspection Dates: July 1 - September 30, 2018

Inspection Procedure: IP 71111 series, IP 71151, IP 71152

Lead Inspector: Dan Bradley, Senior Resident Inspector

Information Requested For 3rd Quarter 2018

The following information should be sent to the resident office in electronic format (Certrec IMS

preferred) to the attention of Dan Bradley by July 26, 2018. Please provide requested

documentation electronically in pdf files, Excel, or other searchable formats, if possible. The

information should contain descriptive names and be indexed or hyperlinked to facilitate ease of

use. If requested documents are large and/or only hard copy formats are available, please

inform the inspector for clarification.

Please provide the following information for the Component Cooling Water (EG) system:

1.

A list of all calculations and drawings associated with the selected system.

2.

A list of condition reports associated with the selected system for the last 3 years.

3.

A list of work orders associated with the selected system for the last 3 years, including

all open work orders.

4.

A list of any pre-existing evaluations or calculations with low design margins for the

selected system.

5.

A copy of the last 3 heat exchanger inspections including performance data for the

selected system.

6.

A list of maintenance rule components and functions; based on engineering or expert

panel judgment, for the selected system.

7.

A list of maintenance rule functional failure evaluations for the last 3 years for the

selected system.

8.

A list of operating experience evaluations for the last 3 years for the selected system.

9.

A list of all procedures and calculations that involve time-critical operator actions.

10. A list of permanent and temporary modifications performed in the past 3 years for the

selected system. Include a list of any documents associated with modifications such as:

calculations, specifications, vendor manuals, Final Safety Analysis Report, Technical

Specifications and Bases updates, updated procedures, and maintenance and

surveillance activities and procedures.

11. A list of root cause and apparent cause evaluations associated with component failures

or design issues initiated/completed in the last 3 years for the selected system.

2. A list of any common-cause failures of components in the last 3 years for the selected

system.

13. An electronic copy of the design bases documents for the selected system.

14. An electronic copy of the system health notebooks for the selected system.

Additionally, please provide the basis documents used to compute or establish the following

NRC Performance Indicators (PIs) for the most recent 4 quarters which data is available:

a) IE-01: Unplanned Scrams per 7000 Critical Hours

b) IE-03: Unplanned Power Changes per 7000 Critical Hours

c) IE-04: Unplanned Scrams with Complications

Inspector Contact Information:

Dan Bradley

Senior Resident Inspector

573-676-3181

Dan.Bradley@nrc.gov

Mailing Address:

U.S. NRC Resident Inspector Office

201 NRC Road

Steedman, MO 65077

ML18295A010

SUNSI Review

By: NHT/RDR

Non-Sensitive

Sensitive

Publicly Available

Non-Publicly Available

Keyword:

NRC-002

OFFICE

SRI/DRP/B

RI/DRP/B

C:DRS/EB1

C:DRS/EB2

C:DRS/OP

C:DRS/PSB2

NAME

DBradley

SJanicki

TFarnholtz

GWerner

VGaddy

HGepford

SIGNATURE

/RA/

/RA/

/RA/

/RA/

/RA/

/RA/

DATE

10/19/18

10/16/18

10/09/2018

10/11/2018

10/9/18

10/15/18

OFFICE

TL:DRS/IPAT

DNMS:FCDB

C:DRP/B

NAME

GGeorge

JKatanic

NTaylor

SIGNATURE

/RA -

HFreeman for/

/RA/

/RA/

DATE

10/09/2018

10/15/2018

10/19/2018