IR 05000440/2014007

IR 05000440-14-007, on 03/03/2014 & 04/04/2014; Perry Nuclear Power Plant. Component Design Bases Inspection (CDBI)

ML14128A310
Person / Time
Site:	Perry
Issue date:	05/07/2014
From:	Ann Marie Stone NRC/RGN-III/DRS/EB2
To:	Harkness E FirstEnergy Nuclear Operating Co
Andrew Dunlop
References
IR-14-007
Download: ML14128A310 (24)

Text

May 7, 2014

SUBJECT:

PERRY NUCLEAR POWER PLANT COMPONENT DESIGN BAS ES INSPECTION 05000 440/2014007

Dear Mr. Harkness

On April 4, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed a Component Design Bases Inspection (CDBI)

inspection at your Perry Nuclear Power Plan The enclosed report documents the results of this inspection, which were discussed on April 4, 2014, with Mr. D. Reeves, and other members of your staf The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your licens The inspectors reviewed selected procedures and records, observed activities, and interviewed personne No findings were identified during this inspection

. In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chie f Engineering Branch 2 Division of Reactor Safety Docket No. 50-440 License No. NPF-58

Enclosure:

Inspection Report 05000 440/20 14007 w/Attachment: Supplemental Information

REGION III==

Docket No:

50-440 License N o: NPF-58 Report No:

05000 440/20 14007 Licensee: FirstEnergy Nuclear Operating Company (FENOC)

Facility: Perry Nuclear Power Plant, Unit 1 Location: Perry, Ohio Dates: March 3 - 7, 2014; March 17 - 21, 2014, and March 31, through April 4, 2014 Inspectors:

A. Dunlop, Senior Engineering Inspector, Lead J. C orujo-Sandin, Engineering Inspector, Mechanical C. Brown, Engineering Inspector, Electrical C. Moore , Operations Inspector S. Kob ylarz, Electrical Contractor M. Yeminy, Mechanical Contractor Approved by:

Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety 2

SUMMARY OF FINDINGS

IR 05000440/20 14007 , 03/03/2014

- 0 4/04/2014; Perry Nuclear Power Plant. Component Design Bases Inspection (CDBI)

The inspection was a 3

-week onsite baseline inspection that focused on the design of components. The inspection was conducted by regional engineering inspectors and t wo consultants. No finding s or violations of significance were identified by the inspectors. The significance of inspection findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using IMC 0609, "Significance Determination Process" dated June 2, 2011.

All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy dated January 28, 201 3. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG

-1649, "Reactor Oversight Process" Revision 4, dated December 2006.

A. NRC-Identified

and Self-Revealed Findings No findings of significance were identified.

B. Licensee-Identified Violations

No violations were identified.

3

REPORT DETAILS

1R21 Component Design Bases Inspection

(71111.21)

.1 Introduction

The objective of the component design bases inspection is to verify that design bases have been correctly implemented for the selected risk significant components and that operating procedures and operator actions are consistent with design and licensing bases. As plants age, their design bases may be difficult to determine and an important design feature may be altered or disabled during a modification. The Probabilistic Risk

-Assessment (PRA) model assumes the capability of safety systems and components to perform their intended safety function successfully. This inspectable area verifies aspects of the Initiating Events, Mitigating Systems, and Barrier Integrity cornerstones for which there are no indicators to measure performance.

Specific documents reviewed during the inspection are listed in the to the report.

.2 Inspection Sample Selection Process

The inspectors used information contained in the licensee's PRA and the Perry Standardized Plant Analysis Risk Model to identify a scenario to use as the bas is for component selection. The scenario selected w as a Loss of Condenser Heat Sink event. Based on th is scenario, a number of risk significant components, including those with Large Early Release Frequency (LERF) implications, were selected for the inspection.

The inspectors also used additional component information such as a margin assessment in the selection process. This design margin assessment considered original design reductions caused by design modification, power uprates, or reductions due to degraded material condition. Equipment reliability issues were also considered in the selection of components for detailed review. These included items such as performance test results, significant corrective actions, repeated maintenance activities, Maintenance Rule (a)(1) status, components requiring an operability evaluation, NRC resident inspector input of problem areas/equipment, and system health reports. Consideration was also given to the uniqueness and complexity of the design, operating experience, and the available defense in depth margins. A summary of the reviews performed and the specific inspection findings identified are included in the following sections of the report.

The inspectors also identified procedures and modifications for review that were associated with the selected components. In addition, the inspectors selected operatin g experience issues associated with the selected components.

This inspection constituted 20 samples as defined in Inspection Procedure 71111.21-0 5.

.3 Component Design

a. Inspection Scope

The inspectors reviewed the Updated Safety Analysis Report (USAR), Technical Specifications (TS), design basis documents, drawings, calculations and other available design basis information, to determine the performance requirements of the selected components. The inspectors used applicable industry standards, such as the American Society of Mechanical Engineers (ASME) Code, Institute of Electrical and Electronics Engineers (IEEE) Standards and the National Electric Code, to evaluate acceptability of the systems' design. The NRC also evaluated licensee actions, if any, taken in response to NRC issued operating experience, such as Bulletins, Generic Letters (GLs),

Regulatory Issue Summaries (RISs), and Information Notices (INs). The review was to verify that the selected components would function as designed when required and support proper operation of the associated systems. The attributes that were needed for a component to perform its required function included process medium, energy sources, control systems, operator actions, and heat removal. The attributes to verify that the component condition and tested capability was consistent with the design bases and was appropriate may include installed configuration, system operation, detailed design, system testing, equipment and environmental qualification, equipment protection, component inputs and outputs, operating experience, and component degradation.

For each of the components selected, the inspectors reviewed the maintenance history, preventive maintenance activities, system health reports, operating experience

-related information, vendor manuals, electrical and mechanical drawings, and licensee Corrective Action Program documents.

Field walkdowns were conducted for all accessible components to assess material condition and to verify that the as

-built condition was consistent with the design. Other attributes reviewed are included as part of the scope for each individual component.

The following 16 components , two with LERF implications, were reviewed:

Residual Heat Removal (RHR) Pump B (1E12-C0002B): The inspectors reviewed hydraulic calculations to ensure design requirements for flow and pressure were translated as acceptance criteria for pump in

-service testing (IST). The inspectors reviewed IST results to assess potential component degradation and impact on design margins. Surveillance procedures for the RHR pump were reviewed to ensure TS surveillance requirements were met. The inspectors reviewed start/stop pump control logic and the different modes of operation of the RHR pump to ascertain that the pump would operate as designed during accident and most limiting conditions.

Pump protection logic and interlocks were reviewed to verif y appropriate testing. Maintenance and calibration procedures were reviewed to ensure instrument setpoints were consistent with design basis assumptions. In addition, the licensee actions to NRC Bulletin 88

-04, "Potential Safety-Related Pump Loss," were reviewed to ensure pump minimum flow requirements were addressed. The inspectors reviewed elementary diagrams to confirm that the pump operation conformed to the design requirements. The one-line diagram and the motor protective relay setting calculation were reviewed to confirm relay calibration testing verified the proper setting and operation for the protective relays. The inspectors also verified adequate control voltage was available for operation of the motor circuit breaker close circuit.

Voltage drop calculations were reviewed to determine whether the motors had adequate voltage for starting and running under degraded voltage conditions and the motor circuit cabling had adequate ampacity.

The inspectors confirmed the adequacy of the motor size based on worse case design conditions affecting pump break horsepower.

RHR Pump B Room Cooler (M39

-B001B): The inspectors reviewed the analysis of the room coolers heat removal capability with respect to heat load, fouling factors, air flow rate

, and water flow rate to verify the capability of the room cooler to maintain the room temperature at or below the design temperature of the safety-related components located in the room.

The inspectors reviewed the modeling of the room cooler into the Aerofin computer program used to assess operation of the cooler at the design conditions.

The inspectors also reviewed the cooler's test procedures, test frequency, and analyzed the validity of test results with respect to air flow rates and impact on the coolers fan motor. The elementary diagrams were reviewed to confirm that the fan operation conformed to the design requirements. The inspectors reviewed the one

-line diagram and the motor overload protection selection calculation to confirm proper selection of the motor circuit and motor overload protection. The inspectors verified adequate control voltage was available for operation of the motor starter contactor.

Voltage drop calculations were reviewed to determine whether the motors had adequate voltage for starting and running under degraded voltage conditions and the motor circuit cabling had adequate ampacity. The inspectors confirmed the adequacy of the motor size based on worse case design conditions affecting fan break horsepower.

RHR Test Return Valve (1E12

-F0 024B): The inspectors reviewed motor-operated valve (MOV) calculations and analys es to ensure the valve was capable of functioning under design conditions. These included calculations for required thrust, maximum differential pressure (d/p), and valve weak link analysis. Diagnostic testing and IST surveillance results, including stroke ti me , seat leakage, and available thrust, were reviewed to verify acceptance criteria were met and performance degradation could be identified.

Control logic and elementary diagrams were reviewed to confirm operation of the valve conformed to design requirements and operating procedures. The inspectors reviewed the circuit protection, the thermal overload application, and the environmental qualification of the motor operator to confirm the circuit was adequately protected and the valve was capable of performing its intended safety function. Voltage drop calculations were reviewed to verify the motor and associated control circuits had adequate voltage under degraded voltage conditions. The inspectors also inspected the valve for actuator orientation, proper greasing, and ability to be manually operated.

Low Pressure Coolant Injection Valve (1E 1 2-F0 0 4 2C): The inspectors reviewed MOV calculations and analys es to ensure the valve was capable of functioning under design conditions. These included calculations for required thrust, maximum d/p, and valve weak link analysis. Diagnostic testing and IST surveillance results, including stroke time, seat leakage, and available thrust, were reviewed to verify acceptance criteria were met and performance degradation could be identified.

The inspectors reviewed control logic and elementary diagrams to confirm operation of the valve conformed to design requirements and operating procedures. This included the procedures used to override the actuator's seal

-in circuit such that the valve could be throttled to control reactor vessel level to ensure the valve would continue to be able to perform its design functions in this mode of operation. In addition, the open permissive signals to the valve were reviewed to ensure the settings would protect the RHR piping from being over pressurized. The inspectors also reviewed the circuit protection, the thermal overload application, and the environmental qualification of the Limitorque motor operator to confirm that the circuit was adequately protected and that the valve was capable of performing its intended safety function during a design basis accident. Voltage drop calculations were reviewed to verify the motor and associated control circuits had adequate voltage under degraded voltage conditions. The inspectors reviewed the actuator for proper orientation, greasing and ability to be manually operated

and the procedures to prevent over torqueing in the manual mode.

Emergency Service Water (ESW) Pump B (1P45-C0001B): The inspectors reviewed hydraulic calculations pump line up, capacity and IST to ensure that the pump was capable of performing its safety functions during the most limiting design conditions. The inspectors reviewed the pressure loss due to the discharge strainer and licensee actions in response to GL 89

-13, "Service Water System Problems Affecting Safety

-Related Equipment.

" The inspectors reviewed elementary diagrams to confirm that the pump operation conformed to the design requirements. The one

-line diagram and the motor protective relay setting calculation was reviewed to confirm that relay calibration testing verified the proper setting and operation for the protective relays. The inspectors also verified adequate control voltage was available for operation of the motor circuit breaker close circuit. Voltage drop calculations were reviewed to verify the motors had adequate voltage for starting and running under degraded voltage conditions and the motor circuit cabling was adequate. The inspectors confirmed the adequacy of the motor size based on worse case design conditions affecting pump break horsepower.

ESW Pump Discharge Strainer (1P45

-D0002B): The inspectors reviewed performance data provided in the design procurement specifications and vendor documents for th e full-flow automatic backwash strainer to verify performance assumptions in the ESW Train B system flow balance and hydraulic calculation. Calculations for normal and design basis accident conditions were reviewed to verify sufficient ESW system flow was available and operators were capable of manually backwashing the strainer upon loss of offsite power.

The inspectors also reviewed worst case plugging of the strainer and the capability of the system to operate under this condition.

The power requirements for the strainer and backwash valves were reviewed to confirm operation of the automatic backwashing strainer conformed to design requirements and operating procedures.

The inspectors also reviewed the available pressure instrumentation as well as the capability of operators to determine the pressure drop across the strainer in case of loss of offsite power.

In addition, the inspectors verified the high pressure drop alarm was properly set and consistent with the value used in design calculations.

Elementary diagrams were reviewed to confirm the pump operation conformed to the design requirements. The inspectors reviewed the one-line diagram and the motor protective relay setting calculation to confirm relay calibration testing verified the proper setting and operation for the protective relays. The inspectors also verified that adequate control voltage was available for operation of the motor circuit breaker close circuit.

Voltage drop calculations were reviewed to verify the motors had adequate voltage for starting and running under degraded voltage conditions and the motor circuit cabling was adequate. The inspectors confirmed the adequacy of the motor size based on worse case design conditions affecting break horsepower.

ESW Pump B Discharge Check Valve (1P45

-F501B): The inspectors reviewed vendor drawings system isometrics and operating procedures to determine whether system design basis conditions were accounted for in the design of the check valve.

The IST procedure and test results were reviewed to verify valve freedom of motion and to ensure that the valve allow ed required flow in the open position and limit ed backflow in the closed position to avoid air voids in the discharge piping.

Automatic Depressurization System (ADS) Safety Relief Valve (F0051G) and Solenoid Valve (1B21-F444A): The inspectors reviewed the pneumatic requirements for operating the components, including the safety

-related instrument air supply storage tank sizing calculations and appropriate component testing in order to ensure the system is allowed leakage requirements were met. The review included original design specifications and pre

-operational testing of the safety relief valve (SRV) to ensure the component could operate under limiting design basis conditions. Testing was reviewed for compliance with applicable IST requirements and approved license amendments. In addition, the inspectors reviewed elementary diagrams to confirm SRV operation conformed to the design requirements. The inspectors reviewed 125Vdc voltage drop calculations to confirm the SRV solenoid valves received adequate voltage to operate during the most limiting battery conditions and the cabling to the solenoid valve had adequate ampacity. The inspectors also reviewed the preventive maintenance to confirm the solenoid coils were maintained in accordance with the equipment qualification requirements

. Emergency Closed Cooling (ECC) Water System Pump B (1P42

-C0001B): The inspectors reviewed the basis for the pump's performance test acceptance criteria, pump performance IST procedure s and results of the most recent test to verify current performance. Part of the review included the testing of required interlocks during design basis events, adequate flow to the system loads

, and adequate net positive suction head (NPSH) for the required mission time.

The inspectors reviewed elementary diagrams to confirm pump operation conformed to the design requirements. The one

-line diagram and the motor protective relay setting calculation were reviewed to confirm relay calibration testing verified the proper setting and operation for the protective relays. The inspectors also verified adequate control voltage was available for operation of the motor circuit breaker close circuit. The voltage drop calculations were reviewed to verif y the motors had adequate voltage for starting and running under degraded voltage conditions and the motor circuit cabling ampacity was adequate.

The inspectors confirmed the adequacy of the motor size based on worse case design conditions affecting pump break horsepower.

Emergency Closed Cooling Heat Exchanger (1P42

-B00011B): The inspectors reviewed recent thermal performance tests and associated calculations to ensure the equipment was capable of removing the required heat under design basis conditions.

Previously completed internal inspections results were also reviewed in order to evaluate for potential component degradation or fouling concerns.

The heat exchanger's tube plugging limit, tube plug g in g criteria , and chemistry control procedures were reviewed to ensure the heat exchanger remained within its heat removal requirement.

Emergency Closed Cooling Temperature Control Valve (1P42

-F0665B): Inspectors reviewed for potential impacts to the plant based on postulated failures of the component. The established temperature setpoints and associated tolerances were reviewe d to ensure they did not impact the design basis assumptions during an accident.

Aspects of the seismic mounting for the component were also reviewed.

The control logic and elementa ry diagrams were reviewed to confirm operation of the valve conformed to design requirements and operating procedures. The inspectors reviewed the circuit protection, the thermal overload application, and the environmental qualification of the valve operator to confirm the circuit was adequately protected and the valve was capable of performing its intended safety function during a design basis accident. Voltage drop calculations were reviewed to determine whether the motor and associated control circuits had adequate voltage under degraded voltage conditions.

Emergency Closed Cooling Surge Tank B (A001B)

The inspectors reviewed the component's design and associated testing to ensure it would be capable of meetings its required function under design basis events. Inspectors verified the adequacy of the tank's capacity, assumed initial volume, expected leakage during a design basis event

, and associated system leakage testing. The component's available instrumentation, available operational guidance (under normal and accident conditions)

, and recent level setpoints modifications were also reviewed to ensure sufficient NPSH was maintained for the ECC pump.

The inspectors discussed with licensee staff, and reviewed calculations, to determine if the seismic qualification would be impacted by the level setpoint modifications.

125Vdc Distribution Panel (ED1B08): The inspectors reviewed the one

-line diagram, the short circuit current calculation, and the coordination calculation to confirm the short circuit duty and the proper coordination between the panel fuses and branch circuit cabling with the upstream protective device. The inspectors also reviewed the panel electrical loading and voltage drop calculations, and the branch circuit cabling, to confirm bus and circuit cable ampacity was adequate and branch circuits had adequate voltage.

4160Vac Bus (EH

-12): The inspectors reviewed bus loading calculations to verify the 4160Vac system had sufficient capacity to support its required loads under worst case accident loading and grid voltage conditions. The inspectors reviewed the degraded voltage protection design scheme to determine whether it afforded adequate voltage to safety

-related devices at all voltage distribution levels. This included review of degraded voltage relay setpoint calculations and voltage calculations for downstream equipment such as MOVs. The inspectors reviewed the overcurrent protection scheme for the 4160Vac buses including drawings and calculations to determine whether loads were adequately protected and immune from spurious tripping. The inspectors also reviewed maintenance frequencies and procedures for the 4160Vac bus, its associated circuit breakers, and the system transformer to determine whether the equipment was being properly maintained. This included reviewing acceptance criteria in procedures for consistency with vendor recommendations and design calculations.

480Vac Motor Control Center (MCC) (EF-1-D): The inspectors reviewed bus and control circuit loading calculations to verify MCC 1D had sufficient capacity to support its required loads under worst case accident loading and grid voltage conditions. The overcurrent protection scheme for the MCC

, including drawings and calculations, were reviewed to determine whether loads were adequately protected and immune from spurious tripping. The inspectors reviewed maintenance schedules and procedures for the 480Vac bus and its associated circuit breakers to determine whether the equipment was being properly maintained. This included reviewing acceptance criteria in procedures for consistency with vendor recommendations and design calculations.

480Vac Motor Control Center (EF

-1D07): The inspectors reviewed bus and control circuit loading calculations to verify MCC 1D had sufficient capacity to support its required loads under worst case accident loading and grid voltage conditions. The overcurrent protection scheme for the MCC

, including drawings and calculations, were reviewed to determine whether loads were adequately protected and immune from spurious tripping. The inspectors reviewed maintenance schedules and procedures for the 480Vac bus and its associated circuit breakers to determine whether the equipment was being properly maintained. This included reviewing acceptance criteria in procedures for consistency with vendor recommendations and design calculations.

b. Findings

No findings of significance were identified.

.2 Operating Experience

a. Inspection Scope

The inspectors reviewe d four operating experience issues to ensure that NRC generic concerns had been adequately evaluated and addressed by the licensee. The operating experience issues listed below were reviewed as part of this inspection:

GL 96-01, "Testing of Safety Related Circuits"; IN 2010-23, "Malfunctions of Emergency Diesel Generator Speed Switch Contacts"; Industry Operating Experience, "Molded Case Circuit Breaker Handle Degraded due to High Temperature Areas

"; and Industry Operating Experience, "Manual Reactor Scram Following Loss of Division 1, 480Vac Safety

-Related Busses

."

b. Findings

No findings of significance were identified.

.3 Modifications

a. Inspection Scope

The inspectors reviewed two permanent plant modifications related to selected risk significant components to verify that the design bases, licensing bases, and performance capability of the components had not been degraded through modifications. The modifications listed below were reviewed as part of this inspection effort:

PERP 000805

"Equivalent Replacement of Limitorque S/N 1YFB01142A4 Motor to Limitorque Model R E04-082100A20 Motor

"; and ECP 02-0045 , "EQ Zone Temperature Changes as a Result of ESW Piping Temperature Changes.

"

b. Findings

No findings of significance were identified.

.4 Operating Procedure Accident Scenario

s

a. Inspection Scope

The inspectors performed a margin assessment and detailed review of three risk significant, time critical operator actions. These actions were selected from the licensee's PRA rankings of human action importance based on risk

-achievement worth values. Where possible, margins were determined by the review of the assumed design basis and USAR response times and performance times documented by job performance measures results. For the selected operator actions, the inspectors performed a detailed review and walk through of associated procedures, including observing the performance of the selected actions in the station's simulator and in the plant, with an appropriate plant operator to assess operator knowledge level, adequacy of procedures, and availability of special equipment where required.

The following operator actions were reviewed:

Loss of Condenser Heat Sink

Alignment of Condensate Transfer Alternate Injection; and Operators Restore Instrument Air to SRVs following an Isolation

.

b. Findings

No findings of significance were identified.

4OA2 Identification and Resolution of Problems

.1 Review of

Items Entered Into the Corrective Action Program

a. Inspection Scope

The inspectors reviewed a sample of the selected component problems identified by the licensee and entered into the corrective action program. The inspectors reviewed these issues to verify an appropriate threshold for identifying issues and to evaluate t he effectiveness of corrective actions related to design issues. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem into the Corrective Action Program. The specific corrective action documents sampled and reviewed by the inspectors are listed in the to this report.

The inspectors also selected five issues identified during previous CDBIs to verify the concern was adequately evaluated and corrective actions were identified and implemented to resolve the concern, as necessary. The following issues were reviewed:

CR-2011-05510; "NRC CDBI SOI

-P45/49 Incorrectly States ESW Strainer Backwash Starts at 2.75 psid"; NCV 05000440/2006009

-01, "ADS and Main Steam Isolation Valve Air Accumulators Stress Analysis Deficiencies

"; NCV 05000440/2006009

-02; "Non-conservative Safety

-Related Air Storage Tank Sizing Calculation

"; NCV 05000440/2008006

-01; "Switchyard Voltage Found Outside Analyzed Maximum Limit

"; and NCV 05000440/2011008

-03; "Failure to Test Safety

-Related Contactors at Degraded Voltage Conditions.

"

b. Findings

No findings of significance were identified.

4OA6 Meeting (s)

.1 Exit Meeting Summary

On April 4, 2014, the inspector s presented the inspection results to Mr. D. Reeves, and other members of the licensee staff. The licensee acknowledged the issues presented. Several documents reviewed by the inspectors were considered proprietary information and were either returned to the licensee or handled in accordance with NRC policy on proprietary information

. ATTACHMENT:

SUPPLEMENTAL INFORMATION

Attachment

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC

T Licensee

E. Harkness, Site Vice

-President

T. Brown, Performance Improvement Director

J. Ellis, Recovery Director

D. Reeves, Site Engineering Director

J. Veglia, Maintenance Director

R. Briggs, Design Engineering

Supervisor

B. Coad, Design Engineering

Supervisor

A. Frey, Mechanical/Structural Engineering

D. Lieb, Nuclear Engineering

Analysis

D. Lockwood, Regulatory Compliance Engineer

C. Olivier, Operations Manager

D. Stoltz, Electrical/I&C Engineering

T. Watterson, Design Engineering

L. Zerr, Regulatory Compliance Supervisor

E. Zidow, BOP Systems Engineering

Nuclear Regulatory Commission

M. Marshfield, Senior Resident Inspector

J. Nance, Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUS

SED Opened, Closed and Discussed

None

LIST OF DOCUMENTS REVIEWED The following is a list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part

of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or

any part of it, unless this is stated in the body of the inspection report.

CALCULATIONS

Number Description or Title

Revision CL-MOV-1E12-16 MOV 12F0024A/B Max Design Basis Differential Pressure

CL-MOV-1E12-3 MOV 12F0042A/B/C Max Design Basis Differential Pressure

CL-MOV-3 Generic Letter 89-10 Program

DI-155 ECC Water (P42) System Heat Exchanger Size, Operating Temperature and Outlet Temperature and P42 System Operating Temperatures

DI-166 P57 - Accumulator Volume Sizing Low

-Low Valve Sizing Set Relief

E12-048 E12/LPCI System Adequacy in Accident Injection Mode

ECA-067 Estimation of EQ Zone Temperature Increases as a Result of Temperature Changes in ESW and ECCW System Piping

EQ-012 Qualified Life of Limitorque Valve Operators

EQ-202 Qualified Life of Valve Operators in Zone AB

-4 With Removed Margin 0 FSPC-0030 Fuse Sizing and Overload Relay Selection for Class 1E 460V Motors (excluding MOVs)

M39-014 HPCS Pump Room Cooler Air Flow Rate and Performance Evaluations at Design Basis Conditions

M39-015 High Pressure Core Spray Pump Room Cooler Performance Test Results 2 M39-016 ECCS Pump Room Coolers Design Flows

MOVC-0073 AC MOV Actuator Degraded Voltage Torque/Thrust Capability using Commonwealth Edison (Com Ed) Method

P42-005, DCC 3

ECC Water System Surge Tank Sizing

P42-005, PIN 1

Expected Expansion Volume of ECC Surge Tank

P42-7 Atmospheric Surge Tank Vent (P

-42) 0 P42-024 Maximum Allowable Leakage From P42 System

P42-030 Evaluation of the ECC Water Temperature Control Valve 1P42F0665A/B

P42-039 Design Basis Heat Load & Required ESW Flow for the ECC HXs

P42-039, PIN 1

Determination of Design Basis Fouling on ECC Heat Exchangers.

P42-039, PIN 10

Vendor Study Results for ESW Water Temperature Above 85°F

P42-047 Required Flowrate

to the HXs Cooled by the ECCW System

P42-049 ECCS Pump Room Coolers Cooled by Emergency Closed Cooling Water Performance

P42-051 ECC Heat Exchanger "B" Loop Performance Test Evaluation

P42-T02 ECC Heat Exchanger Outlet Temperature Bistables

1P42N051A/B

P42-T04 ECC Surge Tank Level Hi/Lo Alarm

CALCULATIONS

Number Description or Title

Revision P42-T05 ECC Surge Tank Hi/Lo Make

-Up Valve Interlock 1P42N0130A,B

P42-T05, PIN 1

Calculation P42

-TO5, Rev. 2, "Emergency Closed Cooling Surge Tank Hi/Lo Make

-up Valve Interlock 1 P42N0130A,B", Contains Misleading Information

P45-54, DCC 1 ESW Makeup To ECC Surge Tank

P45-081 Evaluation of Net Positive Suction Head (NPSH) and Submergence Requirements for the Emergency Service Water System Pumps

P45-081, P-01 This PIN Identifies Altered Design Inputs and Clarifies the Precise Location of the 1

st Stage Impeller

P45-081, P-02 Administrative Changes and Does Not Contain Any Technical Content 0 P45-081, P-03 2% Over-Frequency Condition

P57-013 Required Air Volume and Leakage Acceptance

Criteria for the Division 1 and 2 Safety Related Instrument Air (P57) System

PMRV-0005 Residual Heat Removal Pump Motor Protection 1E12C002A, 1E12C000B, and 1E12C000C

PRDC-0002 Unit 1 Div 1, 2, 3 125VDC System Coordination

PRDC-0004 Class 1E DC Control Circuit Coordination

PRDC-0015 Division 2, 125 VDC System Load Evaluation, Voltage Drop, Battery/Battery Charger Sizing Calculation

PRLV-0002 480 Volt Safety Related Motor Relay Calculation for Motors Connected to Switchgear Breakers

PRMV-0003 Emergency Service Water (1P45)

PSTG-0001 PNPP Class 1E Power Distribution System Voltage Study

SQ-0017 Qualification of 1E12F024B

SQ-0018 Qualification of 1E12F024A

SQ-0027 MOV Mod 1E12F005, 1E12F042A/B/C

SQ-0082 Seismic Qualification for Valves 1P42F665A/B

CORRECTIVE ACTION DOCUMENTS GENERATED DUE TO THE INSPECTION

Number Description or Title

Date CR-2014-01657 Error in PRA Documentation/Model

01/31/14 CR-2014-04352 Breaker F1D12 Panel Door Condition

03/05/14 CR-2014-04357 Verify Material in 1P42C0001B Motor is Grease

03/05/14 CR-2014-04375 Housekeeping Issue With Storage of 50 Gallon Drums In ESW Pumphouse 03/05/14 CR-2014-04512 Calculation

M39-000 Incorrectly Classified as Active

03/07/14 CR-2014-04527 Breaker Nameplate Rating Information Not Clear

03/07/14 CR-2014-04530 Procedure Improvement for ESW Pump B Discharge Check Valve Exercised Closed Test in SVI

-P45-T2002. 03/07/14 CR-2014-04650 Climbing Harnesses Left in Unapproved Storage Location

03/10/14 CR-2014-04772 Procedure Improvements Identified during 2011 CDBI Have Not Been Completely Resolved

03/12/14 CR-2014-04786 Permitted use of Valve Persuaders as listed in the ISTP

03/12/14

CORRECTIVE ACTION DOCUMENTS GENERATED DUE TO THE INSPECTION

Number Description or Title

Date CR-2014-04834 Design Interlock for ESW Pump B Not Tested

03/12/14 CR-2014-04837 Design Interlock for RHR 1E12F027B Manual Operation Not Tested

03/12/14 CR-2014-04862 Drawing 302

-0621-00000 Discrepancy

03/13/14 CR-2014-04868 Potential Non

-Conformance With IEEE Standard 450 Requirements

03/13/14 CR-2014-05166 Minor Drawing Error in ADS Valve 1B21F005G, B Channel Logic Circuit 03/18/14 CR-2014-05204 Inadequate Response to Fire Trouble Indications

03/19/14 CR-2014-05220 Calculation P42

-007 References Historical Setpoints

03/19/14 CR-2014-05226 SOI-P45/49 Revision 20 Was Not Updated to Incorporate Entire Scope of DCR 600720456

03/19/14 CR-2014-05229 Inconsistencies Noted in Calculation E12

-T01, R4 03/19/14 CR-2014-05292 Evaluate Need to Protect DC Buses During System Outages

03/20/14 CR-2014-05336 Extension of "ComEd" Methodology for AC MOV Motors

03/20/14 CR-2014-05370 Overload for RHR B Room Cooler 1M39B0001B Set Higher than NEC Guidance

03/21/14 CR-2014-05543 Vendor Drawing for SRV Solenoids not in Vendor Manual G30

03/24/14 CR-2014-05838 Lack of Procedure Guidance for Monitoring ECC Surge Tank Post Accident 03/28/14 CR-2014-05964 Misleading Statement in the USAR Regarding Closed Cooling Pumps 03/31/14 CR-2014-05972 Evaluation on the Acceptability of Spring

-Charging Motor Control Switch Protection Not Found

03/31/14 CR-2014-05977 Calculation M39

-016 Did Not Consider Worst Case Condition for Brake Horsepower and Used Incorrect Voltage to Calculate Brake Horsepower

03/31/14 CR-2014-060 48 Historical Airflows Measured for RHR B Room Cooler Appear Excessive 04/01/14 CR-2014-06051 Inconsistencies Within Design Input DI

-224 for the High Pressure Core Spray Pump Room Cooler

04/01/14 CR-2014-06054 Misleading Use of Fouling Factors Calculated

for the High Pressure Core Spray Pump Room Cooler

04/01/14 CR-2014-06058 Minor Documentation Error in Tech Specs Bases SR 3.5.1.7

04/01/14 CR-2014-06114 Incorrect Brake Horsepower used in ETAP Calculation PSTG

-0001 04/02/14 CR-2014-06211 Incorrect CA Purpose Provided in CR 2013

-17081 ODMI

04/03/14 CR-2014-06273 Observation Regarding use of NUREG

-1482 in IST Program

04/04/14 CR-2014-06432 Observation Related to Gaps in Knowledge Transfer

04/07/14 CR-2014-06473 Freedom Series MCC Contactor Voltage Concern 04/08/14 CORRECTIVE ACTION DOCUMENTS REVIEWED DURING THE INSPECTION

Number Description or Title

Date CR-2004-02598 ESW Pump A Failure

05/01/04 CR-2006-00815 NRC ID, Maximum Drywell Temperature Affects ADS Accumulator Pressure 02/17/06 CR-2006-00817 NRC ID, Affects Drywell Backpressure Not Addressed in Calculation P57-13 01/17/06

CORRECTIVE ACTION DOCUMENTS REVIEWED DURING THE INSPECTION

Number Description or Title

Date CR-2006-00866 Error Found In Calculation p52

-003 Revision 1

2/22/06 CR -2008-38977 CALC PSTG-0030 Adequacy for Min Pickup Voltages for Motor Starters 04/23/08 CR-2008-40964 CDBI Concern Grid Voltage Above Maximum Limit

05/28/08 CR-2008-40969 High Pressure Core Spray Inoperable

05/28/08 CR-2008-44840 NRC NCV, Switchyard Voltage Outside Analyzed Max Limit 08/15/08 CR-2009-53436 Condensation on ESW Pump B Motor Cooling Pipe with the Pump Shutdown 02/12/09 CR-2009-54497 Emergency Service Water

03/02/09 CR-2009-56880 SRV F0051G Solenoid Coil B Doesn't Fit Well

04/07/09 CR-2009-65802 Motor Fire Pump Discharge Piping Leakage in ESW Pump House

CR-2009-65957 ESW "B" Motor Rigid Conduit is Noted to be Full of Water

10/15/09 CR-2009-65972 ESW Pump B Tripped

10/15/09 CR-2009-65981 ESW Insulation Resistance Anomaly

10/15/09 CR-2010-69818 Chirping Noise Coming From EEC "B" Motor

01/11/10 CR-2010-72234 Elevated Bus and Equipment Voltages

03/01/10 CR-2010-86672 Slight CO2 Leak Noted During ISLT

CR-2011-05484 NRC CDBI Identified Procedure Enhancements May Be Needed

11/16/11 CR-2011-05505 Test/Analysis Report 95

-089 Appears to Provide Inconsistent Data

11/16/11 CR-2011-05507 NRC Identified

- Repetitive Maintenance Plan Not Revised as Required 11/16/11 CR-2011-05510 SOI-P45/49 Incorrectly States ESW Strainer Backwash Starts at 2.75 psid 11/16/11 CR-2011-06244 NRC CDBI 2011

- Potential Green Non

-Cited Violation (NCV)

2/02/11 CR-2011-91479 Vendor Not Approved on Suppliers List

03/22/11 CR-2011-93769 Motor Operated Valve Stem Nut Found to be Worn

04/27/11 CR-2011-94294 ECC "B" - Pump Seals 05/07/11 CR-2012-08324 Emergency Closed Cooling Pump

-B Motor Making Noise

05/20/12 CR-2012-01197 Failure to Test Safety

-Related Contactors at Degraded Voltage Conditions

01/24/12 CR-2012-13700 PTI-P42-P0002, ECC B Heat Exchanger Performance Test

09/06/12 CR-2012-16824 PA-PY-2012; Closure of Corrective Action CR 2012

-05154-3 did not Meet the Intent of the Corrective Action

10/24/12 CR-2012-17544 Cooling Lines Need Recoated

11/05/12 CR-2012-17545 RHR "B" Pump Motor has an Unused Conduit Fitting with a Cutoff Cable Hanging Out

11/05/12 CR-2013-04908 ECC Heat Exchanger "B" Divider Plate Thickness

04/01/13 CR-2013-12036 Molded Case Circuit Breaker Handle Degradation Due to High Temperature Areas

09/23/13 CR-2013-17081 ODMI: Options to Lower Voltage on Safety Related Plant Buses to Allow Exit of Off Normal Instruction, ONI

-S11, Hi/Low Voltage

10/24/13 CR-2014-04402 EQ Life on Several Exceeded for Several MOVs

03/06/14 CR-2014-00426 125VDC Bus D

-1-B Maintenance Requirements

01/10/14

DRAWINGS Number Description or Title

Revision 022-0010-00000 Environmental Conditions for Control Building

03/11/13 22-0140-00002 Emergency Closed Cooling Heat Exchanger Loop "B" Tube Sheet Drawing A 39EA35-C893-7 HPCS Pump Room Cooling Air Handling Unit

F 39EA35-C893-3 RHR A Cooling Air Handling Unit

F 206-0010-00000 Main One-Line Diagram 13.8kV & 4.16kV

BB 206-0017-00000 Electrical One Line Diagram Class 1E 4.16KV Bus EH11 & EH12

EE 206-0027-00000 Electrical One Line Diagram Class 1E 480V Bus EF1D

BBBB 206-0051-00000 Electrical One Line Diagram Class 1E DC System

AAA 208-011 Electrical Elementary Diagram Automatic Depressurization System ADS Valves, Sh. C11

K 208-0011-00004 Electrical Elementary Diagram Automatic Depressurization System Power Distribution Thermocouple Identification

M 208-0011-00012 Electrical Elementary Diagram Automatic Depressurization System ADS Valves

R 208-0039-00004 Electrical Elementary Diagram Remote Shutdown System Division 2 Switch Development and Locations

L 208-0055-00018 Electrical Elementary Diagram Residual Heat Removal System RHR Pump C002B

CC 208-0131-00005 Electrical Elementary Diagram Pump Room Cooling

System RHR Pump 'B' Heat Exchanger Cooler 1M39

-B001B R 208-0173-00002 Electrical Elementary Diagram Emergency Closed Cooling System Pump B C0001B

P 208-0176-00002 Electrical Elementary Diagram Emergency Service Water System "B" Emergency Service Water Pump C001B

FF 208-0176-00005 Electrical Elementary Diagram Emergency Service Water "B" Emergency Service Water Pump Discharge Valve F130B

Y 302-00004 Nuclear Boiler System

M 302-0215-00000 Service water and Emergency Service Water Chlorination System

T 302-0271-00000 Safety Related Instrument Air System

R 302-0605-00000 Nuclear Boiler System

X 302-0621-00000 Emergency Closed Cooling System

SS 302-0719-00000 Emergency Service Water System

VV 302-0792-00000 Emergency Service Water System

NN 304-0649-00101 Residual Heat Removal System Reactor Building

F 304-0644-00105 Residual Heat Removal System Auxiliary Building and Reactor Building D 304-0808-00103 Emergency Service water System Pump House Sheet 1

F 304-0808-00103 Emergency Service water System Pump House Sheet 2

F 304-0808-00103 Emergency Service water System Pump House Sheet 3

F 304-0808-00103 Emergency Service water System Pump House Sheet 4

F 304-0808-00103 Emergency Service water System Pump House Sheet 5

F 304-0808-00103 Emergency Service water System Pump House Sheet 6

F 304-0808-00103 Emergency Service water System Pump House Sheet 7

F 912-0616-00000 ECCS Pump Rooms Cooling Systems

K 912-0630-00000 Emergency Service Water Pump House Ventilation System

L

DRAWINGS Number Description or Title

Revision 912-0648-00000 Misc. HVAC Design Data

G IC-3386 Seal Piping Diagram (RHR Pump)

E IC-3640 Dual Coil Heat Exchanger Flow Path Diagram (RHR Pump)

A MISCELLANEOUS

Number Description or Title Date or Revision 1E12F0024B

-005 MOV Test Report

- 1E12F0024B

0, 1 1E12F0042C

-004 MOV Test Report

- 1E12F0042C

0, 1 1P42B0001B

-0360-002A Vendor Manual for ECC Hear Exchanger (P42

-B0001B) 03/31/77 1P42C0001B

-0504-004A Vendor Manual for ECC Pump (1P42

-C0001B) 10/02/79 1P42F0665B

-1268-001 Vendor Manual for 3

-Way Diverting Valve With ITT Barton Model NH93 Actuator.

04/19/95 1P42N0051B

Alarm Card

- ECC HT Exch 1P42B001B Outlet Temp Hi/Lo

n/a 1P42N0130B

Switch Level Setpoint (1P42N0130B)

n/a 1P42N0131B

Switch Level Setpoint (1P42N0131B)

n/a 1P42N130A & 1P4N130B

Vendor Manual for Magnetrol Level Switches on ECC Surge Tank

01/17/01 22A4622AR Design Spec Data Sheet: Nuclear Boiler System

22A6490 Specification: Plant Air

30DX20CKXH2

- 3STG VMT Byron Jackson Pump Curve

07/21/77 4408081750

Strainer Backwash Required Torque

06/18/02 6400-D2008 Carrier Corporation Fan Performance Curve for item SM

-10 04/30/78 DI-224 HPCS Pump Room Cooler Design Input

07/26/12 G471-6/125.04:10

DIKKERS Nuclear Safety/Relief Valve Instruction Manual Part A Sec. 4

09/17/79 GAI 4549-60A-104-1-0 Motor Data Form Reliance Electric Company

07/28/77 GAI 4549-69-270-0 Carrier Fan Performance Curve 6400D2008

2/07/78 N-1148 Ingersoll-Rand Pump Curve

05/31/79 OE 2014-0303 Industry Operating Experience Report

- Clinton 03/13/14 P-1360-K Installation and Maintenance Instructions Manual Duo

-Check Valves

11/06/80 PY-CEI/NRR-2041L Testing of Safety Related Logic Circuits, Generic Letter 96

-01 04/17/96 SMRF 00-5018 ECCW System Surge Tank Magnetrol Level Switches Replacement with Similar Level Switches With Narrower Ranges 11/02/00 SMRF 05-02122 EQ Zone Temperature Changes as a Result of ESW Piping Temperature Changes

SP-501-4549-00 Large Emergency Service Water Pumps

TAF 81834 Pump Curve 26: Emergency Closed Cooling Pump

TC-10108 Johnston Pump Company Curve and Test Data Sheet

11/06/01 VR-2 10 CFR 50.55a Request

MISCELLANEOUS

Number Description or Title Date or Revision VR-6 10 CFR 50.55a Request

MODIFICATIONS

Number Description or Title

Revision PERP 000805

Equivalent Replacement of Limitorque S/N 1YFB0U42A4 Motor to Limitorque Model R

-302-E04-082100A20 Motor

0, 1 ECP 02-0045 EQ Zone Temperature Changes as a Result of ESW Piping Temperature Changes

ECP 02-0213 Separation

o f the ECCW "B" Loop

from the NCCW System

PROCEDURES

Number Description or Title Revision ARI-H13-P601-0016-D1 ESW to Diesel Heat Exchanger Flow Low

ARI-H13-P601-0017 RHR B & C 13 ARI-H13-P601-0020-G1 ESW Pump A Discharge Pressure Low

EOP-04-2 Emergency Depressurization

B EOP-SPI 2.3 Bypass MSIVs and ECCS Interlocks

EOP-SPI 4.4 Condensate Transfer Alternate Injection

IOI-6 Cooldown - Main Condenser Not Available

ISI-P45-T1103-3 ESW To RHR Emergency Cross

-Tie System Functional Pressure Test 3 NOBP-ER-3603A Check Valve Condition Monitoring Program

NOP-ER-2006 Service Water Reliability Management Program

NOP-ER-3603 Check Valve Program

NOP-OP-1014 Plant Status Control

ONI-B21 Nuclear Steam Supply Shutoff, Automatic

Depressurization and Nuclear Steam Supply

Systems 17 ONI-B21-1 SRV Inadvertent Opening/Stuck Open

PAP-0205 Operability Of Plant Systems

PAP-1910 Fire Protection Program

PMI-0030 Maintenance of Limitorque Valve Operators

PTI-E12-P0012B RHR Loop B Shutdown Cooling Interlock Testing

PTI-P42-P0011 ECC B Loop Total Leakage Verification

PTI-P45-P0002 ESW System Loop B Flow and Differential Pressure Test

PYBP-POS-2-2 Protected Equipment Posting

REC-0104 Chemistry Specifications

SOI-P42 Emergency Closed Cooling System

SOI-P45/P49 Emergency Service Water and Screen Wash Systems

SOI-P45/P49 Emergency Service Water and Screen Wash Systems

PROCEDURES

Number Description or Title Revision SOI-P54/56 (FPM) Fire Protection System

- Fire Protection Monitoring

SOI-P57 Safety Related Instrument Air System

SVI-B21-T2012 SRV Uncoupled Stroke Testing with GMI

-0017A 4 SVI-E12-T1196-B LPCI Pump B Discharge Flow

-Low (BYPASS) Channel Functional for 1E12-N652B 12 SVI-E12-T1406-B ECCS/LPCI B RPV Low Pressure Channel Functional for 1E12

-N658B 6 SVI-E12-T2002 RHR B Pump and Valve Operability Test

SVI-E12-T9407 Type C Local Leak Rate Test of 1E12 Penetration P407

SVI-GEN-T2000 ASME Code Check Valve Disassembly Testing

SVI-P45-T2002 ESW Pump B and Valve Operability Test

SVI-P57-T2200 Safety Related Test 1P57-F555A And 1P57

-F556A Leak Rate Test

SVI-R43-T7000-B Division 2 ECCS Integrated Test

VLI-P57 Safety Related Instrument Air System

TRAINING DOCUMENTS

Number Description or Title Revision OT-3701-P11-001NLO Condensate Transfer Alternate Injection

OTLC-3058201407

-PY-SGF CDBI NRC Inspection Support Scenario F

WORK DOCUMENTS

Number Description or Title

Date 200040464 PY-1P42 ECC Loop Calibration

- Temperature

06/23/05 200097274 The P42 B Inboard Motor Bearing is Making a Light Squealing Noise

11/16/04 200146569 ESW to RHR Emergency Cross Tie System Functional Pressure Test 03/11/09 200160761 Replace The Circuit Boards for HX 'B' Temperature Transmitter 1P42N0052B, and Perform a Loop Calibration Check

2/01/07 200167933 Buss EF-1-D Clean and Service

05/23/11 200169608 Replace Solenoid Assemblies SRV S/N 160863 (EQ)

03/30/07 200169609 Replace All Non

-Metallic Materials SRV S/N 160863 (EQ)

03/30/07 200218408 Replace Tech Pacs and Power Supplies

2/03/10 200238394 RHR B Rm Cooler has Damaged Conduit Covering by Grating on Floor 12/04/06 200260150 Type C Local Leak Rate Test of 1E12 Penetration P407

04/30/11 200274377 At 2315, RHR B Pump Tripped for no Reason

07/12/07 200318399 Replace CUB EH1202/XH1201 PT PRI Fuses

05/15/11 200327573 Performance Monitor Flow Test

11/04/08 200341892 Replace Motor on RHR B Test Valve to Suppression Pool

05/01/11 200342060 Inspect and Clean P42B ECC Heat Exchanger

05/05/11 200342620 LPCI C Injection Valve

04/30/13 200347947 Emergency Service water Pump Discharge

2/02/08

TRAINING DOCUMENTS

Number Description or Title Revision 200358911 ESW to RHR Emergency Cross-Tie System Functional Pressure Test 04/22/13 200360842 Replace Worn ESW Screen Wash Strainer Drive Shaft

03/04/14 200365830 SRV Uncoupled Stroke Testing with GMI

-0017 (SVI-B21T2012) 05/25/11 200366346 SRV Accumulators Air Supply Check Valve Exercise Close

05/23/11 200380798 ECC B Loop Total Leakage Verification

08/14/11 200391129 Engineering Change 09

-726-001 Shall Provide for Drainage Weep Holes to be Installed in Safety Related Conduit 1P45H3B

10/28/09 200410738 Cal 50/51A Relay ESW Pump "B" Bkr EH1205

08/12/12 200410739 Cal 50/51B Relay ESW Pump "B" Bkr EH1205

08/12/12 200410780 Cal 50/51C Relay ESW Pump "B" Bkr EH1205

08/12/12 200410781 Cal 50A-C Device ESW Pump "B" Bkr EH1205 (EQ)

08/12/12 200414069 RHR B Test Valve to Suppression Pool

04/29/11 200415910 Emergency Closed Cooling B Heat Exchanger Performance Testing

03/15/13 200436628 Evaluation of IN 2010

-23, Malfunctions of EDG Speed Switch Circuits 02/02/11 200438857 Exercise and Service Breaker EF1D04

to (1P42C0001B) (EQ)

11/06/12 200456908 RHR B Cold Shutdown Valve Operability Test

04/20/13 200458668 LPCI C Containment Injection Valve Leak Rate Test

04/28/13 200461423 SRV Accumulators Air Supply Check Valve Exercise Close

04/21/13 200461492 SRV Uncoupled Stroke Testing with GMI

-0017 (SVI-B21T2012) 04/19/13 200471779 Relay 1FC66K 50/51A RHR Pump B 1E12C00

08/07/13 200471780 Relay 1FC66K 50/51B RHR Pump B 1E12C00

08/07/13 200471835 Relay 1FC66K 50/51C RHR Pump B 1E12C00

08/09/13 200472712 ECC B Loop Total Leakage Verification

08/10/13 200457499 Support Trouble Shooting Identified During 1R22S0006 Maintenance

05/01/11 200477114 Replace All Elastomers S/N 160899 (EQ)

03/05/13 200487564 Loop Check, EDG1 Digital Tach 'A'

11/23/13 200548443 ESW System Loop B Flow and Differential Pressure Test

09/10/13 200548472 ESW System Loop B Flow and Differential Pressure Test

2/07/13 200548812 ECCS/LPCI A RPV Low Pressure Channel Functional for 1E12

-N658A 01/03/14 200549756 ESW Pump B and Valve Operability Test

08/10/13 200549758 ESW Pump B and Valve Operability Test

2/06/14 200549844 LPCI Pump B Discharge Flow

-Low (BYPASS) Ch. Functional 1E12

-N652B 08/07/13 200549859 ECCS/LPCI B RPV Low Pressure Channel Functional for 1E12

-N658B 08/07/13 200549861 ECCS/LPCI B RPV LOW Pressure Channel Functional for 1E12

-N658B 02/05/14 200549896 ECC System B Pump and Valve Operability

2/09/14 200552130 RHR LOOP B Shutdown Cooling Interlock Testing

03/09/13 200561466 RHR B Cold Shutdown Valve Operability

Test 04/26/13 200591397 ECC Flow Balance

01/25/14

LIST OF ACRONYMS USE

D ADAMS Agencywide Document Access Management System

ADS Automatic Depressurization System

ASME American Society of Mechanical Engineers

CDBI Component Design Bases Inspection

CFR Code of Federal Regulations

CR Condition Report

d/p Differential Pressure

EC Engineering Change

ECC Emergency Closed Cooling

ECCS Emergency Core Cooling System

ECP Engineering Change Package

EOP Emergency Operating Procedure

EQ Equipment Qualifications

ESW Emergency Service Water

FENOC FirstEnergy Nuclear Operating Company

GL Generic Letter

HX Heat Exchanger

IEEE Institute of Electrical & Electronic Engineers

IMC Inspection Manual Chapter

IN Information Notice

IP Inspection Procedure

IR Inspection Report

IST Inservice Testing

LERF Large Early Release Frequency

LOOP Loss of Off

-site Power

LPCI Low Pressure Coolant Injection

MCC Motor Control Center

MOV Motor-Operated Valve

NCV Non-Cited Violation

NPSH Net Positive Suction Head

NRC U.S. Nuclear Regulatory Commission

OE Operating Experience

PARS Publicly Available Records System

PRA Probabilistic Risk Assessment

psid Pounds Per Square Inch Differential

RHR Residual Heat Removal

RIS Regulatory Issue Summary

SDP Significance Determination Process

SPAR Standardized Plant Analysis Risk

SRV Safety Relief Valve

TS Technical Specification

USAR Updated Safety Analysis Report

Vac Volts Alternating Current

Vdc Volts Direct Current

WO Work Order

Mr. Ernest Harkness

Site Vice President

FirstEnergy Nuclear Operating Company

Perry Nuclear Power Plant

P. O. Box 97, 10 Center Road, A

-PY-A290 Perry, OH 44081

-0097 SUBJECT: PERRY NUCLEAR POWER PLANT COMPONENT DESIGN BASES INSPECTION 05000440/2014007

Dear Mr. Harkness:

On April 4, 2014, the

U.S. Nuclear Regulatory Commission (NRC) completed a Component Design Bases Inspection (CDBI) inspection at your Perry Nuclear Power Plant. The enclosed report documents the results of this inspection, which were discussed on April 4, 2014, with Mr.

D. Reeves, and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

No findings were identified during this inspection.

In accordance with Title 10, Code of Federal Regulations

(CFR), Section 2.390 of the NRC's "Rules of

Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html

(the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50

-440 License No. NPF

-58 Enclosure:

Inspection Report 05000440/2014007

w/Attachment: Supplemental Information

cc w/encl: Distribution via LISTSERV

DISTRIBUTION

See next page

DOCUMENT NAME:

G:\DRSIII\DRS\Work in Progress

\PER 2014 007 CDBI AXD.docx

Publicly Available

Non-Publicly Available

Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy

OFFICE RIII RIII RIII RIII NAME ADunlop:ls AMStone DATE 05/0 6/14 05/07/14 OFFICIAL RECORD COPY

Letter to Ernest Harkness

from Ann Marie Stone dated May

7, 2014. SUBJECT: PERRY NUCLEAR POWER PLANT COMPONENT DESIGN BASES INSPECTION

05000 440/2014007 DISTRIBUTION

Joseph Nick

RidsNrrPMPerry Resource

RidsNrrDorlLpl3

-2 Resource

RidsNrrDirsIrib Resource

Cynthia Pederson

Darrell Roberts

Steven Orth

Allan Barker

Carole Ariano

Linda Linn

DRPIII DRSIII Patricia Buckley

Carmen Olteanu

ROPreports.Resource@nrc.gov