IR 05000369/2015007

Ir 05000369/2015007, 05000370/2015007; on 4/27/2015 - 6/5/2015; McGuire Nuclear Station, Units 1, 2; Component Design Bases Inspection

ML15204A381
Person / Time
Site:	Mcguire, McGuire
Issue date:	07/23/2015
From:	Bartley J H NRC/RGN-II/DRS/EB1
To:	Capps S D Duke Energy Carolinas
References
IR 2015007
Download: ML15204A381 (26)

Text

July 23, 2015

Mr. Steven Site Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station MG01VP/12700 Hagers Ferry Rd Huntersville, NC 28078

SUBJECT: MCGUIRE NUCLEAR STATION - U. S. NUCLEAR REGULATORY COMMISSION COMPONENT DESIGN BASES INSPECTION REPORT 05000369/2015007 AND 05000370/2015007

Dear Mr. Capps:

On June 5, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station Units 1 and 2 and discussed the results of this inspection with yourself and members of your staff. In addition, on July 20, 2015, the inspectors conducted a final exit meeting via telephone with M and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.

NRC inspectors documented two findings of very low safety significance (Green) in this report. These findings involved violations of NRC requirements.

If you contest the violations or significance of these non-cited violations (NCVs), 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 II; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the McGuire Nuclear Station.

In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," 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's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17

Enclosure:

Inspection Report 05000369, 370/2015007

w/Attachment:

Supplementary Information cc: Distribution via Listserv

SUMMARY

IR 05000369/2015007, 05000370/2015007; 4/27/2015 - 6/5/2015; McGuire Nuclear Station, Units 1, 2; Component Design Bases Inspection.

A team of five Nuclear Regulatory Commission (NRC) inspectors from Region II, and one NRC contractor conducted this inspection. Two Green non-cited violations (NCVs) were identified.

The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red) using the NRC Inspection Manual Chapter (IMC) 0609, "Significance Determination Process," dated April 29, 2015. All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy, dated February 4, 2015. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014.

Cornerstone: Mitigating Systems

• Green: The team identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, "Design Control," consisting of two examples. In one example, the licensee failed to verify the adequacy of GE model TED molded case circuit breaker (MCCB) design. In the second example, the licensee failed to verify the adequacy of Eaton model HFB MCCB design. The licensee initiated Action Request (AR) 01929605 and AR 193674, which determined the systems were operable because upstream protective devices provided protection from a failed HFB and/or TED MCCBs, and that the HFB and TED MCCBs would be replaced with MCCBs that have adequate ratings. The licensee's failure to design the Class 1E electric system MCCBs in accordance with IEEE 308-1971 Sections 4.1 and 5.3.5 was a performance deficiency. The team determined that the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The finding was determined to be of very low safety significance (Green)because the deficiency affected the design or qualification of a mitigating structure, system, or component (SSC), but the SSC maintained its operability or functionality. No cross-cutting aspect was applicable because the finding was not indicative of current licensee performance. (Section 1R21.2.b.1)

• Green: The team identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion XI, "Test Control," consisting of two examples. In one example, the licensee failed to scope some Class 1E molded case circuit breakers (MCCBs) into the Class 1E MCCB testing program. In the second example, the licensee's test procedure pre-conditioned the Class 1E MCCBs before testing their safety function. The licensee initiated Action Request (AR) 1936760 and AR 01934403, which determined the systems were operable because an engineering review of previous TED breaker testing and PM's has not shown a trend of degradation of the breakers ability to perform its function. In addition, the licensee planned develop a more extensive and adequate testing program.

3 The licensee's failure to perform adequate MCCB testing in accordance with IEEE 308-1971, Section 6.3, "Periodic Equipment Tests," was a performance deficiency. The team determined that the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The finding was determined to be of very low safety significance (Green) because the deficiency affected the design or qualification of a mitigating structure, system, or component (SSC), but the SSC maintained its operability or functionality. No cross-cutting aspect was applicable because the finding was not indicative of current licensee performance. (Section 1R21.2.b.2)

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity

1R21 Component Design Bases Inspection

.1 Inspection Sample Selection Process

The team selected risk-significant components and related operator actions for review using information contained in the licensee's probabilistic risk assessment. In general, this included risk significant structures, systems, and components (SSCs) and operator actions that had a risk achievement worth factor greater than 1.3 or Birnbaum value greater than 1E-6. The sample included 16 SSCs, 2 of which were associated with containment large early release frequency (LERF), and 5 operating experience (OE)items.

The team performed a margin assessment and a detailed review of the selected risk-significant components and associated operator actions to verify that the design bases had been correctly implemented and maintained. Where possible, this margin was determined by the review of the design basis and Updated Final Safety Analysis Report (UFSAR). This margin assessment also considered original design issues, margin reductions due to modifications, or margin reductions identified as a result of material condition issues. Equipment reliability issues were also considered in the selection of components for a detailed review. These reliability issues included items related to failed performance test results, significant corrective action, repeated maintenance, maintenance rule status, Inspection Manual Chapter 0326 conditions, NRC resident inspector input regarding problem equipment, system health reports, industry OE, and licensee problem equipment lists. Consideration was also given to the uniqueness and complexity of the design, OE, and the available defense-in-depth margins. An overall summary of the reviews performed and the specific inspection findings identified is included in the following sections of the report.

.2 Component Reviews

a. Inspection Scope

SSCs

• Refueling Water System (FW)

• Diesel Generator Engine Fuel Oil System (FD) and Auxiliary Fuel Oil System (FS)

• SSCs preventing internal flooding and hazardous environmental conditions of these systems: 125VDC Vital I&C (EPL), 125VDC Aux Control Power (EPK), and 250VDC Aux Power (EPJ)

• Nuclear Service Water System (RN) Sources to the Auxiliary Feedwater System (CA)

• Diesel Generator Engine Cooling Water System (KD)

• Emergency Diesel Generator (EDG) Load Sequencer (EQB) and Safe Shutdown Facility (SSF) Diesel Load Sequencer

• RN System Motor Operated Valves (0RN283AC, 0RN284B, and 1RN297B)

• 4.16KVAC Essential (Blackout) Aux Power system (ETA)

• Transformer 4160V/600V 1ELXA

• Residual Heat Removal System (ND) motor-operated valve 1ND58A

• Seal Water Injection Filter 1A

• Safety Injection System (NI) motor operated valve1NI136B

• Component Cooling Water Heat Exchanger 1A (KC)

• Air Operated Valves1RN161B Components with LERF Implications

• Steam Generator Power-Operated Relief Valves (PORVs) - [SV-11,7, 13, 19]

• Auxiliary Feedwater (CA) to Turbine Driven Auxiliary Feedwater Pump Start Circuits For the 16 components listed above, the team reviewed the plant technical specifications (TS), UFSAR, design bases documents, and drawings to establish an overall understanding of the design bases of the components. Design calculations and procedures were reviewed to verify that the design and licensing bases had been appropriately translated into these documents. Test procedures and recent test results were reviewed against design bases documents to verify that acceptance criteria for tested parameters were supported by calculations or other engineering documents, and that individual tests and analyses served to validate component operation under accident conditions. Maintenance procedures were reviewed to ensure components were appropriately included in the licensee's preventive maintenance program. System modifications, vendor documentation, system health reports, preventive and corrective maintenance history, and corrective action program documents were reviewed (as applicable) in order to verify that the performance capability of the component was not negatively impacted, and that potential degradation was monitored or prevented.

Maintenance Rule information was reviewed to verify that the component was properly scoped, and that appropriate preventive maintenance was being performed to justify current Maintenance Rule status. Component walkdowns and interviews were conducted to verify that the installed configurations would support their design and licensing bases functions under accident conditions, and had been maintained to be consistent with design assumptions.

Additionally, the team performed the following specific reviews:

• The team reviewed operator actions associated with the transfer of the emergency core cooling systems to cold leg recirculation mode during a postulated design basis large break loss of coolant accident. This review included verification of operator actions required due to the effects of a safe shutdown earthquake, including a loss of instrument air supply to air powered equipment. The team performed interviews with engineering and operations staff to discuss operations staffing and response during the event as well as the effect of recent modifications to the initiation of containment spray cooling.

b. Findings

b.1 Failure to Verify Protection System DC Molded Case Circuit Breaker Ratings:

Introduction:

The team identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, "Design Control," consisting of two examples. In one example, the licensee failed to verify the adequacy of GE model TED molded case circuit breaker (MCCB) design. In the second example, the licensee failed to verify the adequacy of Eaton model HFB MCCB design.

Description:

The team identified two examples of a performance deficiency related to the licensee's design of Class 1E power circuits using molded case circuit breakers (MCCBs) since installation in approximately 1981. McGuire's UFSAR Section 8.1.4, "Design Criteria," for the Electric Power Systems, stated, in part, "In the design of all Essential Auxiliary Power Systems the criteria set forth in -, IEEE 308-1971-, have been followed. Standard IEEE 308-1971 Section 4.1 "General." stated, in part, "the Class IE electric systems shall be designed to assure that any design basis events [such as single equipment malfunctions, -, component failure, or circuit fault that can cause multiple equipment malfunctions] listed in Table 1 will not cause: (1) A loss of electric power to a number of engineered safety features (ESF), surveillance devices, or protection system devices-" In addition, Section 5.3.5 "Protective Devices." stated, in part, "protective devices shall be provided to isolate failed equipment automatically."

Example 1: The team noted that calculation MCC-1381.05-00-0214, "Unit 1 and 2, 125VDC Vital I&C Power System (EPL) Short Circuit Analysis," Rev. 7, identified that the Class 1E 125VDC distribution panel MCCBs, GE model TED MCCBs in the EVDA power distribution panel, were Underwriters Laboratories (UL) rated for a 10,000-ampere interrupt rating. Further, the calculation identified the available fault current at the TED MCCBs as high as 12,539 amperes. With this available fault current, these MCCBs have the potential to fail catastrophically when subjected to the calculated fault current.

The design of the TED MCCBs would not isolated failed equipment, and thus could cause upstream protective devices to actuate resulting in the loss of a train of ESF components.

Example 2: Calculation MCC-1381.05-00-0214 identified that the main power feeder Eaton model HFB MCCBs that provide power to the TED MCCBs have available fault currents higher than 12,539 amperes because they are closer to the power source. The team noted that the original technical data sheets from Westinghouse and later data sheets from Eaton, who purchased the Westinghouse product line, both commercially UL rated these MCCBs at 10,000-amperes. The licensee could not demonstrate that the HFB MCCBs were qualified for fault currents greater than 10,000-amperes. With the documented UL rating, these MCCBs could catastrophically fail when subjected to the available fault currents. The design of the HFB MCCBs may not isolated failed equipment, and thus could cause upstream protective devices to actuate resulting in the irreparable loss of a train of ESF components.

Analysis:

The licensee's failure to design the Class 1E electric system MCCBs in accordance with IEEE 308-1971 Sections 4.1 and 5.3.5 was a performance deficiency. The performance deficiency was determined to be more than minor because it was associated with the Design Control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, inadequate design and verification of MCCBs in the Class 1E electric system failed to ensure the availability, reliability, and capability of the ESF components. The team used IMC 0609, Att. 4, "Initial Characterization of Findings,"

issued June 19, 2012, for Mitigating Systems, and IMC 0612, App. A, "The Significance Determination Process (SDP) for Findings At-Power," issued June 19, 2012, and determined the finding to be of very low safety significance (Green) because the finding was a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC), and the SSC maintained its operability or functionality. This finding was not assigned a cross-cutting aspect because the issue did not reflect current licensee performance.

Enforcement:

Title 10 CFR Part 50, Appendix B, Criterion III, "Design Control," required, in part, that "design control measures shall provide for verifying or checking the adequacy of design." Contrary to the above, since 1981, the licensee failed to establish design control measures to provide for verifying or checking the adequacy of design. Specifically, the licensee's design control measures failed to verify the adequacy of GE model TED and Eaton model HFB molded case circuit breakers in the Class 1E electric system. The licensee determined the systems were operable because upstream protective devices provided protection from a failed HFB and/or TED MCCBs, and the HFB and TED MCCBs would be replaced with MCCBs that have adequate ratings. Because this violation was of very low safety significance (Green), and the examples were entered into the licensee's corrective action program as Action Request (AR)01929605 and AR 1936741, this violation is being treated as an NCV, consistent with Section 2.3.2 of the NRC Enforcement Policy. (NCV 05000369/2015007-01, 05000370/2015007-01, Failure to Verify Protection System DC Molded Case Circuit Breaker Ratings.)

b.2 Failure to Perform Adequate Periodic Testing of Molded Case Circuit Breakers

Introduction:

The team identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion XI, "Test Control," consisting of two examples. In one example, the licensee failed to scope some Class 1E molded case circuit breakers (MCCBs) into the Class 1E MCCB testing program. In the second example, the licensee test procedure pre-conditioned the Class 1E MCCBs before testing their safety function.

Description:

The team identified two examples of a performance deficiency related to the licensee's test program for safety related MCCBs that was established in 1991.

McGuire's UFSAR Section 8.1.4, "Design Criteria," for the Electric Power Systems, stated, in part, "In the design of all Essential Auxiliary Power Systems, the criteria set forth in -, IEEE 308-1971-, have been followed." Section 1 "Scope" of IEEE 308-1971, stated, in part, "this standard applies to those parts of the electric systems -that provide electric power to the Class IE electric equipment. These systems consist of -distribution equipment and components (e.g., transformers, switchgear -), and instrumentation and controls (e.g., relays, meters, switches, control devices)." Standard IEEE 308-1971 Section 6.3 "Periodic Equipment Tests," specified, in part, "tests shall be performed at scheduled intervals to: (1) Detect the deterioration of the system toward an unacceptable condition.

(2) Demonstrate that standby power equipment and other components that are not exercised during normal operation of the station are operable."

Example 1: The team determined that the MCCB test program excluded safety related DC panel board MCCBs. Section 401.7 of Nuclear System Directive 401, "Maintenance and Testing of Class QA1 and QA5 AC and DC Molded Cases Circuit Breakers," dated February 8, 2011, excluded certain Class 1E MCCBs from the periodic test program that were included in the scope of IEEE 308-1971. The team determined that the excluded MCCBs were required to be periodically tested to detect deterioration toward an unacceptable condition.

Example 2: The team identified that the licensee's test procedure, IP/0/A/3190/030, "Molded Case Circuit Breaker Inspection and Functional Test," Rev. 44, established steps that cleaned, cycled, and megger tested MCCBs prior to testing the trip function. The team determined that the procedure cycled the MCCBs a number of times prior to testing the trip function. NRC Information Notice (IN) 96-24, "Preconditioning of Molded Case Circuit Breakers before Surveillance," specified, in part, "when needed, they [MCCBs] must rapidly isolate a faulted or overloaded circuit to prevent equipment damage. Therefore, for the safe operation of the electrical distribution system equipment of a nuclear power plant, it is important to periodically verify their continued reliability" and "the practice of preconditioning (e.g. by manually cycling the breaker) before testing defeats the purpose of the periodic test. Such preconditioning does not confirm continued operability between tests nor does it provide information on the condition of the circuit breaker for trending purposes." The team determined that the test procedure failed to test the as-found safety function, and thus masked from detection MCCB deterioration toward an unacceptable condition, which does not meet the intent of IEEE 308-1971, Section 6.3.

Analysis:

The licensee's failure to perform adequate MCCB testing in accordance with IEEE 308-1971, Section 6.3 was a performance deficiency. The performance deficiency was determined to be more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, with inadequate periodic testing to detect deterioration and to demonstrate continued operability, the likelihood that these MCCBs will unpredictably fail when called upon increases with time in service. The team used IMC 0609, Att. 4, "Initial Characterization of Findings," issued June 19, 2012, for Mitigating Systems, and IMC 0612, App. A, "The Significance Determination Process (SDP) for Findings At-Power," issued June 19, 2012, and determined the finding to be of very low safety significance (Green) because the finding was a deficiency affecting the design or qualification of a SSC, and the SSC maintained its operability or functionality. This finding was not assigned a cross-cutting aspect because the issue did not reflect current licensee performance.

Enforcement:

Title 10 CFR 50, Appendix B, Criterion XI, "Test Control," stated, in part, "a test program shall assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents." Contrary to the above, since 1991, the licensee failed to assure that all testing required to demonstrate that SSCs would perform satisfactorily in service was identified and performed in accordance with written test procedures that incorporated the requirements and acceptance limits contained in applicable design documents. Specifically, the licensee failed to assure that all testing required to demonstrate that the safety related MCCBs would perform satisfactorily in service was accomplished in accordance with the acceptance limits contained in IEEE 308-1971. The licensee's determined the systems were operable because an engineering review of previous TED breaker testing and PM's has not shown a trend of degradation of the breakers ability to perform its function. In addition, the licensee would develop a more extensive and adequate testing program.

Because this violation was of very low safety significance (Green) and the examples were entered into the licensee's corrective action program as AR 1936760 and AR 01934403, this violation is being treated as an NCV consistent with Section 2.3.2 of the NRC Enforcement Policy. (NCV 05000369/2015007-02, 05000370/2015007-02, Failure to Perform Adequate Periodic Testing of Molded Case Circuit Breakers.)

.3 Operating Experience

a. Inspection Scope

The team reviewed five operating experience issues for applicability at the McGuire Nuclear Station. The team performed an independent review of these issues and, where applicable, assessed the licensee's evaluation and dispositioning of each item. The issues that received a detailed review by the team included:

• Westinghouse NSD-TB-91-07-R1, "Over pressurization of RCP 11 Seal Leak off Line"

• Operating experience on Complex Programmable Logic Device (CPLD) Based Solid State Protection System (SSPS) Cards (EGM 14-002, "Dispositioning Westinghouse Pressurized Water Reactor Licensee Noncompliance with 10 CFR 50.59, "Changes, Tests, and Experiments," for the Installation of Complex Programmable Logic Device (CPLD) Based Solid State Protection System (SSPS) Cards")

• NRC Information Notice No. 90-25, "Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-up"

• NRC IE Circular No. 79-22, "Stroke Times for Power Operated Relief Valves"

• NRC Information Notice No. 96-27, "Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation"

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On June 5, 2015, the team presented the inspection results to Mr. Capps and other members of the licensee's staff.

In addition, on July 20, 2015, the inspectors conducted a final exit meeting via telephone with Mr. Capps and other members of your staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

4OA7 Licensee-Identified Findings

The following violation of very low safety significance (Green) was identified by the licensee and is a violation of NRC requirements, which meets the criteria of the NRC Enforcement Policy for being dispositioned as a Non-Cited Violation.

Title 10 CFR 50, Appendix B, Criterion III, "Design Control," required, in part, that "design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of a suitable testing program." The McGuire Updated Final Safety Analysis Report, Table 1-4, "Regulatory Guides" stated, in part, "Reg. Guide 1.53 - Application of the Single-Failure Criterion to Nuclear Power Plant Protection System (Rev. 0) [was] Adopted." Regulatory Guide (RG) 1.53 specified that, subject to it's regulatory positions, "IEEE 379-1972 (IEEE Trial Use Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems) provides an adequate interim basis for complying with Section 4.2 of IEEE 279-1971." Standard IEEE 379-1972 Section 3 "Philosophy" specified, in part: "(2) Detectability. All potential single failures are detectable failures - detectable by periodic tests, anomalous indications, or by alarms.

(3) Nondetectability. For the purpose of analysis, all potential nondetectable failures will be identified and all system potential single failures will be considered to be coincident with any and all combinations of nondetectable failures." Standard IEEE 379-1972 Section 5.2 "Undetectable Failures" specified, in part, "In the single-failure analysis all potential undetectable failures should be identified- When undetectable failures are identified, the following courses of action are available:

(1) The preferred course is to redesign the protection system or the test scheme to eliminate potential undetectable failures, or (2) In the analysis of the effect of each single failure, all potential undetectable failures must be assumed to be in their failed mode"

Contrary to the above, since original startup, the interlocks for the McGuire ND system piggyback motor operated valves and NI miniflow motor operated valves were not included in the periodic test program, nor did the analysis identify undetectable failures assumed to be in their failed mode. The inspectors determined that the licensee's failure to account for undetectable failures in a single failure analysis as specified by IEEE 379-1972, was a performance deficiency. The performance deficiency was determined to be more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. In accordance with IMC 0609, Appendix A, the issue was determined to be of very low safety significance (Green) because the SSC maintained its operability or functionality. This issue was documented in the licensee's corrective action program as AR 01906228.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

A. Dewhurst, Civil Design Contractor

B. Meyer, Principal Nuclear Engineer

B. Richards, Sr. Nuclear Engineer

C. Lee, Mgr. Nuclear Engineer

C. Riddle, Lead Nuclear Eng. Technologist

D. Painter, Principal Nuclear Engineer

G. Cutri, Lead Nuclear Engineer

J. Brady, Nuclear Licensing Consultant

J. Herrick, Lead Nuclear Engineer

J. Policke, Principal Nuclear Engineer

J. Robertson, Mgr. Nuclear Regulatory Affairs

K. Crane, Sr. Nuclear Licensing Spc.

K. Norris, Lead Nuclear Eng. Technologist

M. Hunt, Mgr. Nuclear Engineering

M. Weiner, Principal Nuclear Engineer

N. Kunkel, Director Nuclear Engineering

S. Andrews, Sr. Nuclear Engineer

S. Capps, Site Vice President, McGuire Nuclear Site

T. Pederson, Lead Nuclear Engineer

T. Sarver, Principal Nuclear Engineer

NRC personnel

R. Cureton, Resident Inspector, Division of Reactor Projects

F. Ehrhardt, Chief, Projects Branch 1, Division of Reactor Projects

J. Hanna, Senior Reactor Analyst, Division of Reactor Projects

J. Zeiler, Senior Resident Inspector, Division of Reactor Projects

J. Worosilo, Senior Project Engineer, Projects Branch 1, Division of Reactor Projects

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened and Closed

05000369, 370/2015007-01 NCV Failure to Verify Protection System DC Molded Case Circuit Breaker Ratings [Section 1R21.2.b.1]

05000369, 370/2015007-02 NCV Failure to Perform Adequate Periodic Testing of Molded Case Circuit Breakers [Section 1R21.2.b.2]

LIST OF DOCUMENTS REVIEWED

Procedures

AP/1/A/5500/20, Loss of RN, Rev. 33

AP/2/A/5500/22, Loss of VI, Rev.31

EP/1/A/5000/E-0, Reactor Trip or Safety Injection, Rev. 34

EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant, Rev. 16

EP/1/A/5000/F-0, Critical Safety Function Status Trees, Rev. 6

IP/0/A/3066/013C, Rotork Actuator Testing Using Kalsi Engineering Test Bench With VIPER, Rev. 16

NSD-408, Testing, Rev. 18

OP/1/A/6500/001, Liquid Waste System, Rev. 94, completed 4/4/15

OP-MC-STM-BB, McGuire Operations Training, Rev. 36

PT/0/A/4250/004, Fire Barrier Inspection, Rev. 35 PT/2/A/4403/008, RN Train 2B Flow Balance, Rev. 65 RP/0/A/5700/007, Earthquake, Rev. 24

TT/0/A/9100/607, RN Pump Characteristic Test, Rev. 0

AP/1/A/5500/07, Loss of Electrical Power, Rev. 35

AP/1/A/5500/20, Loss of RN, Rev. 33 AP/2/A/5500/22, Loss of VI, Rev.31 CP/0/A/8120/044, Particulate Containment in Fuel Oil, dated 4/40/2015

CP/0/A/8600/027, Sampling Diesel Fuel Oil Tank Trucks, dated 3/10/2015

CP/0/A/8600/027, Sampling Diesel Fuel Oil Tank Trucks, Rev. 14

CP/1/A/8600/041, Unit 1 Diesel Fuel Oil Sampling, dated 4/20/2015

CP/2/A/8600/041, Unit 2 Diesel Fuel Oil Sampling, dated 4/20/2015 EDM - 102, Instrument Setpoint/Uncertainty Calculations, Rev.4 EP/1/A/5000/E-0, Reactor Trip or Safety Injection, Rev. 34

EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant, Rev. 16

EP/1/A/5000/ES-1.3, Transfer to Cold Leg Recirc, Rev. 27

EP/1/A/5000/ES-1.4, Transfer to Hot Leg Recirc, Rev. 5 EP/1/A/5000/F-0, Critical Safety Function Status Trees, Rev. 6 IP/0/A/3002/009, Auxiliary Feedwater Pumps Suction Pressure Sw Calibration, Rev. 18

IP/0/A/3066/013C, Rotork Actuator Testing Using Kalsi Engineering Test Bench With VIPER, Rev. 16 IP/0/B/3050/013 D, FWST Heater Test, dated 2/23/2013

IP/1/A/3250/012 A, Diesel Load Sequencer 1A Timer Calibration, Rev. 008 IP/2/A/3090/021, KC Loop Calibration and Operational Test, dtd 10/17/2013 IP/O/A/3250/026, NTS Tempo 812 Series Time Delay Calibration, Rev.006

MCM 1301.00-0033.001, Fuel Oil Transfer Pump Group 7200, Rev. D3

MCM 1301.00-0034.001, Fuel Oil Transfer Pump Group 7200, Rev. D2

MCM 1301.00-0035.001, 275 Gallon Day Tank, Rev. D2 MCM 3.7, Petroleum Products Analytical Requirements and Corrective Actions, Rev. 22 MP/0/A/7150/046, Seal Water Injection Filter Removal And Installation, Rev. 16

MP/0/A/7650/074, Service Level I And III Surface Preparation And Coating Application, Rev. 23 MP/0/B/7300/062, Safe Shutdown Facility Diesel Inspection And Oil Sampling, Rev. 10

NSD-408, Testing, Rev. 18

OP/1/A/6100/010H, Annunciator Response For Panel 1AD-7, Rev. 65 OP/1/A/6100/22, Refueling Water Storage Tank Level (Volume vs. Tank Level), Enclosure 4.3, Curve 7.7 OP/1/A/6500/001, Liquid Waste System, Rev. 94, completed 4/4/15

OP/2/A/6100/22, Refueling Water Storage Tank Level (Volume vs. Tank Level), Enclosure 4.3, Curve 7.7

OP-MC-STM-BB, McGuire Operations Training, Rev. 36

OP-MC-STM-SM:107, Control Steam Pressure Locally using SM PORVs, Rev. 12

OP-MC-STM-SM:189T, Locally Close 1SV-25, Rev. 1

PT/0/A/4200/002, Standby Shutdown Facility Operability Test, Rev. 62

PT/0/A/4250/004, Fire Barrier Inspection, Rev. 35

PT/0/A/4600/113, Operator Time Critical Task Verification, 5/2013

PT/0/B/4700/085, Environmental Chemistry Periodic Surveillance for Emergency Diesel Generator New Fuel Oil, dated 1/13/2015 PT/1/A/4200/009, Engineered Safety Features Actuation Periodic Test Train A, Rev. 142

PT/1/A/4200/017A, NV to Cold Legs Flow Balance, dated 10/15/2014

PT/1/A/4200/018, AFW Auto-Swap Time Delay Relay Testing, Rev. 5

PT/1/A/4200/041, Unit 1 SSF Systems Integrated Test, Rev. 004 PT/1/A/4200/017B, NI to Cold Legs Flow Balance, dated 4/30/1997 PT/1/A/4201/015A, 1A Safety Injection Pump Head Curve Performance Test, Rev. 23, dated 9/18/2014 PT/1/A/4206/015B, 1B Safety Injection Pump Head Curve Performance Test, Rev. 27, dated 10/20/2014 PT/1/A/4209/012A, Centrifugal Charging Pump 1A Head Curve Performance Test, Rev. 25, dated 9/28/2014 PT/1/A/4209/012B, Centrifugal Charging Pump 1B Head Curve Performance Test, Rev. 034, dated 11/3/2014 PT/1/A/4250/033, SM PORV and PORV Isolation Valve Movement Test, dtd 9/5/2014

PT/1/A/4250/033, SM PORV and PORV Isolation Valve Movement Test, dtd 10/28/2014 PT/1/A/4252/007 A, CA System Train 1B Performance Test, Rev. 031 PT/1/A/4255/004, SV Train A Valve Stroke Timing Quarterly, dtd 1/30/2015

PT/1/A/4350/004 A, 1A D/G Periodic and Load Sequencer Test, Rev. 031

PT/1/A/4350/017 A, 1A D/G Fuel Oil Transfer Pump Performance Test, dated 3/3/2015

PT/1/A/4350/017 B, 1B D/G Fuel Oil Transfer Pump Performance Test, dated 1/19/2015 PT/1/A/4350/055 A, 1A D/G Slave Start Test, Rev. 026 PT/1/A/4401/014, Train A KC/ND Hx Valve Stroke Timing Quarterly, dtd 1/29/2015

PT/1/A/4401/014A, Train A KC/ND Hx Valve Stroke Timing Quarterly, dtd 2/3/2015

PT/1/A/4401/014B, Train B KC/ND Hx Valve Stroke Timing Quarterly, dtd 3/12/2015

PT/1/A/4403/001B, 1B RN Pump Performance Test, dtd 4/8/2015

PT/1/A/4403/002, RN Train A Valve Stroke Timing Quarterly, Rev. 64 PT/1/A/4403/002, RN Train A Valve Stroke Timing Quarterly, dtd 11/19/2014 PT/1/A/4403/002, RN Train A Valve Stroke Timing Quarterly, dtd 8/1/2014

PT/1/A/4403/002, RN Train A Valve Stroke Timing Quarterly, dtd 2/6/2015

PT/1/A/4403/002B, RN Train A Valve Stroke Timing Quarterly, dtd 1/14/2015

PT/1/A/4403/002B, RN Train B Valve Stroke Timing Quarterly, dtd 4/8/2015 PT/1/A/4403/003B, RN Train B Valve Stroke Timing Quarterly, dtd 9/19/2014 PT/1/A/4600/003 B, Daily Surveillance Items, dated 4/5/2015

PT/1/A/4600/003 B, Daily Surveillance Items, dated 4/6/2015

PT/1/A/4600/003 B, Daily Surveillance Items, dated 4/8/2015

PT/1/A/4600/003 B, Daily Surveillance Items, dated 4/8/2015

PT/1/A/4600/003 C, Weekly Surveillance Items, dated 3/21/2015 PT/1/A/4600/003 C, Weekly Surveillance Items, dated 3/28/2015 PT/1/A/4600/003 C, Weekly Surveillance Items, dated 4/4/2015

PT/1/A/4700/056, Unit 1 Containment Building Civil Structures Inspection, Rev. 14

PT/1/B/4700/083, Unit 1 Environmental Chemistry Periodic Surveillance for Emergency Diesel Generator Stored Fuel Oil, dated 1/13/2015 PT/2/A/4200/17A, NV to Cold Legs Flow Balance, dated 5/10/2005 PT/2/A/4200/17B, NI to Cold Legs Flow Balance, dated 12/10/1997 PT/2/A/4206/015A, Safety Injection Pump 2A Head Curve Performance Test and Acceptance Testing of Various NI Check Valves, Rev. 20, dated 4/9/2014 PT/2/A/4206/015B, Safety Injection Pump 2B Head Curve Performance Test and Acceptance Testing of Various NI Check Valves, Rev. 20, dated 4/9/2014 PT/2/A/4209/012A, 2A NV Pump Head Curve Performance Test and Acceptance Testing of Various NV/NI Check Valves, Rev. 16, dated 4/9/2014 PT/2/A/4209/012B, Centrifugal Charging Pump 2B Head Curve Performance Test, and Acceptance Testing of Various NV/NI Check Valves, Rev. 16, dated 4/9/2014 PT/2/A/4350/017 A, 2A D/G Fuel Oil Transfer Pump Performance Test, dated 12/30/2015

PT/2/A/4350/017 B, 2B D/G Fuel Oil Transfer Pump Performance Test, dated 4/7/2015 PT/2/A/4401/009A, KC Train 2A Flow Verification, dtd 12/9/2013 PT/2/A/4403/008, RN Train 2B Flow Balance, Rev. 65

PT/2/A/4600/003 B, Daily Surveillance Items, dated 4/5/2015

PT/2/A/4600/003 B, Daily Surveillance Items, dated 4/6/2015

PT/2/A/4600/003 B, Daily Surveillance Items, dated 4/7/2015 PT/2/A/4600/003 C, Weekly Surveillance Items, dated 3/21/2015 PT/2/A/4600/003 C, Weekly Surveillance Items, dated 3/28/2015

PT/2/A/4600/003 C, Weekly Surveillance Items, dated 4/4/2015

PT/2/B/4700/083, Unit 2 Environmental Chemistry Periodic Surveillance for Emergency Diesel Generator Stored Fuel Oil, dated 1/22/2015 RP/0/A/5700/007, Earthquake, Rev. 24 TT/0/A/9100/607, RN Pump Characteristic Test, Rev. 0 IP/1/A/4971/001, Brown Boveri

ITE 50 and

ITE 51 Relays Test, Rev. 16

IP/1/A/4971/002, Brown Boveri

GR-5 Ground Shield Relay, Rev. 06

IP/1/A/4972/001, Essential Shield Trip Device Test, Rev. 7

MCDD-138-00.81, Elementary Diagram Train B Eng. Safeguards Modulating Control Valves, Rev. 3 IP/0/A/2001/004 B, ABB K-Line 600 VAC Air Circuit Breaker Inspection and Maintenance, Rev. 18 IP/0/A/2001/004 D, Refurbishing ABB/ ITE K-Line 600 VAC Air Circuit Breaker, Rev. 21

IP/0/A/3250/035, Valcor Solenoid Valves V70900-21, V70900-65 and V70900-65-24 Maintenance, Rev. 44 PT/1/A/4403/005B, RN Train 1B Head Curve Verification, Rev. 23 IP/0/A/3250/035 A, Valcor Solenoid Valves V70900-21, V70900-65 and V70900-65-24 Removal and Replacement, Rev. 4 IP/0/A/2001/004 A, 5 HK Air Circuit Breaker Inspection and Maintenance, Rev. 14

AP/1/A/5500/017, Loss of Control Room, Rev. 28

Drawings

2-MCA-S-YC-500-1, Chilled Water System EDS Line Numbers 965 & 961, Rev. 1

MC-ISIL-1574-01.00, ASME Section XI Inservice Inspection Pressure Test Boundary of Nuclear Service Water System (RN), Rev. 4

MC-1027-04.00, Auxiliary Nuclear Service Water Pipe Intake Layout and Details, Rev. 12

MC-1202-4, Auxiliary Building Units 1 & 2 Floor El 733+0 General Arrangement Battery Room Plan, Rev. 31

MC-1202-4.2, Auxiliary Building Architectural Battery Room El. 733+0 Details and Notes, Rev. 3

MC-1202-4.1, Auxiliary Building Architectural Battery Room El. 733+0 Plan, Sections, & Details, Rev. 6

MC-1220-14, Auxiliary Building Units 1 & 2 Trench Drain Layout El. 716' + 0"- El. 733' + 0" - El. 767' + 0", Rev. 10

MC-1220-096, Auxiliary Building Units 1 & 2 Cable Tray Covers Miscellaneous Steel, Rev. 10

MC-1220-97, Auxiliary Building Units 1 & 2 Flood Protection Wall Elevation, Rev. 15

MC-1220-98, Auxiliary Building Units 1 & 2 Flood Protection Penetration Schedule and Details, Rev. 23

MC-1220-114, Auxiliary Building Unit 1 Plan at El. 733'-0" Miscellaneous Steel, Rev. 1

MC-1220-151, Auxiliary Building Unit 2 Plan at El. 733'-0" Miscellaneous Steel, Rev. 1

MC-1220-153, Auxiliary Building Unit 2 Flood Protection for Exterior and Interior Doghouse Above 750'-0", Rev. 8

MC-1220-215, Auxiliary Building Interior and Exterior Doghouse Penetration Locations Requiring Flood Protection Elevation 750'-0" to 756'-10", Rev. 5

MC-1240-04.10-01, Radiation Zone Map Auxiliary Building Elevation 733'+0" Figure 4.10-1, Rev. 0

MC-1240-04.10-02, Pipe Rupture Zone Map Auxiliary Building Elevation 733'+0" Figure 4.10-2, Rev. 0

MC-1315-00.04, General Arrangement HVAAC System Boundaries Plan at Elevation 733+0 & 739+0, Rev. 2

MC-1315-01.02-002, Auxiliary Building Fire, Flood, & HVAC Boundaries General Arrangement Plan at El. 716+0, Rev. 0

MC-1315-01.02-004, Auxiliary Building Fire, Flood, & HVAC Boundaries General Arrangement Aux. Feedwater Pump Room Plan at El. 716+0, Rev. 0

MC-1315-01.03-004, Auxiliary Building Fire, Flood, & HVAC Boundaries General Arrangement Plan at El. 733+0, Rev. 0

MC-1315-01.03-005, Auxiliary Building Fire, Flood, & HVAC Boundaries General Arrangement Plan at El. 733+0, Rev. 5

MC-1331-01.00, Condenser Cooling Water Low Level Intake Pipes Support Structure and Valve Platform Concrete and Misc. Steel, Rev. 3A

MC-1384-07.07-00, Fire Plan Unit 2 Turbine Building Elevation 739'+0", Rev. 8

MC-1384-07-08-00, Fire Plan Unit 2 Turbine Building Elevation 760+6, Rev. 10

MC-1384-07.14-00, Fire Plan Auxiliary Building Elevation 733+0, Rev. 12

MC-1384-07.14-03, Fire Plan Auxiliary Building Elevation 733+0 & 736+6, Rev. 12

MC-1506-04.85-01, Piping Layout Exterior Miscellaneous Piping Plans and Sections, Rev. 33

MC-1522-03.46-00, Heating-Ventilation-Air conditioning Battery Room El. 733+0 Plans, Sections, & Details, Rev. 13

MC-1578-03.00, Flow Diagram of Control Area Ventilation System (VC) Cable, Battery, and MCC Rooms, Rev. 16

MC-2506-04.85-00, Piping Layout Exterior Miscellaneous Piping Plans and Sections, Rev. 27

MC 1384-07-09-00, Fire Plan Unit 2 Turbine Building Elevation 786+0, Rev. 4

MCEE-0.41-00.07, Elementary Diagram NDHX 1A Outlet to Centrifugal Charging Pump 1A and 1B Block Valve 1ND0058A, Rev. 6

MCEE-114-00.03, Elementary Diesel Generator Load Sequencer Part 3, Rev. 5

MCEE-114-00.03-01, Elementary Diesel Generator Load Sequencer Relay, Rev. 21

MCEE-114-00.04, Elementary Diesel Generator Load Sequencer Part 4, Rev. 7

MCEE-114-00.04-01, Elementary Diesel Generator Load Sequencer Relay, Rev. 20

MCEE-114-00.05, Elementary Diesel Generator Load Sequencer Part 5, Rev. 7

MCEE-114-00.06, Elementary Diesel Generator Load Sequencer Part 6, Rev. 10

MCEE-114-00.06-01, Elementary Diesel Generator Load Sequencer Relay, Rev. 5

MCEE-114-00.07, Elementary Diesel Generator Load Sequencer Part 7, Rev. 3

MCEE-114-00.08, Elementary Diesel Generator Load Sequencer Part 8, Rev. 10

MCEE-114-00.08-01, Elementary Diesel Generator Load Sequencer Relay, Rev. 4

MCEE-115-00.31, Elementary 4160V Swgr #1ETB, Unit#11 AFW Pump Motor, Rev.18

MCEE-115-00.31-02, Elementary 4160V Swgr #1ETB, Unit#11 AFW Pump Motor, Rev.13

MCEE-115-00.15-03, Elementary 4160V Swgr #ETA, Unit#14 EDG Feeder Brkr, Rev. 13

MCEE-115-00.15-05, Elementary 4160V Swgr #ETA, Unit#14 EDG Feeder Brkr, Rev. 8

MCEE-115-00.32-02, Elementary 4160V Swgr #1ETB, Unit#12 NSW Pump Motor, Rev.6

MCEE-138-00.04, Elementary CCS Supply B Shutoff Valve 0RN4A, Rev. 12

MCEE-138-00.04-01, Elementary CCS Supply B Shutoff Valve 0RN4A, Rev. 5

MCEE-138-00.08, Elementary Low Level Supply B Shutoff 0RN10A, Rev. 11

MCEE-138-00.08-01, Elementary Low Level Supply B Shutoff 0RN10A, Rev. 9

MCEE-138-00.26, Elementary 1A Supply to AFW Isolation Vlv 1RN69A, Rev. 10

MCEE-138-00.26-01, Elementary 1A Supply to AFW Isolation Vlv 1RN69A, Rev. 8

MCEE-138-00.45-01, Elementary 1B Supply to AFW Isolation Vlv 1RN162B, Rev.11

MCEE-0141-00.07, Elementary ND HX 1A Outlet to Charging Pump 1A and 1B Block Valve 1ND0058A, Rev. 6

MCEE-0147-21.00, Elementary AFW NSW Supply Valve 1CA0015A, Rev. 4

MCEE-0147-22.00, Elementary AFW NSW Supply Valve 1CA0018B, Rev. 6

MCEE-0147-28.00, Elementary AFW NSW Supply Valve 1CA0086A, Rev. 5

MCEE-0147-29.00, Elementary AFW NSW Supply Valve 1CA0116B, Rev. 6

MCEE-151-00.51, Elementary Diagram ND HX 1B to Safety Injection Pump 1B 1NI136B, Rev. 15

MCEE-151-00.51, Elementary ND HX 1B to Safety Injection Pump 1B 1NI136B, Rev. 15

MCFD-1554-03.01, Flow Diagram of Chemical and Volume Control System (NV), Rev. 24

MCFD-1560-01.00, Flow Diagram of Standby Shutdown Diesel System (AD), Rev 6

MCFD-1561-01.00, Flow Diagram of Residual Heat Removal System (ND), Rev. 23

MCFD-1561-01.00, Flow Diagram of Residual Heat Removal System (ND), Rev. 23

MCFD-1562-01.00, Flow Diagram of Safety Injection System (NI), Rev. 6

MCFD-1562-02.00, Flow Diagram of Safety Injection System (NI), Rev. 8

MCFD-1562-02.01, Flow Diagram of Safety Injection System (NI), Rev. 7

MCFD-1562-03.00, Flow Diagram of Safety Injection System (NI), Rev. 17

MCFD-1562-03.01, Flow Diagram of Safety Injection System (NI), Rev. 14

MCFD-1562-03.00, Flow Diagram of Safety Injection System (NI), Rev. 17

MCFD-1565-01.01, Flow Diagram of Liquid Waste Recycle System, Rev. 7

MCFD-1573-01.01, Component Cooling Water Flow Diagram, Rev. 10

MCFD-1574-01.00, Flow Diagram of Nuclear Service Water System (RN), Rev. 27

MCFD-1574-02.00, Nuclear Service Water Flow Diagram, Rev. 31

MCFD-1574-02.00, Nuclear Service Water Flow Diagram, Rev. 31

MCFD-1574-01.01, Nuclear Service Water Flow Diagram, Rev. 32

MCFD-1592-01.01, Flow Diagram of Auxiliary Feedwater System, Rev. 31

MCFD-1603-01.00, Flow Diagram of Hydrogen Blanket and Bulk Storage System (GB, GS), Rev. 11

MCFD-1609-03.00, Flow Diagram of Diesel Generator Engine 1A Fuel Oil System (FD), Rev. 21

MCFD-1609-03.01, Flow Diagram of Diesel Generator Engine 1B Fuel Oil System (FD), Rev. 17

MCFD-2609-03.00, Flow Diagram of Diesel Generator Engine 2A Fuel Oil System (FD), Rev. 10

MCFD-2609-03.00, Flow Diagram of Diesel Generator Engine 2A Fuel Oil System (FD), Rev. 18

MCFD-2609-03.01, Flow Diagram of Diesel Generator Engine 2B Fuel Oil System (FD), Rev. 12

MCID-2499-WP.02, Instrument Detail Turbine Building Sump Level, Rev. 3

MCM-1050.00-0058.001, Vert Grating Perf 309 TP C, 2/8/2007

MCM-1201.04-0027, Filter Assembly-GN-1BH 80 GPM, Rev. 1

MCM-1201.04-0103, Purchase Requisition & Bill of Materials, 4-12'-00" O.D. X 59'-2" 50,000 Gal Storage Tanks, Rev. 2

MCM-1203.05-6, Fuel Oil Recirculation Pump, dated 4/7/1977

MCM-1205.00-0037.001, Gate Valve Assembly, Rev. A

MCM-1205.19-0068.001, Rotork Alternate Wiring Method for Torque Bypass Switch, Rev. 014

MCM-1211.00-1802-001, Fire Dampers by Ruskin, dated 8/21/85

MCM-1318.16-0003 001, Squirrel Cage Induction Motor Data Sheet, 12/20/1973

MCM 1201.04-0099-001, 2' Dia Undergroound Diesel Fuel Oil Storage Tank, Sht 1 of 3, Rev. 9

MCSF-1554.NV-01, Summary Flow Diagram Chemical & Volume Control System, Rev. 8

MCSF-1554.NV-02, Summary Flow Diagram Chemical & Volume Control System, Rev. 1

MCSF-1574.RN-01, Flow Diagram of Nuclear Service Water (RN), Rev. 6C

MCSF-1592.CA-01, Summary Flow Diagram (CA), Rev. 7

MCSF-1609.FD-01, Flow Diagram Diesel Generator Engine Fuel Oil System (FD), Rev.1

MCSF-1609.LD-01, Flow Diagram EDG Lubrication Oil System (LD), Rev.1

MCTC-1571-FW.0001-01, Test Acceptance Criteria FW system Index, Rev. 2

MCTC-1571-FW.S001-01, Test Acceptance Criteria ECCS FWST Requirements, Rev. 4

MCTC-1571-FW.S002-01, Test Acceptance Criteria Borated Water Source - Operating, Rev. 4

MCTC-1571-FW.S003-01, Test Acceptance Criteria Borated Water Source - Shutdown, Rev. 3

MCTC-1571-FW.S005-01, Test Acceptance Criteria FWST Level for Automatic Switchover to Recirculation, Rev. 5

MCCD-1702-02.00, One Line Diagram 4160V Essential Auxiliary Power System, Rev. 13

MCCD-1703-06.00, One Line Diagram 600 V AC Load Centers 1ELXA and 1ELXC, Rev. 4

MCEE-138-00.27, Elementary Diagram 1A Diesel Generator HX Supply Isolation Valve 1RN70A, Rev. 12

MCEE-138-00.28, Elementary Diagram HX 1A Control Valve 1RN73A, Rev. 6

MCEE-0147-13.00, Elementary Diagram Aux Feedwater System Turbine Start Circuit (Auto), Rev. 6

MCEE-0147-31.00, Elementary Diagram Aux Feedwater System Solenoid Valves 1SASV0482 & 1SASV0484, Rev. 6

MCEE-0147-02.00, Elementary Diagram Aux Feedwater System Selector Station Control Circuit, Rev. 1

MCEE-0147-14.00, Elementary Diagram Aux Feedwater System Flow to Steam Generator Status, Rev. 1

MCEE-0147-14.01, Elementary Diagram Aux Feedwater System TD CA Pump Miniflow to UST Status and Indicating Lights, Rev. 2

MCID-1499-SA.02, Instrument Detail Steam to Auxiliary FWPT, Rev. 4

MCDD-138-00.81, Elementary Diagram Train B Eng. Safeguards Modulating Control Valves, Rev. 3

MCID-1499-RN.09, Instrument Detail Nuclear Service Water Pump Motor Cooler Temperature Control, Rev. 1

MCEE-115-00.32, Elementary Diagram 4160 V Switchgear #1ETB, Unit 1 and 2 Nuclear Service Water Pump Motor #1B, Rev. 10

MCRS-0115-01.01, Overcurrent Relay Setting 151G/ETA-01, Rev. 1

MCRS-0115-01.02, Overcurrent Relay Setting 151/ETA-01, Rev. 1

MCRS-0115-01.03, Overcurrent Relay Setting 150B/ETA-01, Rev. 2

MCRS-0115-01.04, Overcurrent Relay Setting 125/ETA-01, Rev. 4

MCRS-0115-01.05, Timer/Time Delay Relay Setting 162B/ETA-01, Rev. 1

MCEE-115-00.04, Elementary Diagram 4160 V Switchgear #1ETA, Unit #3 4160/600V Transformer 1ELXA, Rev. 7

MCEE-115-00.04-02, Elementary Diagram 4160 V Switchgear #1ETA, Unit #3 4160/600V Transformer 1ELXA, Rev. 5

MCEE-115-00.39, Elementary Diagram 4160 V Breaker Internal Control, Rev. 5

MCEE-112-00.01, Elementary Diagram 600V Essential Load Center 1ELXA Compartment 4B Normal Incoming, Rev. 5

MCEE-112-00.01-01, Elementary Diagram 600V Essential Load Center 1ELXA Compartment 4B Normal Incoming Feeder Breaker, Rev. 1

MCEE-112-00.27, Elementary Diagram 600V Essential Load Center Breaker Internals, Rev. 2

Calculations

MCC-1139.01-00-0054, Auxiliary Building Flood Protection, Rev. 16

MCC-1139.01-00-0268, Turbine Building Design Basis Flooding Analysis, Rev. 2

MCC-1167.01-00-0001, Coatings Inside Containment, Rev. 4

MCC-1205.19-00-0003, Electric Motor Operator Sizing Guidelines Per GL89-10 for Gate Valves, Rev. 43

MCC-1205.19-00-0003, Valve EMO Thrust Requirements, Rev. 24

MCC-1206.02-84-2053, RN Buried Pipe Analysis to Evaluate Pipe Degradation, Rev. 7

MCC-1206.47-00-0001, Evaluation of the Environmental Consequences Due to Pipe Rupture, Rev. 4

MCC-1206.47-00-0002, Determination of Maximum Moderate Energy Water Spray Temperatures in Pipe Rupture Zones, Rev. 1

MCC-1206.47-69-1001, Auxiliary Building Flooding Analysis, Rev. 17

MCC-1210.01-00-0068, Instrument Loop Accuracy Calculation for FWST Level (Loops FW500, 501, 502), Rev. 8

MCC-1210.04-00-0060, FWST Temperature Loop Accuracy Calculation (loop FW5030, FW5120, FW5280), Rev. 14

MCC-1210.04-00-0068, FWST WR Level Instrument Uncertainty Calculation, Rev. 8

MCC-1210.04-00-0043, Instrument Loop Uncertainty for

CA-RN Swap over Suction Switch Loops, Rev. 6

MCC-1223.02-00-0001, ESF Valve Response Time Testing Requirements, Rev. 23

MCC-1223.11-00-0024, Data Sheets for ND EMO Valves Per Gl89-10, Rev. 9

MCC-1223.12-00-0017, Maximum Expected Delta P's of NI EMO Valves, Rev. 12

MCC-1223.12-00-0010, Verification of Minimum Available NPSH for ECCS Pumps, Rev. 7

MCC-1223.21-00-0003, Refueling Water Storage Tank Capacity, Rev. 0

MCC-1223.21-00-0004, Refueling Water Storage Tank - Vent Sizing, Rev. 2

MCC-1223.24-00-0085, Operability Evaluation for PIP M04-3803, Analysis of RN/CA System Following a Safe Shutdown Earthquake, Rev. 2

MCC-1223.24-00-0096, RN System Flow Balance Acceptance Criteria Calculation, Rev 14

MCC-1223.24-00-0102, RN Pump NPSH and Runout Analysis, Rev. 4

MCC-1223.24-00-0138, Buried 42" RN Pipe From the LLI at Cowans Ford Dam to the Auxiliary Building, Rev. 0

MCC-1223.24-00-0050,

GL 89-10 RN Valves, Rev. 8

MCC-1223.42-00-0074, Prompt Determination of Operability for PIP M-14-011149ca Pump Motor Loads Under Adverse Conditions), Rev. 1

MCC-1223.59-03-0007, D/G Fuel Oil Requirements, Rev. 7

MCC-1226.21-00-0003, Refueling Water Storage Tank Capacity, Rev. 0

MCC-1381.05-00-0260, Emergency Diesel Loading Analysis, Rev. 5

MCC-1381.05-00-0331, FMEA of Diesel Generator load Sequencer Accelerated Sequence Circuitry, Rev. 0

MCC-1381.05-00-0258, U1, 6.9KV, 4.16KV and 600V Auxiliary Power Systems Safety-Related Voltage Analysis, Rev. 4

MCC-1535.00-00-0123, Characterization of Flood Scenarios for McGuire Nuclear Station Units 1 & 2, Rev. 3

MCC-1552.08-00-0118, FWST Level Setpoints Calculation (PIP 0-M97-0045), Rev. 11

MCC-1552.08-00-0390, Replacement Containment Recirculation Sump Strainer Performance Calculation, Rev. 2

MCC-1552.08-00-0396, Downstream Sump Debris Effects Evaluation of Auxiliary Equipment, Rev. 0

MCC-1552.08-00-0397, Sump Debris Downstream Effects Evaluation for ECCS Valves, Rev. 1

MCC-1552.08-00-0446, Evaluation of Containment Recirculation Sump Downstream Effects for MNS Units 1 & 2 Excluding Chemical Effects, Rev. 0

MCM-1151.00-0040.001, McGuire Low Level Intake Water Pipeline Seismic Fragility Assessment, Rev. 0

MCM-1205.00-0722, Seismic Acceleration Calculation Report No. 53A, Rev. 1

MCM-1205.19-0039.001, Electric Motor Operator GL89-10 Setup Information, Rev. D56

OTC-185, Thrust and Torque Calculations, Rev. 0

MCC-1381.05-00-0230, U1/2, 125Vdc Vital I&C Power System (EPL) Voltage Drop Analysis, Rev.7

MCC-1381.05-00-0258, 6.9KV, 4.16KV and 600V Auxiliary Power System Safety Related voltage, Rev. 3

MCC-1381.05-00-0214, Unit 1 and 2 125VDC Vital I&C Power System (EPL) Short Circuit Analysis, Rev. 7

MCC-1381.05-00-0094, Protective Relay Setting Calculation for Essential Switchgear, Rev. 17

MCS-1240.03-00-0001, Plant Environmental Parameters (PEP), Rev. 8

MCC-1381.05-00-0258, Unit 1, 6.9KV, 4.16KV and 600V Auxiliary Power System Safety Related Voltage Analysis, Rev. 3

MCC-1381.05-00-0265, Unit 2, 6.9KV, 4.16KV and 600V Auxiliary Power System Short Circuit Analysis, Rev. 6

MCC-1381.05-00-0301, Unit 1, 6.9KV, 4.16KV and 600V Auxiliary Power System Short Circuit Analysis, Rev. 7

Design Basis Documents

LAR 273, License Amendment Request for TS 3.3.2, 8/27/2014.

MCM-1201.04-0156.001, Technical Manual for NMSS Filters, Rev. 4

MCM-1210.03-0172.001, I/M & O/M Meriam DP Indicating Switches, Rev. D02

MCS-114.00-EQB-0001, Design Basis Specification for the EQB System, Rev. 17

MCS-120.00-EQC-0001, Design Basis Specification for the EQC System, Rev. 12

MCS-1218.04-00-0001, Containment Recirculation Sump Intake Screen Replacement Specification, Rev. 5

MCS-1223.SS-00-0001, Design Basis Specification for the Standby Shutdown System, Rev. 35

MCS-1465.00-00-0001, Design Basis Specification for Systems Single Failure (GDCS), Rev. 2

MCS-1465.00-00-0002, Design Basis Specification for System Class, Rev. 3

MCS-1465.00-00-0008, Design Basis Specification for Fire Protection, Rev. 19

MCS-1465.00-00-0009, Design Basis Specification for Seismic Design, Rev. 1

MCS-1465.00-00-001, Plant Specifications for Single Failure, Rev. 2

MCS-1465.00-00-0010, Design Basis Specification for Tornado/Wind, Rev. 2

MCS-1465.00-00-0012, Design Basis Specification for Flooding From External Sources, Rev. 2

MCS-1554.NV-00-0001, Design Basis Specification for the NV System, Rev. 31

MCS-1561.ND-00-0001, Design Basis Specification for the ND System, Rev. 20

MCS-1571.FW-00-0001, Design Basis Specification for the FW System, Rev. 26

MCS-1574.RN-00-0001, Design Basis Specification for the RN System, Rev. 47

MCS-1592.CA-00-0001, Design Basis Specification for the CA System, Rev. 32

MCS-1609.FD-00-0001, Design Basis Specification for the FD System, Rev. 17

NSD 408, Testing, Rev. 18

Nuclear Guide 1.137, Fuel Oil Systems for Standby Diesel Generators, Rev. 1

MCS-0115.00-EPC-0001, 4160 V Essential Auxiliary Power, Rev. 15

MCS-0112.00-EPE-0001, 600V Essential Auxiliary Power System, Rev. 12

Condition Report

(CRs)

AR 01572235

AR-01901517

(formerly PIP M-

14-1114) G-14-2368 G-96-0028

G-97-00040

M-06-00689

M-06-04364 M-06-0857 M-08-00353

M-08-00959

M-08-01109

M-08-07134 M-09-02341 M-09-02844

M-09-03122

M-09-0627

M-09-6278

M-10-06504 M-11-07075 M-11-07336

M-11-07537

M-11-07705

M-12-00437 M-12-01342 M-12-01400

M-12-01525

M-12-01895 M-12-02158 M-12-02503

M-12-03380

M-12-03599

M-12-03910 M-12-03955 M-12-04649

M-12-04650

M-12-05240

M-12-05360 M-12-08240 M-12-08268

M-12-10304

M-13-00439

M-13-00693

M-13-01925 M-13-02838 M-13-03040

M-13-03882

M-13-04222

M-13-06807 M-13-07003 M-13-08761

M-13-09665

M-13-09909 M-13-09987 M-13-10088

M-13-10739

M-14-00114

M-14-01043 M-14-01452 M-14-01694

M-14-01694

M-14-02524

M-14-03245 M-14-03272 M-14-05327

M-14-05789

M-14-06052

M-14-07180

M-14-07700 M-14-08235 M-14-08652

M-14-08688

M-14-08720

M-14-09443 M-14-10396 M-14-10593

M-14-11246

M-14-11456 M-14-11779 M-14-11964

M-15-00885

M-15-00903

M-15-00907 M-15-01677 M-15-01746

M-15-02038

M-15-02133

M-15-02351 M-15-02403 M-15-03513

M-15-03552

M-15-03647

M-15-0907

M-96-00530 O-02-02819 O-10-00494

Work Orders

(WO)

01757931

02151272

02027556

01728853

00390319

00581206

0207628601

01107286

01956570

01712809

02047011

0173656

01984484

01712809

02048799

00411433

01988509

01833506

02058396

01738654

2080918

01858794

02063618

201493302

2086853

02080022

02096548

203076702

2104214

01957921

02192240

204558402

02142044

01968228

01728576

212453201

0058932701

0058932701

0058939706

0058928001

0174319803

0175074101

0178437901

0178718501

0184038701

0058927901

0183242801

0186242901

0186202701

0186229902

0195700601

0195720101

0187281601

0187288901

0198259301

0204430501

0197899201

0198259201

0204614001

0204614101

0204529401

0204529501

0204640403

0204640601

204638301

0204638401

0206361801

0210017501

204701105

0204879901

0210836601

0211523101

210017601

0210195201

0213073601

0213073701

0213047701

0213058202

0213129201

0213132601

0213078001

0213078101

0201592001

0217976901

213132701

0213134301 Plant Modifications

EC 093387, Eliminate auto containment Spray Logic, Rev. 0

EC 101080, RN to CA Relocation, Rev. 17

EC 108503, Update Turbine Building and Doghouse Flood Information, Rev. 0

EC 108849, Update McGuire's PMP Flood Analysis, Rev. 0

EC 112020, Control of Turbine Driven Auxiliary Feedwater (TDCA) flow and steam generator pressure from the Control Room on SBO, Rev.

EC103327, Enable Use of Modified Pall Filters in the Seal Water Injection, dated 11/28/2011

EC103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0 H.P. AC Motor, Rev. 2 EC106659, 1/2FWLT5000/5010/5020 ADD CORRECT SPAN IN EDB, Rev. 0

EC106929, Redesign Remote Hand wheel Operation of 2FD-67, 2FD-74, Rev. 2

EC107049, Spare Motor for D/G Fuel Oil Booster Pump Motor, Rev. 3

EC107870, Standby Shutdown Facility Diesel Generator Engine Driven Fuel Pump, Rev 0 EC110198, Change in the hard facing material for 1FW0537 from NOREM (cobalt-free) to Satellite 6 (cobalt-containing), Rev 2

EC110198, Unit 1 Provide Fukushima FLEX FW System Mechanical Connections for Portable Pumps, Rev. 2

EC112228, United Electric Pressure Switch J300 Series is Obsolete.

Allow the Obsolete, Rev. 0 EC93397, Revise

MC-2730-02.04 to show wiring on devices AB, AC & CF on left side of terminal strip, Rev. 3

EC96531, MD200566 - Replace FWST Heater Terminal Boxes Mod, Rev. 3

Miscellaneous

Nuclear System Directive 401, Maintenance and Testing of Class QA1 and QA5 AC and DC

Molded Cases Circuit Breakers, dated 02/08/2011 1101016.401, Duke- McGuire GWT Excavation Support, Rev. 0

ANSI N18.2-1973, Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants ANSI/ISA-67.04.01-2000, Set points for Nuclear Safety Related Instrumentation, February 2000 AWWA C201-66, AWWA Standard for Fabricated Electrically Welded Steel Water Pipe, dated 1/23/66 DUK007-SPEC-001, Specification for Replacement Containment Recirculation Sump Intake Screen Procurement and Fabrication, Rev. 0

EDM-210, Engineering Responsibilities for Maintenance Rule, Rev. 27

ER-5.0, Equipment Inaccuracy Summary for Motor-Operated Valves, Rev. 26 Form 654, SOR Nuclear Qualified Pressure Switches, 4/13 GBC06-040, McGuire Unit 2 Certificate of Conformance for Work Order

TRAN-009-Q, Rev. 1

GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, dated 9/13/2004

GO-2006-01, Duke Power PM Program Template, Rev. 6

IN 96-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation, dated 5/1/1996

LER, Braidwood Station, Unit 1, Through-weld Leak of the Line from the 1B Seal Injection Filter to Vent Valve, dated 11/15/2010

LER, Donald C. Cook Nuclear Plant, Unit 2, Manual Reactor Trip Due to RCP Seal Degradation Caused by Accumulation of Corrosion Products, dated 2/18/2010

LER, Salem Generating Station, Unit 1, ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement), dated 7/5/2005

Letter from A. Washburn, Sulzer Pumps Inc., to A. Beaver, Duke Energy Corporation, Emergency Service Water (RN) Pumps NRC CDBI Audit Inquiry on Inadequate NPSHA Scenarios, dated 6/3/15

MCC-1205.19-00-0082, JOG Classification of McGuire's GL96-05 MOV Population, Rev. 3

McGuire Maintenance Coating Schedule

MMCS-1167.02, Service Level I Coating Schedule, Rev. 10

McGuire Nuclear Station, Units 1 and 2, Closeout of Generic Letter, 2004-02, "Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC NOS. MC4692, and MC4693)

MCM 1338.00.0041 0001, NTS Series 812 Timing Relays, Rev. 0

MCM 3.7, Petroleum Products Analytical Requirements and Corrective Actions, Rev. 22

MCM-1201.05-0195.001, Nuclear Service Water Pump I/B, Rev. D26

MCM-1205.00-0570.001, Vendor Manual for 1-RN70A Valve, 12/30/81

MCM-1205.00-0938.001, Vendor Manual for 1-RN70A Valve, 12/30/81

MCM-1205.02-0083 001, Vendor Drawing for N-MKII Valve, 2/25/74

MCM-1205.02-0122.001, Vendor Manual for 1-KC-56A

AND 81B Valve, 9/10/75

MCRS-0114-00.01, Timer/Time Delay Settings for EQB System, Rev. 1

MCS-1151.00-1, Condenser Cooling Water Pipe System, dated 4/30/71

MCS-1151.00-5, Specification for Relieving Residual Stress in the 10'-6" Diameter Condenser Cooling Water Pipes, dated 10/9/81

MCS-1205.00-1, Specification for Cast Stainless Steel Gate, Globe, and Check Valves, Rev. 7

MCS-1206.00-00-0001, McGuire Pipe Rupture Analysis Criteria Specification, dated 2/5/15

MCS-1206.00-2.1, Underground Auxiliary Nuclear Service Water Piping, dated 2/16/72

MCS-1218.04-00-0001, Containment Recirculation Sump Intake Screen Replacement Specification, Rev.5

MCS-1240.03-00-0001, Specification for Plant Environmental Parameters (PEP), Rev. 8

MCS-1465.00-00-0001, Design Basis Specification for Systems Single Failure (GDCS), Rev. 2

MCS-1465.00-00-0002, Design Basis Specification for System Class, Rev. 3

MCTC-1574.RN.V024-01, Valve Design Criteria/Operability Requirements, Rev.9 Modification Test Plan for MD100374, Rev. 0

NCMM-1167.02, Attachment 3.0 Approved Materials Sheet System 107-I, NCMM Section 5, Rev. 6

NCMM-1167.02, Attachment 4.0 Surface Preparation Procedure

DP-SP5-1(White Metal Blast Cleaning), NCMM Section 6, Rev. 9

NCMM-1167.02, Attachment 5.0 Application Procedure DP #71-1, NCM Section 7, Rev. 11

NCMM-1167.02, Attachment 6.0 Touch Up Procedure

TP-1-3, NCMM Section 8, Rev. 8

NCMM-1167.02, Attachment 7.0 Workmanship Guide

WG-1, NCMM Section 9, Rev. 6

NCMM-1167.02, Attachment 8.0, Inspection Guide IG#1, NCMM Section 10, Rev. 8

NCMM-1167.02, Coatings Product Data Sheet VIIA, NCMM Section 12, Rev. 8

NCMM-1167.02, Nuclear Coating Maintenance Specification 107-I, NCMM Section 3, Rev. 13

NSD 208, Rev. 41

OBDN Number: M-14-01114 Action Plan Summary, 5/15/2015

Oberdorfer Pumps, A Gardner Denver Product, Bronze Rotary Gear Pumps Installation, Operation, and Maintenance Instruction Oberdorfer Pumps, Bronze Close Coupled Rotary Gear Pumps, Model N993 Series

PD-EG-PWR-1611, Boric Acid Corrosion Control Program, Rev. 0PO

00077824, Element, Filter, Cartridge, 5, Cotton, 10/12/2006

PO 00183658 00002, Filter, Water, 0.1, Ultipore GF Plus Fiberglass Media, 11/6/2014

PO 00184695, Filter, Water, 0.1, Ultipore GF Plus Fiberglass Media, 4/30/2014

Rotork Publication No. AE1/4, Rotork Electric Actuators for Nuclear Power Plants, dated 5/81

SECY-77-439, Single Failure Criterion, dated 8/17/77

SG PORV JPM Procedures ST2072 WO Task Complete Comment Report (WO 00459520), Last Refreshed On: 5/20/2015 9:15:55 AM

ST2072 WO Task Complete Comment Report (WO 00469978), Last Refreshed On: 5/20/2015

9:19:39 AM

ST2072 WO Task Complete Comment Report (WO 00469978), Last Refreshed On: 5/20/2015

9:19:39 AM ST2072 WO Task Complete Comment Report (WO 01972571), Last Refreshed On: 5/14/2015 9:46:46 AM

ST2072 WO Task Complete Comment Report (WO 02014933), Last Refreshed On: 5/14/2015

9:39:51 AM

ST2072 WO Task Complete Comment Report (WO 02151085), Last Refreshed On: 5/14/2015 8:59:15 AM ST2072 WO Task Complete Comment Report (WO 02152108), Last Refreshed On: 5/14/2015

9:34:33 AM

ST2072 WO Task Complete Comment Report (WO 1972570), Last Refreshed On: 5/14/2015

9:08:37 AM ST2160 Work Order Task Completion Comments (WO 00469978), Report Executed: 5/20/2015 9:22:09 AM

ST2160 Work Order Task Completion Comments (WO 01972571), Report Executed: 5/20/2015

9:37:12 AM

ST2160 Work Order Task Completion Comments (WO 00459520), Report Executed: 5/20/2015

9:26:27 AM ST2160 Work Order Task Completion Comments (WO 02030767), as of: 7/2/2012 14:55 Strip Chart, ESF Testing Black Out with SI, 4/16/2014

System Health Report for the FW system (1/1/2015 - 3/31/2015)

System Health Report for the ND system (1/1/2015 - 3/31/2015)

System Health Report for the NV system (1/1/2015 - 3/31/2015)

WCAP-17308-NP, Treatment of Diesel Generator (DG) Technical Specification Frequency and Voltage Tolerances, 04/2012

Corrective Action Documents Written Due to this Inspection AR -

01906228 (formerly M-15-03552)

AR 01929605, 2015 CDBI Inspection Questioned 125VDC Breaker AIC rating, dated 6/1/2016 M-15-03568, SG PORV Time Critical Action to Include Ladder Prep

NCR 01929491, Perform Review of

MCM-1151.00-0040.001, "Fragility Analysis"

NCR 01929505, 2015 NRC CDBI

NCR 01929994, 2015 NRC CDBI- Enhance Battery Room HELB Discussion

NCR 01930048, 2015 NRC CDBI Inspection - Provide Enhancements to TSC Guide PIP M-15-03190, Items Identified during 2015 NRC CDBI in Room 602 (Midget Hole) PIP M-15-03315, NRC CDBI question 164. Validate pipe breaks in curbed area of vital battery room area higher than 6" curbs. PIP M-15-03479, 2015 NRC CDBI Inspection- Questions on current PDO in PIP M-09-2341

PIP M-15-03517, 2015 CDBI Audit Team questions- Evaluate design deliverable documents associated with control of 1RN0001