IR 05000338/2015007

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IR 05000338/2015007, 05000339/2015007; on 07/20/2015 - 08/21/2015; North Anna Power Station, Units 1 and 2; Component Design Bases Inspection
ML15278A309
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 10/01/2015
From: Bartley J H
NRC/RGN-II/DRS/EB1
To: Heacock D A
Virginia Electric & Power Co (VEPCO)
References
IR 2015007
Download: ML15278A309 (26)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 October 1, 2015

Mr. David President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060

SUBJECT: NORTH ANNA POWER STATION - NRC COMPONENT DESIGN BASES INSPECTION REPORT 05000338/2015007 AND 05000339/2015007

Dear Mr. Heacock:

On August 21, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your North Anna Power Station and discussed the results of this inspection with Mr. G. Bischof and other members of your staff. Additional inspection results were discussed with Mr. G. Bischof and other members of your staff on September 30, 2015. Inspectors documented the results of this inspection in the enclosed inspection report.

NRC inspectors documented one finding of very low safety significance (Green) in this report. This finding involved a violation of NRC requirem ents. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC resident inspector

at the North Anna Power 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 Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Managem ent 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: Eric Stamm for/

Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos.: 05000338, 05000339 License Nos.: NPF-4, NPF-7

Enclosure:

Inspection Report 05000338/2015007 and 05000339/2015007 w/ Attachment: Supplementary Information cc: Distribution via Listserv

___ML15278A309_________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRP NRR NRR RII:DRP SIGNATURE G KO SXL5 VIA EMAILILMAR1 VIA EMAIL TGR1 VIA EMAIL CJB2 VIA EMAIL OSM VIA EMAIL SDR2 NAME GOTTENBERG SHERRICK MRILEY GSKAGGSRYA CBARON OMAZZONI SROSE DATE 9/30/2015 9/21/2015 9/22/2015 9/21/2015 9/21/2015 9/22/2015 9/30/2015 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICE RII:DRS SIGNATURE EJS2 FOR JHB1 NAME JBARTLEY DATE 10/1/2015 10/ /2015 10/ /2015 10/ /2015 10/ /2015 10/ /2015 10/ /2015 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosure U.S. NUCLEAR REGULATORY COMMISSION

REGION II

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Report Nos.: 05000338/2015007 and 05000339/2015007

Licensee: Virginia Electric and Power Company (VEPCO)

Facility: North Anna Power Station, Units 1 & 2

Location: Mineral, VA 23117

Dates: July 20, 2015 - August 21, 2015

Inspectors: G. Ottenberg, Senior Reactor Inspector (Lead) S. Herrick, Reactor Inspector M. Riley, Reactor Inspector G. Skaggs Ryan, Resident Inspector C. Baron, Contractor (Mechanical) O. Mazzoni, Contractor (Electrical)

Approved by: Jonathan H. Bartley, Chief Engineering Branch 1

Division of Reactor Safety

SUMMARY

IR 05000338/2015007, 05000339/2015007; 07/20/2015 - 08/21/2015; North Anna Power Station, Units 1 and 2; Component Design Bases Inspection.

This inspection was conducted by a team of three Nuclear Regulatory Commission (NRC)inspectors from Region II, one resident inspector, and two NRC contract personnel. One Green non-cited violation (NCV) was identified. The significance of inspection findings is indicated by their color (Green, White, Yellow, 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 operati on of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.

NRC-Identified and Self-Revealing Findings

Cornerstone: Mitigating Systems

Green.

The team identified a non-cited violation (NCV) of 10 Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion III, "Design Control," for the licensee's failure to control deviations from their piping design code of record for the auxiliary feedwater (AFW) system discharge lines. The licensee failed to consider the impact forces from a potential water hammer event as required by USA Standard (USAS) B31.1.0. The licensee entered this issue into their corrective action program as CR1003896. The licensee measured the discharge line temperatures of the AFW system to verify that current seat leakage past the check valves did not support steam void formation based on the recorded temperature and pressure in the discharge line such that water hammer was avoided. Additionally, the licensee implemented weekly temperature monitoring for continued operability of the AFW discharge lines in CA3003072.

This performance deficiency was more than minor because it was associated with the mitigating systems cornerstone attribute of design control 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, the licensee did not ensure the capability of the AFW piping because they did not consider that an undiscovered steam pocket in any of the AFW pumps discharge lines could lead to a water hammer in the line when AFW is initiated during an event. The team used IMC 0609, Att. 4, "Initial Characterization of Findings," issued June 19, 2012, for Mitigating Systems, and IMC 0609, 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 of a mitigating structure, system, or component (SSC), and the SSC maintained its operability or functionality (as shown through review of documentation related to prior identified leakage).

The team determined that no cross-cutting aspect was applicable because the finding was not indicative of current licensee performance. (Section 1R21.3)

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity

1R21 Component Design Bases Inspection

Main article: IP 71111.21

.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 components and operator actions that had a risk achievement worth factor greater than 1.3 or Birnbaum value greater than 1E-6. The sample included 15 components, three of which were associated with containment large early release frequency (LERF), and five 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) response times associated with operator actions. 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, Manual Chapter 0326 conditions, NRC resident inspector input r egarding 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

Components

  • Quench Spray Pumps [1-QS-P-1A and 1-QS-P-1B]
  • Casing Cooling Pumps [1-RS-P-3A and 1-RS-P-3B]
  • Air-Operated Valves and Manual Valves Needed to Re-align the Turbine Driven Auxiliary Feedwater (TDAFW) Pump to an Alternate Steam Generator [1-FW-PCV-159A(B), 1-HCV-100A(B)(C), 1-FW-155, 1-FW-64, 1-FW-96, 1-FW-149, 1-FW-62, 1-

FW-94, and 1-FW-126]

  • Motor-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-MOV-100A(B)(C)]
  • Emergency Diesel Generator Lubricating O il System [1-EG-P-4H, 1-EG-P-4J, 1-EG-CLR-600H, 1-EG-FL-600H, 1-EG-S-600H, and 1-EG-P-603H]
  • 4160 Volt to 480 Volt Transformers [1-EE-ST-1J, 1-EE-ST-1J1, 1-EE-ST-1H, and 1-EE-ST-1H1]
  • Vital Inverters [1-VB-INV-01 and 1-VB-INV-03]
  • Turbine Building Flooding Protective Circuitry [1-DB-LS-103, 1-DB-LS-104, 1-CW-LS-106A-1, 1-CW-LS-106A-2, and 1-CW-LS-106A-3]

Components with LERF Implications

  • Main Steam Non-return Valves [1-MS-NRV-101A(B)(C)]
  • Recirculation Spray Heat Exchanger Inlet, Outlet, and Return Valves [1-SW-MOV-103A(B)(C)(D), 1-SW-MOV-104A(B)(C)(D), and 1-SW-MOV-105A(B)(C)(D)]

For the 15 components listed above, the team reviewed the plant technical specifications (TS), UFSAR, design bases documents (DBDs), and drawings to establish an overall understanding of the design bases of the components. Applicable 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 DBDs 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 component-specific reviews:

  • The team observed a simulator scenario involving the recovery of the quench spray pumps to verify the actions could be accomplished by the operators upon recognition of their failure to start on a high containment pressure signal.
  • The team inspected spare valve cages for Air-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-PCV-159A, 1-FW-PCV-159B, 1-HCV-100A, 1-HCV-100B, 1-HCV-100C] and for Motor-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-MOV-100A, 1-FW-MOV-100B, and 1-FW-MOV-100C] in the station warehouse to verify that these valves would not be susceptible to clogging if the auxiliary feedwater system supply was aligned to the service water or fire protection systems.
  • The team reviewed and evaluated the capability of the emergency diesel generator batteries to provide power to equipment necessary to cope during a station blackout event.
  • The team reviewed Air-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-PCV-159A, 1-FW-PCV-159B, 1-HCV-100A, 1-HCV-100B, 1-HCV-100C] to verify the capacity of the associated air accumulators to ensure operation of the air-operated valves for at least 30 minutes.
  • The team reviewed Air-Operated Valves and Manual Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-PCV-159A, 1-FW-PCV-159B, 1-HCV-100A, 1-HCV-100B, 1-HCV-100C, 1-FW-155, 1-FW-64, 1-FW-96, 1-FW-149, 1-FW-62, 1-FW-94, and 1-FW-126] to verify the time available for the operators to realign these valves under accident conditions with postulated single failures.
  • The team reviewed Motor-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-MOV-100A, 1-FW-MOV-100B, and 1-FW-MOV-100C] to verify the Thermal Overload settings were appropriate to prevent tripping the valves under accident conditions.
  • The team reviewed Motor-Operated Valves Needed to Re-align the TDAFW Pump to an Alternate Steam Generator [1-FW-MOV-100A, 1-FW-MOV-100B, and 1-FW-MOV-100C] to verify the time available for the operators to realign these valves under accident conditions with postulated single failures.
  • The team reviewed Main Steam Trip Valves [1-MS-TV-101A, 1-MS-TV-101B, 1-MS-TV-101C] closing times to verify the resulting steam hammer transient would be acceptable.
  • The team reviewed Main Steam Trip Valves [1-MS-TV-101A, 1-MS-TV-101B, 1-MS-TV-101C] environmental conditions to verify the qualification of associated electrical equipment in the area.
  • The team observed a simulator exercise to verify the station's response to a steam generator tube rupture event with a single active failure of an AFW pump would not result in overfilling the ruptured steam generator and that the radiological releases would be terminated within 30 minutes.

b. Findings

No findings were identified. However, the following unresolved item (URI) was identified.

(Opened) Adequacy of Class 1E 120VAC Vital Bus Design

Introduction:

The team identified an unresolved item (URI) regarding the adequacy of design for the 120VAC Vital Buses.

Description:

Calculation

14258.79 - E-4, "Short Circuit Currents - 120V AC Vital Buses and Miscellaneous Circuits - Appendix R Evaluation," Rev.1, Addendum C, stated that

the maximum short circuit available to the 120VAC vital buses from the Units 1 and 2 20KVA inverters was 200% of rated full load current, equaling 334A, and 175% of full rated current, equaling 365A, when supp lied by the 25KVA voltage regulating transformer. These values were input into Technical Report EE-0118, "10 CFR Part 50 Appendix R Electrical Distribution System Coor dination Study," Rev. 2, to verify proper breaker coordination for the 120 VAC Vital instrumentation buses.

In 2003, the licensee received concurrence from the vital inverter vendor stating that while the steady state short circuit current limit was indeed approximately 200% of rated full load current for the inverter, the steady state short circuit current was approximately 200% of rated full load current for the regulating transformer, which was different than what was assumed in the technical report. The memo also stated that the 1/2 cycle instantaneous fault current for the inverter and regulating transformer would be approximately 500% of rated full load current, equaling 833A and 1042A for the inverter and transformer respectively. These values were not evaluated in the technical report.

The team noticed that when the 120VAC instrument buses were supplied by the regulating transformer, a condition allowed by TS, breaker coordination could not be verified for the 120VAC buses based on the instantaneous fault values concurred on by the vendor. Specifically, coordination could not be verified for the breakers associated

with the 1-I and 2-I 120VAC buses. TS 3.8.7 allows the regulating transformer to supply the vital buses for <=24 hours while the batteries are being equalized and TS 3.8.9 allows the licensee to consider the vital buses operable while they are energized from this transformer. The team was concerned that TS could allow the licensee to be on the regulating transformer when coordination could not be verified for the 120VAC buses.

The lack of breaker coordination could result in the loss of additional engineered safety features during a design bases event.

The licensee entered this issue into their corrective action program as CR1006865. This issue is a URI pending the determination of whether a violation of NRC requirements exists. (URI 05000338/2015007-01; 05000339/2015007-01, Adequacy of Class 1E 120VAC Vital Bus Design)

.3 Operating Experience

a. Inspection Scope

The team reviewed five operating experience issues for applicability at the North Anna Power 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:

  • NRC Generic Letter 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps"
  • NRC IN 94-24, "Inadequate Maintenance of Uninterruptible Power Supplies and Inverters"

b. Findings

Failure to Consider Potential Water Hammer Impact Loading on AFW piping

Introduction:

The team identified a non-cited violation (NCV) of 10 Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion III, "Design Control," for the licensee's failure to control deviations from their piping design code of record for the auxiliary feedwater (AFW) system discharge lines. The licensee failed to consider the impact forces from a potential water hammer event as required by USA Standard (USAS)

B31.1.0.

Description:

The Unit 1 and Unit 2 AFW system discharge piping check valves 1FW-68, -100, -132 and 2FW-70, -102, and -134, were designed to provide a boundary between the main feedwater (MFW) and the AFW systems. The piping downstream of these valves is normally exposed to high pressure and temperature MFW system operating conditions, while the upstream piping is normally exposed to lower pressure and temperature AFW system standby conditions. As a result, any significant leakage through these check valves could result in high temperature MFW fluid entering the lower pressure AFW system piping and flashing to steam. This condition could result in a steam void in the AFW system piping. Starting the AFW pump associated with the leaking check valve would rapidly pressurize the piping and could result in a severe water hammer event and damage to the AFW and/or MFW system piping and pipe supports. This piping was not analyzed for the resulting water hammer impact loading conditions. The team determined that the licensee had not implemented other measures to ensure the water hammer event would not occur, such as periodically monitoring AFW piping temperatures to detect significant check valve leakage.

The team noted that these check valves were classified as Category 'C' in the U1/U2 IST Program Plan for Interval 4, "Inservice Testing Program Plan for Pumps and Valves, Fourth Inspection Interval," dated December 15, 2010 to December 14, 2020. As Category 'C' valves, there was no defined acceptable seat leakage limit for the AFW line

check valves at the MFW boundary. Thus, some unknown amount of leakage is expected during normal operation. Additionally, several instances of actual seat leakage were identified on both Unit 1 and Unit 2 check valves. The following condition reports are historical examples of check valve leakage covering Units 1 and 2: CR378515, CR476664, CR538669, and CR568511.

The potential for this severe water hammer impact loading was discussed in NRC IN 84-06, "Steam Binding of Auxiliary Feedwater Pumps." The IN identified that significant leakage from the MFW system into the AFW system could result in the AFW pumps becoming inoperable due to steam binding and could also lead to the "potential for water hammer damage if an AFW pump discharges relatively cold water into a region of the piping system that contains steam." In 1984, the licensee evaluated the concerns of IN 84-06 and determined, in part, that "back leakage has never occurred at North Anna," and therefore did not implement routine monitoring to detect back leakage, as suggested in the IN. The licensee addressed potential steam binding of AFW pumps, but did not address the potential for water hammer in the AFW discharge piping.

The licensee committed to meeting USAS B31.7-1969, "Nuclear Power Piping," in North Anna's Updated Final Safety Analysis Report, section 3.2.2. The USAS B31.7 quality standard required, in Subsection 3, "Requirements for Class III Piping," Chapter 3-II, that the design of Class III piping shall be in accordance with the requirements of Chapter II of USAS B31.1.0. Chapter II of USAS B31.1.0, "Power Piping," section 101.5.1, "Impact," required that "impact forces caused by all internal and external conditions shall be considered in the piping design."

The licensee entered this issue into the corrective action program as CR1003896. The licensee measured the discharge line temperatures of the AFW system and confirmed that current seat leakage past the check valves did not support steam void formation based on the recorded temperature and pressure in the discharge line. Additionally, the licensee implemented weekly temperature monitoring for continued operability of the AFW discharge lines in CA3003072.

Analysis:

The team determined that failure to consider impact forces on the AFW system piping as required by USAS B31.1.0 was a performance deficiency and a failure to meet 10 CFR 50, Appendix B, Criterion III, "Design Control." This performance deficiency was more than minor because it was associated with the mitigating systems cornerstone attribute of design control 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, the licensee did not ensure the capability of the AFW piping because they did not consider that an undiscovered steam pocket in any of the AFW pumps discharge lines could lead to a water hammer in the line when AFW is initiated during an event. The team used IMC 0609, Att. 4, "Initial Characterization of Findings," issued June 19, 2012, for Mitigating Systems, and IMC 0609, 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 of a mitigating structure, system, or component (SSC), and the SSC maintained its operability or functionality (as shown through review of documentation related to prior identified leakage). The team determined that no cross-cutting aspect was applicable because the finding was not indicative of current licensee performance.

Enforcement:

The team identified a Green NCV of 10 CFR Part 50, Appendix B, Criterion III, "Design Control," which required, in part, that design control "measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled." Contrary to the above, since 1984, the licensee did not control a deviation from their quality standard for piping design. Specifically, the licensee was committed to meeting USAS B31.7-1969, "Nuclear Power Piping," for their piping design. Standard B31.7-1969 required the use of USAS B31.1.0, "Power Piping," for the design of class III piping, which included the AFW system piping, and USAS B31.1.0 required that impact forces caused by all external and internal conditions be considered in the piping design. The licensee did not consider impact forces for postulated credible water hammer events. In response to this issue, the licensee evaluated the temperature of the piping

where current check valve leakage was obser ved, and instituted periodic monitoring of the piping temperatures to eliminate the potential for water hammer. This violation is being treated as an NCV consistent with section 2.3.2 of the Enforcement Policy. The violation was entered into the licensee's corrective action program as CR 1003896. (NCV 05000338/2015007-02 and 05000339/2015007-02, "Failure to Consider Potential Water Hammer Impact Loading on AFW piping.")

4OA6 Meetings, Including Exit

On August 21, 2015, the team presented the inspection results to Mr. G. Bischof and other members of the licensee's staff. Additional inspection results were discussed with Mr. G. Bischof and other members of the licensee's staff on September 30, 2015. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

J. Leberstien, Technical Consultant, Licensing
D. Hinspater, Supervisor, Nuclear Projects
M. Nichols, Operations
J. McEnroe, Electrical Engineer
M. Phillips, Corporate Electrical Engineer
C. Bock, Substation Engineer
B. Clarke, Substation Engineer
M. Morris, Electrical I&C Systems Engineer
J. Chapman, Electrical I&C Systems Engineer
B. Morrison, Corporate Engineering Manager

NRC personnel

S. Rose, Chief, Projects Branch 5, Division of Reactor Projects
G. Kolcum, Senior Resident Inspector, Division of Reactor Projects, North Anna Resident Office
G. MacDonald, Senior Reactor Analyst, Division of Reactor Projects

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened

05000338 & 339/2015007-01

Opened and Closed

05000338 & 339/2015007-02

URI

NCV

Adequacy of Class 1E 120VAC Vital Bus

Design [Section 1R21.2]

Failure to Consider Potential Water Hammer

Impact Loading on AFW piping [Section

1R21.3]

LIST OF DOCUMENTS REVIEWED

Calculations

11715-24N, Quench Spray Pumps Specification Requirements, Rev. 0 11715-349N, Head Loss in Quench Spray - Train "A", Rev. 0
11715-350N, Head Loss in Quench Spray - Train "B", Rev. 0
11715-ES-007, Recirculation Spray System Design, Rev. 0
13075. 62-NPB-125-XF, Time History Analysis of Steamhammer due to Turbine Trip Closing for Main Steam Piping Contained in 11715-MSK-101A, Rev. 0 13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Rev. 1 13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum A, Rev. 1
13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum B, Rev. 1
13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum C, Rev. 1
13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum D, Rev. 1 13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum E, Rev. 1 13075.49-ES-194, Maximum Sump Water Level Final NPSH Modification, Addendum F, Rev. 1
13075.62-NPB-120-XF, Time History Analysis of Steamhammer due to Turbine Trip for Main Steam Piping Contained in 12050-MSK-101A, Rev. 0 13929.11-2, Ampacity Calculation - Emergency Buses - Sources, Rev. 1 13929.11-2, Ampacity Calculation - Emergency Buses - Sources, Rev. 1, Addendum A, Cable Ampacity Upon Removal of Three of Twelve Conductors from RSST A to Transfer Bus "D", Rev. 1
13929.11-2, Ampacity Calculation - Emergency Buses - Sources, Rev. 1, Addendum B, Cable Ampacity Upon Removal of Three of Twelve Conductors from RSST B to Transfer Bus "E", Rev. 1 Calc 59-01-PT-71.1Q, 1-FW-P-2, Turbine Driven AFW Pump, dated 2/5/14
CE-0911, Seismic Verification of Emergency Diesel Generator Aux and Fuel Oil Pump and Lube Oil Pump Control Panels, dated 2/21/92
CME-99-0067, Motor Operated AFW Pumps Discharge Piping Rerating North Anna Power Station - Units 1 & 2, Rev. 0 Coltec Engineering Report R-6.06-0260, Emerg ency Diesel Generator Cooling System Evaluation, dated 1/20/1995
EE-0008, North Anna Voltage Profiles, Addendum I, Rev. 2
EE-0027, Emergency Diesel Generator Load Sequencing, Rev. 3
EE-0092, North Anna Refueling Water Storage Tank Level Uncertainty, Rev. 4
EE-0343, Relay Settings for Safety Bus 1H, Rev. 0
EE-0373, 4.16kV Degraded Voltage & Loss of Voltage Relay Safety Limits, Rev. 2
EE-0394, EDG Fault Current and Voltage, Rev. 0
EE-0500, Motor Terminal Voltage for Motor-Operated Valves, Rev. 3
EE-0806, Coordination curves showing cable withstand, dated 8/4/2015
EWR 86-331, Engineering Work Request, Is It Necessary to Put Glycolin Diesels During Winter, dated 10/28/86 M-100, Time Required to Flood the Turbine Building After REJ Failure, Rev. 0
ME-0317, Addendum F, Revised MOV Test Limitations and Margin Calculations and Support DC
NA-11-01023 (OGR Change for 1-SW-MOV-105C), Rev. 0
ME-0317, Service Water Motor Operated Valve Operating Torque Requirements, Rev. 0
ME-0317, Service Water Motor Operated Valv

e Operating Torque Requirements, Addendum E, Rev. 0

ME-0435, Auxiliary Feedwater System Piping Design Pressure, Rev 5
ME-0487, Verification of Casing Cooling System Flow Rates Using Weakest Pump Total Developed Head (TDH) Curve for Units 1 & 2, Trains "A" & "B", Rev. 1
ME-0487, Verification of Casing Cooling System Flow Rates Using Weakest Pump Total Developed Head (TDH) Curve for Units 1 & 2, Trains "A" & "B", Addendum A, Rev. 1
ME-0579, AFW Minimum Flow, AFW Pump Operability, FW Check Valve Leakage, Rev. 4
ME-0584, AFW Pump Maximum Flow and NPSH Analysis, Rev. 0
ME-062, Service Water Reservoir Improv., Reservoir Performance Analysis, dated 5/1/87
NA-CALC-000-ME-3028, JOG Calculation of Required Thrust Settings for MOV 1-FW-MOV-100A, Rev. 1
NA-CALC-000-ME-3029, JOG Calculation of Required Thrust Settings for MOV 1-FW-MOV-100B, Rev. 1
NA-CALC-000-ME-3030, JOG Calculation of Required Thrust Settings for MOV 1-FW-MOV-100C, Rev. 1
NA-CALC-EEP-EE-0008, North Anna Voltage Profiles, Rev. 2
NA-CALC-EEP-EE-0025, North Anna Station Electrical Load List, Rev. 3
NA-CALC-EEP-EE-0037, Short Circuit Currents - 125VDC Control System, Rev. 0
NA-CALC-EEP-EE-0857 (ADD-000-00B), NAPS Station Battery 1-III Voltage Profile Calculation,
Rev. 0
NA-CALC-ELE-14258.79-E-4 (ADD-001-00C), Short Circuit Currents-120VAC Vital Buses and Miscellaneous Circuits-Appendix R Evaluation, Rev. 1
NA-CALC-NFL-SM-0914, Main Steamline Break Core Response for North Anna Power Station, Rev. 1
NA-CALC-ZZZ-01040.4910E, EDG DC System Sizing Verification (Battery, Charger, and
Cables), Rev. 1
NA-CALC-ZZZ-ME-0194, Adequacy of Backup Air Tanks, Rev. 0
NA-ENGT-000-ET-N-10-0025, Stem Connector for 1-FW-MOV-100A-D and 2-FW-MOV-200A-D, Rev. 0 Potential Problem Report No.90-014, North Anna Power Station Over Pressurization Potential of the Turbine Driven Auxiliary Feed Pumps, dated 5/23/90
SEO-371, Seismic Analysis of Lube Oil Gages and Tubing for Emergency Diesels, dated
9/10/85
SM-0549, Loss of Feedwater Sensitivity Study to Pressurizer Heaters and Sprays, Rev. 1
SM-1425, Instrument Uncertainty Allowance for RWST Level Based on Surveillance Practices, Rev. 0
SM-1510, Documentation and Benchmark of the GOTHIC Base Models for NAPS Containment Analysis, Rev. 0
SM-1511, Design Inputs for GOTHIC Containment Analysis for North Anna Power Station,
Rev. 1
SM-1511, Design Inputs for GOTHIC Containment Analysis for North Anna Power Station, Addendum A, Revision North Anna Containment Temperature Uncertainty, Rev. 1
SM-1511, Design Inputs for GOTHIC Containment Analysis for North Anna Power Station, Addendum B, Heat Sink Inventory Update for Removal of 260 Square-Feet of Metal Grating

from the NAPS Unit 1 Containment via Design Change

NA-13-00072, Rev. 1
SM-1511, Design Inputs for GOTHIC Containment Analysis for North Anna Power Station, Addendum C, Update to Correct
NSAL-11-5 LOCA Mass and Energy Release Errors and Other Issues, Rev. 1
SM-1512, North Anna LOCA Containment Peak Pressure and Depressurization Analyses with GOTHIC, Rev. 0
SM-1512, North Anna LOCA Containment Peak Pressure and Depressurization Analyses with GOTHIC, Addendum A, Longterm RS Flow Requirements, Rev. 0
SM-1512, North Anna LOCA Containment Peak Pressure and Depressurization Analyses with GOTHIC, Addendum B, Reduced RS Pump Flow Rates, Rev. 0
SM-1512, North Anna LOCA Containment Peak Pressure and Depressurization Analyses with GOTHIC, Addendum C,
NSAL-11-5 LOCA Mass and Energy Error Resolution and Casing Cooling Tank Volume Reduction, Rev. 0
SM-1513, North Anna GOTHIC Analysis of NPSH Available for the LHSI and RS Pumps, Rev. 1
SM-1513, North Anna GOTHIC Analysis of NPSH Available for the LHSI and RS Pumps, Addendum A, Rev. 1
SM-1513, North Anna GOTHIC Analysis of NPSH Available for the LHSI and RS Pumps, Addendum B, Rev. 1
SM-1513, North Anna GOTHIC Analysis of NPSH Available for the LHSI and RS Pumps, Addendum C, Correct
NSAL-11-5 LOCA Mass and Energy Release Errors and Other
Issues, Rev. 1
SM-1516, North Anna MSLB Containment Response with GOTHIC, Addendum A, Assessment of Unbounded Reactivity Parameter in Mass and Energy Release Data, Rev. 0
SM-1516, North Anna MSLB Containment Response with GOTHIC, Rev. 0
SM-1540, North Anna Minimum Indicated Containment Sump Level for Manual RS and LHSI Pump Start in Recirculation Mode, Rev. 0
Completed Procedures
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet for Comprehensive Pump Test, Attachment 1, dated 3/27/15
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 2/27/15
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 11/24/14 1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 8/29/14
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 6/9/14 1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 2/25/14
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 11/26/13
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 10/9/13 1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet for
Comprehensive Pump Test, Attachment 1, dated 5/28/13
1-PT-71.1Q.1, 1-FW-P-2, Turbine Driven AFW Pump, Full Flow Test Data Sheet, Attachment 1, dated 2/26/13

Condition Reports

(CRs)

200006
328984
380019
394634
395229
395233
402103
404855
430053
433912
440307
440307
444910
445383
453727
453729
453729
455557
461957
461957
461957
465747
465806
465806
465806
466136
466136
466209
466463
466481
467387
467435
484081
484081
494306
497328
497393
497947
501352
523685
25331
525532
528303
528404
532965
533387
558442
565845
568706
573799
574520
580894
Design Basis Documents
SDBD-NAPS-AFW, Auxiliary Feedwater System, Revision 15
SDBD-NAPS-CW, System Design Basis Document for Circulating Water System, Rev. 15
SDBD-NAPS-ED, 125 VDC Emergency Power System, Rev. 15
SDBD-NAPS-EG, Emergency Diesel Generator, Rev. 19
SDBD-NAPS-EP, Emergency Power System, Rev. 16
SDBD-NAPS-ESS, System Design Basis Document for Station Service Power System Rev 18
SDBD-NAPS-EV, Emergency Power and Vital Bus (120-240V) System, Rev. 15
SDBD-NAPS-MS, Main Steam and Ancillary Systems, Rev. 17
SDBD-NAPS-QS, System Design Basis Docum ent for Quench Spray System, North Anna Power Station, Rev. 17
SDBD-NAPS-RS, System Design Basis Document for Recirculation Spray System, North Anna Power Station, Rev. 19
SDBD-NAPS-SW, System Design Basis Docum ent for Service Water System, North Anna Power Station, Rev. 18

Drawings

11715-6.50-32, C. S. of Flanged Butterfly Valve 16" 20"
VVF-15A, Rev. B
11715-ES-026-0, Curve N436, Containment Quench Spray Pump, Mark No. 1-QS-P-1A, dated
4/7/1972 11715-ES-026-0, Curve N437, Containment Quench Spray Pump, Mark No. 1-QS-P-1B, dated
4/10/1972
11715-ESK-10AAV, Elementary Diagram, Annunciator Sheet 20 of 36, North Anna Power Station - Unit 1, Rev. 22 11715-ESK-11C, Sht. 2, Emergency Diesel Generator 1H, Rev. 19,
11715-ESK-11C, Sht. 3, Emergency Diesel Generator 1H, Rev. 23,
11715-ESK-11S, Elementary Diagram Circulating Water Flooding Trips North Anna Power Station - Unit 1, Rev. 6 11715-ESK-11T, Elementary Diagram Circulating Water Flooding Trips North Anna Power Station - Unit 1, Rev. 6 11715-ESK-3N, Control Switch Contact Diagrams Sheet 13, North Anna Power Station - Unit 1, Rev. 8 11715-ESK-5M, Elementary Diagram 4160V Ckts Circulating Water Pump 1-CW-P-1C
North Anna Power Station - Unit 1, Rev. 25 11715-ESK-6CL Elementary Diagram 480V Circuits Motor Operated Valves Sheet 11, 01-FW-MOV-100B, D & 154A, North Anna Power Station - Unit 1, Rev. 22 11715-ESK-6CY, Elementary Diagram 480V Circuits Motor Operated Valves 01-SW-MOV-102A & B, Sh 23, Rev. 1 11715-ESK-6PY-4, Elementary Diagram - 480V Circuits Solenoid Operated Valves - Sheet 45-4, North Anna Power Station - Unit 1, Rev. 4 11715-FE-1AE, 120V AC & 125V DC One Line Diag. Vital Power, Rev. 29
11715-FE-1BB, Electrical Distribution System, Rev. 50
11715-FE-1D, 4160V One Line Diagram-Sh.3, Emergency Bus 1H and 1J, North Anna Power Station - Unit 1, Sh. 1, Rev. 23 11715-FE-21AG, D.C. Elementary Diagram 4160V Bus 1H Bkr 15H2, 15H11, North Anna Power Station - Unit 1, Rev. 16 11715-FE-21E, 4160V AC Elementary Diagram, Emergency Buses 1H & 1J, Emergency Generators 1H and 1J, North Anna Power Station - Unit 1, Sh. 1, Rev. 23
11715-FE-21E, 4160V AC Elementary Diagram, Emergency Buses 1H & 1J, Emergency Generators 1H and 1J, North Anna Power Station - Unit 1, Sh. 2, Rev. 1 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 1, North Anna Power Station - Unit 1, Rev. 28 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 2, North Anna Power Station - Unit 1, Rev. 19 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 3, North Anna Power Station - Unit 1, Rev. 23 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 4, North Anna Power Station - Unit 1, Rev. 17 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 5, North Anna Power Station - Unit 1, Rev. 14 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 6, North Anna Power Station - Unit 1, Rev. 17 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 7, North Anna Power Station - Unit 1, Rev. 11 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 8, North Anna Power Station - Unit 1, Rev. 4 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 9, North Anna Power Station - Unit 1, Rev. 6 11715-FE-ESK-11C, Elementary Diagram, Emergency Diesel Generator 1H, Sh. 10, North Anna Power Station - Unit 1, Rev. 5 11715-FM-070A, Sheet 1, Main Steam System - Unit 1, Rev. 52
11715-FM-070A, Sheet 2, Main Steam System - Unit 1, Rev. 40
11715-FM-070A, Sheet 3, Main Steam System - Unit 1, Rev. 43 11715-FM-070A, Sheet 4, Main Steam System - Unit 1, Rev. 2 11715-FM-070B, Sheet 1, Main Steam System - Unit 1, Rev. 39
11715-FM-070B, Sheet 2, Main Steam System - Unit 1, Rev. 40
11715-FM-070B, Sheet 3, Main Steam System - Unit 1, Rev. 46
11715-FM-074A, Sheet 1, Feedwater System - Unit 1, Rev. 55 11715-FM-074A, Sheet 3, Feedwater System - Unit 1, Rev. 45 11715-FM-074A, Sheet 4, Feedwater System - Unit 1, Rev. 13
11715-FM-074A, Sht. 3, Flow/Valve Operating Numbers Diagram, Feedwater System, Rev. 45 11715-FM-078A, Flow/Valve Operating Numbers Diagram Service Water System North Anna Power Station Units 1 & 2 Virginia Power, Rev. 103
11715-FM-078B, Sht. 1, Flow/Valve Operating Numbers Diagram, Service Water, Rev. 35 11715-FM-091A, Flow/Valve Operating Numbers Diagram Cont Quench & Recirc Spray Sub Sys North Anna Power Station Unit 1 Virginia Power, Sh 1, Rev. 46 11715-FM-091A, Flow/Valve Operating Numbers Diagram Cont Quench & Recirc Spray Sub Sys North Anna Power Station Unit 1 Virginia Power, Sh 2, Rev. 35 11715-FM-091A, Flow/Valve Operating Numbers Diagram Cont Quench & Recirc Spray Sub Sys North Anna Power Station Unit 1 Virginia Power, Sh 3, Rev. 27 11715-FM-091A, Flow/Valve Operating Numbers Diagram Cont Quench & Recirc Spray Sub Sys North Anna Power Station Unit 1 Virginia Power, Sh 4, Rev. 35 11715-FM-091B, Flow/Valve Operating Numbers Diagram Cont Quench & Recirc Spray Sub Sys North Anna Power Station Unit 1 Virginia Power, Rev. 14 11715-FM-094A, Sht. 1, Flow/Valve Operating Numbers Diagram, Residual Heat Removal System, Rev. 17 11715-FM-107B, Sht. 1, Valve Operating Numbers Diagram, Emergency Diesel Lube Oil System, Rev. 7 11715-FP-14A, Reactor Containment Quench & Recirc. Spray Sub System, Rev. 13
11715-FP-14C, Reactor Containment Quench & Recirc Spray Sub System, Sh3, Rev. 11 11715-FV-65A, Refueling Water Chemical Addition Tank, Rev. 4
11715-FV-65A-4, Refueling Water Chemical Addition Tank 1&2-QS-TK-2, dated 11/15/1977 1175-6.82-2A, QS & RS Spray Nozzles - Full Cone 30° Injector Type, dated 7/16/1975
1175-6.82-3A, RS & QS Spray Nozzles - Hollow Cone, dated 7/16/1975
1175-FP-14C, Reactor Containment Quench & Recirc Spray Sub System, Sh. 3, Rev. 11
1175-FP-14D, Reactor Containment Quench & Recirc Spray Sub System, Sh. 4, Rev. 11
1-47W610-1-1, Sht. 1, Mechanical Control Diagram, Main Steam System, Rev. 14
23021C, Dimensional Assembly 16" 150FR, Rev. 0
59-B731-00003, Bingham Types:
HS, HSA, HSB, HSI, HSM Installation, Operation, Maintenance Instructions, Rev. 1 59-W893-00050, Installation and Maintenance Instructions for Life-Line T Motor, Frames 143T-449T, Rev. 2 Main One Line Diagram North Anna Power Station - Units 1 & 2, Rev. 51
One Line Diagram Electrical Distribution System North Anna Power Station Units 1 & 2, Rev. 50

Miscellaneous

01-FW-PCV-159A, AOV Program Diagnostic Trace Analysis, dated 9/11/13 01-FW-PCV-159B, AOV Program Diagnostic Trace Analysis, dated 9/11/13 01-FW-PCV-159B, AOV Program Diagnostic Trace Analysis, dated 9/16/13
2050-RUP-2, North Anna Power Station Unit 2 Pipe Rupture Report, Rev. 0
1860C, Limitorque H0BC Operator Overload Cycle Test Report, Rev. 0
1-FW-HCV-100A, AOV Program Diagnostic Trace Analysis, dated 6/24/15 1-FW-HCV-100B, AOV Program Diagnostic Trace Analysis, dated 6/24/15 1-FW-HCV-100C, AOV Program Diagnostic Trace Analysis, dated 9/16/13
1-SC-5.12, Refueling Water Storage Tanks 1-QS-TK-1, Rev. 2
59-A205-00004, Installation, Operation, Maintenance Large Frame Horizontal Induction Motors, Rev. 1 59-A209-00007, Streamseal Butterfly Valves 3 in. through 168 in., Rev. 9 59-F264-00002, Vendor Manual - Fisher Valves, Rev. 9 59-I096-00001, Quench Spray Pumps, Rev. 2
ACE019183 Effectiveness Review
AFW System Health Report, Q1-2015
AFW02, Maintenance Rule Screening, Aux Feedwater Function Chapter 9 Electrical Distribution System Coordination Study Results, Rev. 36
CME 98-0041, Water hammer Evaluation for Au xiliary Feedwater System, North Anna Power Station - Units 1 and 2, July 17, 1998 Coltec Industries, R-6.06-0260, Virginia Power, North Anna Power Station, Emergency Diesel Generator Cooling System Evaluation, January 20, 1995 Completion of Licensing Action for Generic Letter 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps"; North Anna Power Station, Unit Nos. 1 and 2 (TAC Nos. MA0015 and MA0016), dated 2/25/1999 DC
NA-12-00008, Instrument Air to Unit 2 Main Steam Trip Valves, dated 8/7/12 DC
NA-14-00061, Main Steam Trip Valve Stroke Time Improvement, dated 9/12/14
DNES-AA-ME/MOV-1001, Motor-Operated Valves, Rev. 7
DNES-AA-MOV-1001, Motor-Operated Valve Diagnostic Test Preparation and Evaluation, Rev.
DNES-VA-EEN-0011, Thermal Overload Relays and Heater Coil Selection
GL-89-10 MOVs Rev. 1
DOM-QA-1, Quality Assurance Program, Rev. 20
EE-0088, Investigation of the Addition of Ground Detection to the 4 KV System, dated 12-15-92
EE-0103, VEPCO Technical Report, Requirement

s for Protection of Emergency Diesel Generators for Testing Modes Running in Parallel to the Grid, April 15, 1994 Emergency Diesel Generator System Health Report, Quarter 1 2015 Emergency Power System Health Report, Quarter 1 2015

Engineering Data for 1H EDG Lube Oil Temperatures and Jacket Coolant Delta T, 2015
ER-AA-102, Recurring Task Evaluation, Emergency Diesel Generators, RTE number P-NANN-338290, dated 4/24/14
ER-AA-AOV-10, Air Operated Valve Program, Rev. 0
ER-AA-MOV-10, Motor-Operated Valve Program, Rev. 0
ER-AA-MOV-101, Motor-Operated Valve Program Process, Rev. 0
ET-CME-05-0034, Transmittal of Acceptance Criteria for Periodic Test Procedure 1-PT-64.4A, 1-PT-64.4B, 2-PT-64.4A, 2-PT-64.4B, Rev. 0
ET-CME-07-0011, Limitorque Technical Reference Information, Rev. 0
ET-CME-07-0049, New Test Limit Pump Curve Data for Casing Cooling Pumps, Rev. 1
ET-CME-98-0050, Available Margin in IRS, ORS, and LHSI Pump NPSH Calculations for Containment Screen Blockage, North Anna Power Station - Units 1 & 2, Rev. 0
ETE-CEE-2010-0001, Transmittal of Document Impacts and Program Updates due to the Revision of Calculation
EE-0720, Rev. 0
ETE-NA-2014-0030,
GL-96-05 Motor-Operated Valve Risk Ranking, Rev. 0
ETE-NA-2014-0035, Modification of Qualified Lives for Main Steam Trip and Bypass Limit Switches, Rev. 0
ETE-NA-2015-0030, Open Phase Project: EMTP model development, simulation results, and recommendations, Rev. 0
ET-N-06-0034, Evaluation of AQUASHADE to Control Algae Growth in the Service Water Reservoir, dated 11/9/2006
ET-N-06-0043, Evaluation of Emergency Diesel Generator Ambient Room Temperature, Rev. 1
ET-SE-98-0010, Discontinuing the Periodic Flush of SW System Pipelines that Supply the AFW Pumps Suction Pipelines, dated 3/23/09
EWR 84-307, Temporary Molybdate Addition System to SW Reservoir, dated 4/27/1988
EWR-93-009, Engineering Work Request, Turbine Driven AFW Pump Discharge Piping Rerate, dated 3/27/93 Fairbanks Morse & Co. Certified Test reports on Synchronous Generator, file
872057, dated
8/9/72 Fairbanks Morse & Co. Certified Test reports on Synchronous Generator, file
872060, dated
8/18/72 Fairbanks Morse & Co. Certified Test reports on Synchronous Generator, file
872066, dated
10/19/73 Fairbanks Morse & Co. Certified Test reports on Synchronous Generator, file
874001, dated11/12/73 Flood Scenario Development, Rev. 1
FP017, Maintenance Rule Screening, Fire Protection Log entries regarding high exhaust temperatures for the EDG from January 1, 2010 to June 17, 2015
MS System Health Report, Q1-2015
NAF 2001-0075, Maximum Service Water Flow from System Flow Rebalance Impact on IRS/ORS Pump NPSH Available, North Anna Power Station, Units 1 and 2, Rev. 1
NAF 99-0062, Service Water Flow and Temperature Sensitivity on IRS/ORS NPSH, North Anna Power Station, Units 1 and 2, Rev. 0
NAF-1997-0087, Evaluation of Shortfall in Flowrate for Outside Recirculation Spray Pump (Mark Number: 2-RS-P-2A), North Anna Power Station, Unit 2, Rev. 0
NAS-0044, Specification for Recirculation Spray Pumps for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 5/22/1972
NAS-0048, Specification for Flanged and Water Type Butterfly Valves 24 in and Smaller for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 8/25/1977
NAS-0148, Specification for Containment Quench Spray Pumps for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 11/6/1970
NAS-0155, Specification for Emergency Diesel Generator Sets, Rev. 3
NAS-0476, Specification for Casing Cooling Pumps for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 1/19/1979
NAS-155 Specification for Emergency-Diesel Generator Sets by Stone and Webster, Rev. 3
NAS-3012, Criteria Specification for Design and Identification of Electrical Cable, Rev. 14
NAS-64, Specification for Quench Spray Pump Discharge Strainers for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 6/8/1970
NAS-90-23, Specification for Instruments and Controls Temperature Elements for North Anna Power Station 1975 Extension - North Anna Power Station, Virginia Electric and Power Company, Richmond, Virginia, dated 8/4/1980
NA-VTM-000-59-I245-0005, Indoor & Outdoor Dry and Cast Transformers 111 1/2 through 10,000KVA, Rev. 4
NA-VTM-000-59-S984-00005, 20 KVA Inverter; 20 KVA Static Switch and 25 KVA Isolimiter, S/N C79674, Rev. 1 North Anna Power Station Unit Nos. 1 and 2 Response Letter to Generic Letter 88-03, "Steam Binding of Auxiliary Feedwater Pumps," dated 5/23/88 North Anna Power Station Unit Nos. 1 and 2 Response to I.E.Bulletin 85-01 "Steam Binding of Auxiliary Feedwater Pumps," dated 2/18/86 North Anna Power Station Units 1 & 2, Emergency Diesel Generator Systems & Component Vulnerability Evaluation North Anna Power Station, Units 1 and 2 - Issuance of Amendments RE: Quench Spray and Recirculation Spray Nozzles Surveillance Frequency (TAC NOS. MB4270 AND MB4271), dated 10/1/2002 North Anna Setpoint Document 2015 Second Quarter Update, Rev. 32
NOTEBK-PRA-NAPS-IF.2, North Anna Power Station Probabilistic Risk Assessment Model Notebook, Part III PRA Model Development, Category IF - Internal Flooding, Volume
IF.2 NRC Acceptance Letter of North Anna Power Station Unit Nos. 1 and
2 Response to Generic Letter 88-03, "Steam Binding of Auxiliary Feedwater Pumps," dated 7/6/88
NRC Inspection Report Nos. 50-338/27-27 and 50-339/87-26 Nuclear Control Room Operator Development Program, North Anna Power Station, Station Diesel Generator Systems, Revised 4/28/15 Nuclear Control Room Operator Development Program, North Anna Power Station, Feedwater System, Revised 4/28/15 Operating Stationary Batteries Vendor Manual, Rev. 9 Program/Comp Health Report,
CRS-GSI-191, Q2-2013 R-6.00-6033, Coltec Report, VEPCO Diesel Generator Loading Studies, dated 12/17/91
Request for Additional Information Related to Generic Letter 97-04 - Surry Power Station (SPS), Units 1 and 2; North Anna Power Station (NAPS), Units 1 and 2 (TAC Nos: MA0050,
MA0051, MA0015 and MA0016) Response to
IN 94-24 Inadequate Maintenance of Uninterruptible Power Supplies and Inverters, dated 7/6/94 RTE P-NANN-338290, Establish PMs to perform fuse and fuse holder replacements, dated
4/24/14 Safety Evaluation Report for Station Blackout Rule for North Anna Units 1 and 2, dated 10/18/90
Safety Evaluation Report for Station Blackout Rule for North Anna Units 1 and 2, dated 6/8/92 Safety Evaluation Report related to the operation of North Anna Power Station Units 1 and 2, Auxiliary Feedwater System, dated 6/76 Safety Evaluation Report related to the operation of North Anna Power Station Units 1 and 2, Service Water System, dated 6/76
Safety Evaluation Report, North Anna Power Station, Auxiliary Feedwater System, dated 6/76
Safety Evaluation Report, North Anna Power Station, Service Water System, dated 6/76
SAR 003048, Self-Assessment for Component Design Basis Inspection, 3/31/2015
Stone & Webster letter to Fairbanks Morse Incorporated, Add items to PO
NA-1220, dated
3/12/73 Stone & Webster letter to VEPCO, EDG Bid Analysis, dated 3/31/71
Summary of January 19, 1999, Meeting to Discuss Issues Related Generic Letter 97-04, dated
2/23/1999 System Health Report,
EG-Emer Diesel Gen, Q2-2015 System Health Report, Quench Spray, dated 7/10/2015 System Health Report, Recirc Spray, dated 7/10/2015 System Health Report,
RS-Recirc Spray, Q1-2015 System Health Report, Service Water, dated 7/8/2015 Technical Report
EE-0118, 10CFR50 Appendix 'R' Electrical Distribution System Coordination Study, Rev. 2 Technical Report
EE-0120, Review of 120VAC Vital Bus Voltages, Rev. 0 Technical Report No.
ME-0105, EDG Room High Temperature Operation Study, Rev. 0 TSCR N-007, Basis for 3.7.5 AFW System, dated 6/11/02 Virginia Electric and Power Company North Anna and Surry Power Stations Units 1 and 2 Generic Letter 97-04 - Assurance of Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps Response to a Request for Additional Information, dated 10/29/1998 Virginia Electric and Power Company North Anna and Surry Power Stations Units 1 and 2, Response to NRC Generic Letter 97-04 - Assurance of Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal, dated 12/29/1997

Procedures

0-ECM-1501-02, Disconnection and Reconnection of Motor-Operated Valves (1-SW-MOV-103A), Rev. 16, Performed 3/30/2006 0-ECM-1509-01, Quiklook MOV Testing (1-SW-MOV-103A), Rev. 15, Performed 9/22/2010 0-ECM-1509-01, Quiklook MOV Testing (1-SW-MOV-103B), Rev. 20, Performed 3/19/2012
0-ECM-1509-01, Quiklook MOV Testing (1-SW-MOV-103C), Rev. 20, Performed 3/14/2012
0-ECM-1510-01, Installation of Teledyne Quick Stem Sensor (1-SW-MOV-103C), Rev. 4, Performed 3/15/2012 0-EPM-0301-01, Testing of Single-Pole, Double-Pole, and Three-Pole Panel Type Molded-Case Circuit Breakers, Rev. 12 0-EPM-0307-01, Testing of Thermal Overloads, Rev. 35
0-EPM-1503-01, Inspection of Limitorque Motor-Operated Valves (1-SW-MOV-103B), Rev. 16, Performed 3/13/2012 0-EPM-1503-01, Inspection of Limitorque Motor-Operated Valves (1-SW-MOV-103C), Rev. 16, Performed 3/14/2012 0-EPM-2401-01, 4160/480 VAC Transformer Inspection, Rev. 9
0-GOP-17.0, Time Critical Action Validation and Verification, Rev. 10
0-GOP-82, General Operating Procedures, Routine Operations, Engineering, and Maintenance Department Weekly EDG Inspection, Rev. 0 0-MPM-0701-01, Mechanical Preventative Maintenance, 36-Month Preventive Maintenance of Emergency Diesel Generators, Rev. 78 0-MPM-0701-02, Mechanical Preventative Maintenance, 6-Year Preventative Maintenance of Emergency Diesel Generators, Rev. 20 0-OP-39.1, Turbine Building Flooding, Rev. 9 0-OP-59.1, Increasing / Re-Increasing Lake Level Gate Schedule, Rev. 42
0-PT-75.1, Service Water System-Valves (Monthly), Rev. 20, Performed 6/14/2015 1-AP-22.1, Loss of 1-FW-P-2 Turbine Driven AFW Pump, Rev. 16 1-AP-22.1, Loss of 1-FW-P-2 Turbine-Driven AFW Pump, Rev. 16 1-AP-22.5, Loss of Emergency Condensate Storage Tank 1-CN-TK-1, Rev. 9
1-AP-22.5, Loss of Emergency Condensate Storage Tank 1-CN-TK-1, Rev. 9 1-AP-31, Loss of Main Feedwater, Rev. 13 1-AR-20, Annunciator Response, Emergency Diesel 1H-Local, Rev. 23 1-AR-D-G7, 1-EI-CB-21D Annunciator G7, Turbine Building Flood Alarm Trouble, Rev. 1 1-AR-D-G7, 1-EI-CB-21D Annunciator G8, Cond Tube Clean Pit Hi-Hi Level, Rev. 1 1-DRP-02, Air Operated Valve Setpoints, Rev. 12
1-E-0, Reactor Trip or Safety Injection (with Eleven Attachments), Rev. 49 1-E-1, Loss of Reactor or Secondary Coolant, Rev. 27 1-LOG-4, U1 Control Board (Modes 1-4), Rev. 112, Performed 7/4/2015
1-LOG-6F, Unit 1 Safeguards, Operations-Daily, Rev. 110 1-MOP-6.90, Maintenance Operating, Emergency Diesel Generator 1-EE-EG-1H, Rev. 69 1-OP-1.4, Unit Startup from Mode 4 to Mode 3, Rev. 73 1-OP-31.2, Operating Procedure, Steam Generator Auxiliary Feedwater System, Rev. 36 1-OP-6.8A, Operating Procedure, Valve Checkoff-Emergency Generator Fuel Oil System, Rev.
1-OP-7.8, Refueling Water Chemical Addition Tank, Rev. 22 1-PT-212.14, Valve Inservice Inspection (Backup Air Supply for Aux. Feedwater Valves), Rev.
1-PT-212.9, Valve Inservice Inspection (Main Steam), Rev. 19
1-PT-213.11, Valve Inservice Inspection (Service Water), Rev. 22, Performed 5/19/2015
1-PT-214.18, Valve Inservice Inspection (Misc. Outside Containment Isolation Valve Position Indication), Rev. 13, Performed 3/25/2015
1-PT-36.32, Steam Line Isolation Operational Test, Rev. 9 1-PT-57.3, Containment Recirculation Spray Sump and LHSI Suction Header / Recirc Spray Suction Header Visual Examination, Rev. 27, Performed 3/22/2015 1-PT-57.4, Safety Injection Operational Test, Rev. 57
1-PT-58.4, Containment Recirc Spray System - Casing Cooling Tank Boron Concentration, Rev. 13, Performed 7/2/2015 1-PT-61.3, Containment Type C Test, Rev. 33, Performed 4/29/2012
1-PT-61.3, Containment Type C Test, Rev. 35, Performed 10/6/2013
1-PT-61.3, Containment Type C Test, Rev. 37, Performed 3/25/2015
1-PT-63.1A, Quench Spray System - "A" Subsystem, Rev. 36, Performed 7/8/2015
1-PT-63.1A.2, Quench Spray System - "A" Subsystem Comprehensive Pump Test, Rev. 5, Performed 4/10/2014 1-PT-63.1B, Quench Spray System - "B" Subsystem, Rev. 38, Performed 5/27/2015
1-PT-63.1B.2, Quench Spray System - "B" Subsystem Comprehensive Pump Test, Rev. 5, Performed 2/25/2014 1-PT-63.3, Quench Spray System - Spray Header Air Test, Rev. 5, Performed 3/27, 1993
1-PT-63.4, Quench Spray and Chemical Addition System Valve Lineup Verification, Rev. 8, Performed 6/4/2015 1-PT-64.1.1, Outside Recirculation Spray Pump 1-RS-P-2A, Rev. 28, Performed 3/21/2015 1-PT-64.1.2, Outside Recirculation Spray Pump 1-RS-P-2B, Rev. 28, Performed 3/21/2015
1-PT-64.3, Recirculation Spray System - Spray Header Air Test, Rev. 9, Performed 10/3/2004
1-PT-64.4A., Casing Cooling Pump (1-RS-P-3A) Test, Rev. 22, Performed 5/7/2015
1-PT-64.4A.2, Casing Cooling Pump (1-RS-P-3A) Biennial IST Comprehensive Pump Test, Rev. 3, Performed 11/8/2013 1-PT-64.4B., Casing Cooling Pump (1-RS-P-3B) Test, Rev. 22, Performed 6/15/2015
1-PT-64.4B.2, Casing Cooling Pump (1-RS-P-3B) Biennial IST Comprehensive Pump Test, Rev. 3, Performed 12/16/2013 1-PT-64.7, Outside Recirc Spray and Casing Cooling System Valve Lineup Verification, Rev. 6, Performed 5/23/2015 1-PT-64.8, Flow Test of the Inside Recirculation Spray Pumps, Rev. 29, Performed 3/22/2015
1-PT-66.3, Containment Depressurization Actuation Operational Test, Rev. 52, Performed
3/16/2015 1-PT-71.12, AFW System Valve Position Verification, Rev. 7
1-PT-71.1Q, Operations Periodic Test, 1-FW-P

-2, Turbine Driven Auxiliary Feedwater Pump and Valve Test, Rev. 62 1-PT-71.4, AFW Pump Test Response and Logic Test Including SW Pump and SBO Diesel Auto Start Tests on U1 Loss of Reserve Power, Rev. 39 1-PT-71.5, Auxiliary Feedwater Line Flush, Rev. 13 1-PT-82H, Operations Periodic Test, 1H Emergenc

y Diesel Generator Slow Start Test, Rev. 55 2-AP-22.5, Loss of Emergency Condensate Storage Tank 2-CN-TK-1 (With Three Attachments), Rev. 11 2-EPM-080d1-01, Testing the Flood Control System, Rev. 7

CHAP-0105, Auxiliary Cooling Water System Chemistry Control Program (North Anna), Rev. 24
CM-AA-CLC-301, Engineering Calculations, Rev. 9
CM-AA-CLC-301-1001, Guidance and Reference Documents, Engineering Calculations, Rev. 7
Crackle Test Procedure
DNES-AA-ME/MOV-1001, Motor-Operated Valves, Rev. 7
DNES-AA-MOV-1001, Motor-Operated Valve Diagnostic Test Preparation and Evaluation, Rev.
DNES-NA-EE/MOV-1001, Over-Current and Voltage Phase Imbalance Analysis for MOVs, Rev.
ER-AA-AOV-100, Air Operated Valve Program Categorization, Rev. 1
ER-AA-AOV-101, Design Basis Review, Rev. 1
ER-AA-AOV-102, AOV Testing and Control of Setup Parameters, Rev. 2
ETE-NA-2014-0040, Preventive Maintenance Optimization Strategy of the North Anna Emergency Diesel Generators, Rev. 0. Dated 9/10/14.
Fairbanks Morse Technical Manual
NA-VTM-000-59-F173-00002, Rev. B
NA-PROCNA-ADM-AD-AA-102, Procedure Use and Adherence, Rev. 10 O-EPM-2004-01, Testing Level Switches, Rev. 17
OP-AA-102, Operability Determination, Rev. 12
PI-AA-200, Corrective Action, Rev. 24
PI-AA-300, Cause Evaluation, Rev. 7
PI-AA-300-3001, Root Cause Evaluation, Rev. 5
PI-AA-300-3002, Apparent Cause Evaluation, Rev. 9
Visgage Procedure, Pocket Viscosity Comparator, Model 38 & 76 Operating Instructions
VPAP-0812, Station Lubrication Program, Rev. 16
VPAP-1802, Quality Assurance Program Elements for Supply Chain Management, Rev. 12

Work Orders

00603587 01, MPM/3REF/01-SW-MOV, dated 3/30/2006
59101610358, Perform MOV PM, dated 3/13/2012
59101610367, Perform MOV PM, dated 3/13/2012
59101616878, 4160/480 VAC 1J Transformer Inspection, dated 4/12/12 59101616888, 4160/480 VAC 1J1 Transformer Inspection, dated 4/12/12
59101625122, MPM/6REF/01-SW-MOV, dated 3/15/2012
59101625541, Perform As-Found MOV Test, dated 9/22/2010
59101625553, Perform As-Found MOV Test, dated 3/19/2012
59101625565, Perform As-Found MOV Test, dated 3/14/2012
59101673419, 01-EE-EG-1H-Engine, MPM/6 YR/01-EE-EG-1H, dated 10/12/09 59101696703, Emergency Diesel Generator 1H Battery Capacity Test, dated 4/19/12 59101873191, Spare Operator Rebuild (1-MS-NRV-101A), dated 3/21/15
59101907990, 4160/480 VAC 1H1 Transformer Inspection, dated 9/17/13
59101908053, 4160/480 VAC 1H Transformer Inspection, dated 9/17/13 59101928799, Replace RTD, dated 7/1/2010 59101948992, IPM Replace RTD, dated 12/29/2009 59102138626, Replace Anti-Rotation Pin, dated 3/14/12 59102142035, 01-EG-CLR-600H-HTEXCH, Perform Eddy Current Testing Lube Oil Cooler, dated 3/14/13 59102142047, 1-EG-CLR-6000J-HTXECH, Perform Eddy Current Testing Lube Oil Cooler, dated 2/25/14 59102216687, 01-FW-P-2-Pump, Perform Annual Maintenance, dated 10/9/13 59102231681, 01-DB-LS-03IBISSW PM O-EPM-2004-01 /TUR/BLDILEV/PROB/TEST, dated
2/23/13 59102288849, 01-EE-EG-1H-Engine, Perform 2 Year Inspection of Lube Oil System, dated
3/7/13 59102299662, Replace Anti-Rotation Pin, dated 3/14/12 59102299663, Replace Anti-Rotation Pin, dated 3/14/12 59102299664, Replace Anti-Rotation Pin, dated 3/15/12 59102310625, Packing Adjust, dated 6/28/11
59102349886, Repack Valve, dated 10/3/11
59102413979, Noise from 1-MS-TV-101A, dated 4/23/12
59102443768, AFW Pressure Control Valve Positioner, dated 9/16/13 59102444682, Repair of Minor Fitting Leak, dated 9/16/13 59102444683, 1-FW-HCV-100A Air Leaks, dated 3/27/12
59102444690, Repair of Minor Positioner Air Leaks, dated 3/19/13
59102465721, Weld Repair, dated 4/16/12
59102564631, 01-EG-CLR-600H-HTEXCH, Tube Plugging 1-EG-CLR-600H (Contingency WO)
59102627941, SMB000 Grease Change, dated 9/30/13 59102635393, Intercell Connection Resistance Test for Battery 1J, dated 3/14/15
59102639895, Intercell Connection Resistance Test for Battery 1H, dated 3/23/15 59102649465, Emergency Diesel Generator Battery Charger 1H Service Test, dated 3/17/15 59102654683, Emergency Diesel Generator 1H Battery Capacity Test, dated 3/19/15 59102657389, Emergency Diesel Generator Battery Charger 1J Service Test, dated 3/13/15
59102665554, Torque Switch Replacement, dated 10/7/13
59102667447, Packing Adjust, dated 10/17/13
59102667968, 1-MS-NRV-101A Both Light Indication, dated 10/13/13
59102668148, Field cable for 1-MS-NRV-101A, dated 10/13/13
59102668211, Degraded Cable Jacket, dated 10/13/13 59102668435, Packing Adjust, dated 10/13/13 59102668466, 1-MS-NRV-101A Torque on Open Backseat, dated 10/13/13
59102668596, Stem/Bonnet Pressure Ring Replacement (Backseat Repair), dated 3/20/15
59102669831, Packing Adjust, dated 10/25/13
59102741991, Repair Limit Switch, dated 3/23/15 59102754419, Instrument Gauge Replacement, dated 3/22/15 59102812045, Electrical Periodic Test of DC Distribution System, dated 6/24/15
59102812529, Quarterly DC Distribution System Test for Battery 1H, dated 6/2/15
59102813855, Quarterly DC Distribution System Test for Battery 1J, dated 6/15/15
59102813865, AC Distribution and Reactor Coolant Pump Operability Verification, dated 7/1/15
59102848761, Repack Valve, dated 3/25/15 59102850988, Packing Adjust, dated 3/28/15
Corrective Action Documents Written Due to this Inspection
CR1003398, Discrepancy identified for 1-PT-88H
CR1003896, Routine method needed for monitoring AFW piping temperatures for water hammer
CR1005454, EDG Battery Charger Testing and Calculations Not Including Instrument Error
CR1005481, Enhancements to update DBD references to include SBO Documentation
CR1005622, Review of UFSAR to determine RG 1.155 reference
CR1006865, Review of Appendix R Current Fault Coordination
CR1006913, NAPS 2015 CDBI- EDG Nameplate Discr epancy Identified during CDBI Inspection
CR1006935, Service Water Usage Calculation Requires Revision
PIR1005191, Evaluate addition of cable withstand capability to 4160V switchgear coordination curves
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