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=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 December 14, 2011  
{{#Wiki_filter:UNITED STATES ber 14, 2011


Mr. Michael Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
==SUBJECT:==
 
WATTS BAR NUCLEAR PLANT UNIT 2 CONSTRUCTION - NRC INSPECTION REPORT 05000391/2011612
SUBJECT: WATTS BAR NUCLEAR PLANT UNIT 2 CONSTRUCTION - NRC INSPECTION REPORT 05000391/2011612


==Dear Mr. Skaggs:==
==Dear Mr. Skaggs:==
On November 18, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a team inspection of construction activities at your Watts Bar Unit 2 reactor facility. The enclosed inspection report documents the inspection results, which were discussed on November 18, 2011, with Mr. David Stinson and other members of your staff.
On November 18, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a team inspection of construction activities at your Watts Bar Unit 2 reactor facility. The enclosed inspection report documents the inspection results, which were discussed on November 18, 2011, with Mr. David Stinson and other members of your staff.


The NRC team performed an Electrical Distribution System Functional Inspection (EDSFI) using selected portions of NRC Temporary Instruction (TI) 2515/107. This inspection examined activities conducted under your Unit 2 construction permit as they relate to safety and compliance with the Commission's rules and regulations, with the conditions of your construction permit, and with fulfillment of Unit 2 regulatory framework commitments. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The NRC team performed an Electrical Distribution System Functional Inspection (EDSFI) using selected portions of NRC Temporary Instruction (TI) 2515/107. This inspection examined activities conducted under your Unit 2 construction permit as they relate to safety and compliance with the Commissions rules and regulations, with the conditions of your construction permit, and with fulfillment of Unit 2 regulatory framework commitments. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.


Based on the results of this inspection, no findings or violations of significance were identified.
Based on the results of this inspection, no findings or violations of significance were identified.


TVA 2 In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
TVA   2 In accordance with 10 CFR 2.390 of the NRCs 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 NRCs document 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,
Sincerely,
/RA/ Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection Docket No. 50-391 Construction Permit No: CPPR-92  
/RA/
Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection Docket No. 50-391 Construction Permit No: CPPR-92


===Enclosure:===
===Enclosure:===
Inspection Report 05000391/2011612 w/attachment  
Inspection Report 05000391/2011612 w/attachment


REGION II==
REGION II==
Docket No.: 50-391  
Docket No.: 50-391 Construction Permit No.: CPPR-92 Report No.:  05000391/2011612 Applicant:  Tennessee Valley Authority (TVA)
Facility:  Watts Bar Nuclear Plant, Unit 2 Location:  1260 Nuclear Plant Rd Spring City TN 37381 Dates:  October 24 - November 18, 2011 Inspectors:  Caudle Julian, Team Leader, Construction Inspection Branch 1 (CIB 1), Division of Construction Inspection (DCI)
Region II (RII)
G. Crespo, Senior Construction Inspector, CIB1, DCI, RII R. Mathis, Construction Inspector, CIB1, DCI, RII C. Even, Project Inspector, Construction Projects Branch 3 (CPB 3), Division of Construction Projects (DCP), RII G. Morris, Consultant Approved by: Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection Enclosure


Construction Permit No.: CPPR-92 Report No.: 05000391/2011612
=EXECUTIVE SUMMARY=
 
Watts Bar Nuclear Plant, Unit 2
Applicant: Tennessee Valley Authority (TVA)
Facility: Watts Bar Nuclear Plant, Unit 2 Location: 1260 Nuclear Plant Rd Spring City TN 37381 Dates: October 24 - November 18, 2011
 
Inspectors:
Caudle Julian, Team Leader, Construction Inspection Branch 1 (CIB 1), Division of Construction Inspection (DCI) Region II (RII) G. Crespo, Senior Construction Inspector, CIB1, DCI, RII R. Mathis, Construction Inspector, CIB1, DCI, RII C. Even, Project Inspector, Construction Projects Branch 3 (CPB 3), Division of Construction Projects (DCP), RII G. Morris, Consultant


Approved by: Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection
This inspection included aspects of engineering activities performed by TVA associated with the Watts Bar Nuclear (WBN) Plant Unit 2 construction project. This report covered a two week period of inspection in the area of Electrical Distribution System Functional Inspection (EDSFI)as specified in NRC Temporary Instruction (TI) 2515/107. The inspection program for Unit 2 construction activities is described in NRC Inspection Manual Chapter (IMC) 2517. Information regarding the WBN Unit 2 Construction Project and NRC inspections can be found at http://www.nrc.gov/reactors/plant-specific-items/watts-bar.html.
 
=EXECUTIVE SUMMARY=
Watts Bar Nuclear Plant, Unit 2  


This inspection included aspects of engineering activities performed by TVA associated with the Watts Bar Nuclear (WBN) Plant Unit 2 construction project. This report covered a two week period of inspection in the area of Electrical Distribution System Functional Inspection (EDSFI) as specified in NRC Temporary Instruction (TI) 2515/107. The inspection program for Unit 2 construction activities is described in NRC Inspection Manual Chapter (IMC) 2517. Information regarding the WBN Unit 2 Construction Project and NRC inspections can be found at http://www.nrc.gov/reactors/plant-specific-items/watts-bar.html. Inspection Results The inspectors assessed the capability of the Electrical Distribution System (EDS) to perform its intended safety function during plant operating and accident conditions. The inspectors reviewed electrical calculations and analyses associated with cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and emergency diesel generator loading. The inspectors interviewed responsible engineering staff to confirm understanding of records. The inspectors determined that in general the calculations were complete, understandable, and technically adequate.
Inspection Results The inspectors assessed the capability of the Electrical Distribution System (EDS) to perform its intended safety function during plant operating and accident conditions. The inspectors reviewed electrical calculations and analyses associated with cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and emergency diesel generator loading. The inspectors interviewed responsible engineering staff to confirm understanding of records. The inspectors determined that in general the calculations were complete, understandable, and technically adequate.


No violations of regulatory requirements were identified.
No violations of regulatory requirements were identified.
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=REPORT DETAILS=
=REPORT DETAILS=


II. Management Oversight and Control E.1 Engineering Activities E.1.1 (Closed) EDSFI Temporary Instruction (TI) 2515/107
II.
 
Management Oversight and Control E.1   Engineering Activities E.1.1 (Closed) EDSFI Temporary Instruction (TI) 2515/107


====a. Inspection Scope====
====a. Inspection Scope====
Background: In 1979, the NRC published Generic Letter (GL) 79-36 to ask licensees to examine undervoltage protection of safety related electric equipment for potential damage as a result of sustained degraded voltage from the offsite electric grid system. This generic letter was issued in response to events at a number of operating nuclear plants that brought into question the conformance of the station electric distribution system to 10 CFR 50, Appendix A - General Design Criteria - 17, Electric Power Systems. TI 2515/107 - EDSFI was issued on October 19, 1990 to provide a comprehensive NRC team inspection focused primarily on the EDS at operating nuclear plants to address the concerns raised by the Safety System Functional Inspections performed between 1986-1990 and Generic Letter 79-36. This inspection performed a portion of TI 2515/107 at Watts Bar 2.
Background: In 1979, the NRC published Generic Letter (GL) 79-36 to ask licensees to examine undervoltage protection of safety related electric equipment for potential damage as a result of sustained degraded voltage from the offsite electric grid system.
 
This generic letter was issued in response to events at a number of operating nuclear plants that brought into question the conformance of the station electric distribution system to 10 CFR 50, Appendix A - General Design Criteria - 17, Electric Power Systems. TI 2515/107 - EDSFI was issued on October 19, 1990 to provide a comprehensive NRC team inspection focused primarily on the EDS at operating nuclear plants to address the concerns raised by the Safety System Functional Inspections performed between 1986-1990 and Generic Letter 79-36. This inspection performed a portion of TI 2515/107 at Watts Bar 2.


Using the guidance of TI 2515/107, the inspectors examined the electrical distribution system with focus on the path supplying Shutdown Board 2B-B. The inspectors reviewed available design basis information and conducted plant walk-downs as necessary to assess the capacity of the electrical distribution system to perform its safety functions.
Using the guidance of TI 2515/107, the inspectors examined the electrical distribution system with focus on the path supplying Shutdown Board 2B-B. The inspectors reviewed available design basis information and conducted plant walk-downs as necessary to assess the capacity of the electrical distribution system to perform its safety functions.


The inspectors assessed the capability of the EDS to perform its intended safety function during plant operating and accident conditions and reviewed design basis calculations for the EDS to evaluate whether they were coherent, accurate, and complete for supporting dual unit operation. The inspectors reviewed the calculations documenting the loading on various electrical sources such as emergency diesel generators, batteries, and shutdown boards. Specifically the inspectors performed detailed review of 11 electrical calculations focusing on cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and diesel generator loading. The complete list of electrical calculations reviewed is included in the supplemental information at the end of this report. The inspectors also reviewed Final Safety Analysis Report (FSAR) descriptions, design specifications, drawings, system descriptions, and other design documents to support the assessment of the EDS design. The inspectors reviewed selected referenced supporting calculations to confirm selected design inputs and assumptions. The inspectors interviewed responsible personnel, performed field walk-downs, and observed software analysis. The supplemental information attachment also includes a list of the documents reviewed in support of the inspection.
The inspectors assessed the capability of the EDS to perform its intended safety function during plant operating and accident conditions and reviewed design basis calculations for the EDS to evaluate whether they were coherent, accurate, and complete for supporting dual unit operation. The inspectors reviewed the calculations documenting the loading on various electrical sources such as emergency diesel generators, batteries, and shutdown boards. Specifically the inspectors performed detailed review of 11 electrical calculations focusing on cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and diesel generator loading. The complete list of electrical calculations reviewed is included in the supplemental information at the end of this report. The inspectors also reviewed Final Safety Analysis Report (FSAR) descriptions, design specifications, drawings, system descriptions, and other design documents to support the assessment of the EDS design.
 
The inspectors reviewed selected referenced supporting calculations to confirm selected design inputs and assumptions. The inspectors interviewed responsible personnel, performed field walk-downs, and observed software analysis. The supplemental information attachment also includes a list of the documents reviewed in support of the inspection.


The inspection team reviewed the design inputs used in TVA's Electrical Transient Analyzer Program (ETAP) from the emergency diesel generators (EDGs) loading calculation to verify that the ETAP program matched the assumptions and conclusions of the calculation in dealing with the time zero loads in the EDG loading sequence. The inspection team's review of the EDG design calculation focused on the loads that are started at time zero in the loading sequence to verify that all design loads were appropriately captured and analyzed in ETAP. The inspectors took a sample of the time zero components and performed walk-downs of those components to gather nameplate data to verify that the components modeled in ETAP were the same as the components in the plant.
The inspection team reviewed the design inputs used in TVAs Electrical Transient Analyzer Program (ETAP) from the emergency diesel generators (EDGs) loading calculation to verify that the ETAP program matched the assumptions and conclusions of the calculation in dealing with the time zero loads in the EDG loading sequence. The inspection teams review of the EDG design calculation focused on the loads that are started at time zero in the loading sequence to verify that all design loads were appropriately captured and analyzed in ETAP. The inspectors took a sample of the time zero components and performed walk-downs of those components to gather nameplate data to verify that the components modeled in ETAP were the same as the components in the plant.


The inspectors interviewed responsible engineering staff to address questions generated from the review of the engineering documentation. The inspectors also reviewed surveillance and test procedures for the 125V DC vital power system and the 125V DC diesel generator system.
The inspectors interviewed responsible engineering staff to address questions generated from the review of the engineering documentation. The inspectors also reviewed surveillance and test procedures for the 125V DC vital power system and the 125V DC diesel generator system.
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No findings of significance were identified.
No findings of significance were identified.


During the review of the DC vital power system, the inspectors found that Battery IV was degraded and there was evidence of problems from the results of the February 2011 performance test that had not been entered into the corrective action program. This issue was followed up by the Unit 1 NRC Senior Resident Inspector for operability concerns and will be appropriately documented in a subsequent inspection report for Unit 1. The team determined that Degraded Voltage Relay settings and the associated degraded voltage analysis calculation is the subject of Open Item 30 in Appendix HH of NUREG-0847, Supplement 22. This issue will be resolved by the Office of Nuclear Reactor Regulation and was not inspected.
During the review of the DC vital power system, the inspectors found that Battery IV was degraded and there was evidence of problems from the results of the February 2011 performance test that had not been entered into the corrective action program. This issue was followed up by the Unit 1 NRC Senior Resident Inspector for operability concerns and will be appropriately documented in a subsequent inspection report for Unit 1.
 
The team determined that Degraded Voltage Relay settings and the associated degraded voltage analysis calculation is the subject of Open Item 30 in Appendix HH of NUREG-0847, Supplement 22. This issue will be resolved by the Office of Nuclear Reactor Regulation and was not inspected.


====c. Conclusions====
====c. Conclusions====
The inspectors determined that in general the calculations reviewed were complete, understandable, and technically adequate.
The inspectors determined that in general the calculations reviewed were complete,         understandable, and technically adequate.


IV.
IV.


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
OA.1.1 (Discussed) Construction Deficiency Report (CDR) WBRD-50-391/86-13, entitled Lack of Adequate Calculations to Document Electrical System Design Basis
OA.1.1 (Discussed) Construction Deficiency Report (CDR) WBRD-50-391/86-13, entitled           Lack of Adequate Calculations to Document Electrical System Design Basis


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors followed up on TVA resolution of Construction Deficiency Report (CDR)
The inspectors followed up on TVA resolution of Construction Deficiency Report (CDR)
WBRD-50-391/86-13, entitled Lack of Adequate Calculations to Document Electrical System Design Basis and an associated Action Item 7 in Appendix HH of SSER 22. TVA initiated PER 144072 on February 3, 1989 associated with this issue. The inspectors examined the existing inventory of issued Unit 2 electrical design calculations and compared it to TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15, Appendix E, Electrical/I&C Engineering Calculation Classifications. The purpose was to confirm that all TVA specified essential electrical and I&C calculations have been prepared and issued.
WBRD-50-391/86-13, entitled Lack of Adequate Calculations to Document Electrical System Design Basis and an associated Action Item 7 in Appendix HH of SSER 22.
 
TVA initiated PER 144072 on February 3, 1989 associated with this issue. The inspectors examined the existing inventory of issued Unit 2 electrical design calculations and compared it to TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15, Appendix E, Electrical/I&C Engineering Calculation Classifications. The purpose was to confirm that all TVA specified essential electrical and I&C calculations have been prepared and issued.


====b. Observations and Findings====
====b. Observations and Findings====
TVA's method of resolving the CDR was to establish a list which identifies a minimum set of Electrical and Instrumentation and Control (I&C) calculations necessary to fully document the design basis of a TVA nuclear plant. The list was first issued as a memo for electrical branch direction on July 17, 1987, and contained essential and desirable calculations. The content of that list was subsequently issued as Appendix E, Electrical/I&C Engineering Calculation Classifications of TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15. TVA calculations are now organized and controlled by the Calculation Cross Reference Information System (CCRIS) computer system. The inspectors examined an index of calculations from CCRIS and found that most of the topics listed in Appendix E had corresponding calculations issued. However the inspectors could not find calculations listed for all of the topics under the headings of Raceway System Calculations or Instrumentation and Control System Calculations. TVA representatives stated that they needed to do more work on this item before it is ready for NRC review and closure and they initiated PER 458200 to track corrective action on this item. No findings of significance were identified.
TVAs method of resolving the CDR was to establish a list which identifies a minimum set of Electrical and Instrumentation and Control (I&C) calculations necessary to fully document the design basis of a TVA nuclear plant. The list was first issued as a memo for electrical branch direction on July 17, 1987, and contained essential and desirable calculations. The content of that list was subsequently issued as Appendix E, Electrical/I&C Engineering Calculation Classifications of TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15. TVA calculations are now organized and controlled by the Calculation Cross Reference Information System (CCRIS) computer system. The inspectors examined an index of calculations from CCRIS and found that most of the topics listed in Appendix E had corresponding calculations issued. However the inspectors could not find calculations listed for all of the topics under the headings of Raceway System Calculations or Instrumentation and Control System Calculations. TVA representatives stated that they needed to do more work on this item before it is ready for NRC review and closure and they initiated PER 458200 to track corrective action on this item. No findings of significance were identified.


c. Conclusion TVA representatives concluded that this item requires more work before it is ready for NRC review and closure and they initiated PER 458200 to track corrective actions.
c. Conclusion TVA representatives concluded that this item requires more work before it is ready for NRC review and closure and they initiated PER 458200 to track corrective actions.
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====a. Inspection Scope====
====a. Inspection Scope====
This unresolved item contained nine examples of electrical issues requiring further inspection to determine if a violation existed. The ninth example concerned a lack of information in calculation EDQ00099920080014, Rev. 8, Diesel Generator Loading  
This unresolved item contained nine examples of electrical issues requiring further inspection to determine if a violation existed. The ninth example concerned a lack of information in calculation EDQ00099920080014, Rev. 8, Diesel Generator Loading


=====Analysis.=====
=====Analysis.=====
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Partial List of Persons Contacted
Partial List of Persons Contacted
Applicant personnel
Applicant personnel
: [[contact::A. Bangalore]], Electrical Design Manager, Bechtel  
: [[contact::A. Bangalore]], Electrical Design Manager, Bechtel
: [[contact::D. Beckley]], Electrical Design Engineer, TVA Unit 2  
: [[contact::D. Beckley]], Electrical Design Engineer, TVA Unit 2
: [[contact::D. Charlton]], Licensing, TVA  
: [[contact::D. Charlton]], Licensing, TVA
: [[contact::W. Elliott]], TVA Oversight  
: [[contact::W. Elliott]], TVA Oversight
: [[contact::S. Hilmes]], Unit 2 Lead Electrical Engineer, TVA  
: [[contact::S. Hilmes]], Unit 2 Lead Electrical Engineer, TVA
: [[contact::I. Khan]], Electrical Engineer, Washington Group  
: [[contact::I. Khan]], Electrical Engineer, Washington Group
: [[contact::G. Scott]], Licensing, TVA  
: [[contact::G. Scott]], Licensing, TVA
: [[contact::D. Stinson]], Vice President, TVA Unit 2
: [[contact::D. Stinson]], Vice President, TVA Unit 2
Inspection Procedure Used
Inspection Procedure Used
TI 2515/107, Electrical Distribution System Functional Inspection (EDSFI)
TI 2515/107, Electrical Distribution System Functional Inspection (EDSFI)
List of Items Opened, Closed, and Discussed
List of Items Opened, Closed, and Discussed
Closed   2515/107 TI EDSFI - Assess the capacity of the EDS to perform its intended functions during all plant operating and accident
Closed
2515/107                           TI                             EDSFI - Assess the capacity
of the EDS to perform its
intended functions during all
plant operating and accident
conditions. (Section E.1.1)
conditions. (Section E.1.1)
2011606-01 (Example #9)
2011606-01 (Example #9)           URI                           Diesel Generator Loading
URI Diesel Generator Loading Analysis - Electrical Design Issues (Section OA.1.2)
Analysis - Electrical Design
Discussed 86-13 CDR Inadequate calculations to document electrical system
Issues (Section OA.1.2)
Discussed
86-13                             CDR                           Inadequate calculations to
document electrical system
design basis (Section OA.1.1)
Open Item 7                        SSER-22                        Inadequate calculations to
                                  (App. HH)                      document electrical system
design basis (Section OA.1.1)
design basis (Section OA.1.1)
Open Item 7
SSER-22 (App. HH)
Inadequate calculations to document electrical system design basis (Section OA.1.1)


List of Documents Reviewed
List of Documents Reviewed
Problem Evaluation Reports Generated During This Inspection
Problem Evaluation Reports Generated During This Inspection
PER 458200, NRC identified that not all calculations listed in NEDP-2, Appendix E can be found in CCRIS PER 462617, NRC identified discrepancies in calculation EDQ00299920080016, Rev. 5 PER 464997, NRC identified unanalyzed load in calculation EDQ00099920080014, Rev. 14 PER 463429, NRC identified "Calculation of Record" contradiction in calculation EDQ00023620070003, Rev. 12 PER 463512, NRC identified incorrect test result value in 1-EI-82-40A
PER 458200, NRC identified that not all calculations listed in NEDP-2, Appendix E can be found
in CCRIS
PER 462617, NRC identified discrepancies in calculation EDQ00299920080016, Rev. 5
PER 464997, NRC identified unanalyzed load in calculation EDQ00099920080014, Rev. 14
PER 463429, NRC identified Calculation of Record contradiction in calculation
EDQ00023620070003, Rev. 12
PER 463512, NRC identified incorrect test result value in 1-EI-82-40A
PER 464992, NRC identified errors contained in Unit 2 protection and coordination calculations
PER 464992, NRC identified errors contained in Unit 2 protection and coordination calculations
Calculations
Calculations
EDQ00299920080016, 6.9 kV Protection and Coordination Calculation, Rev. 5 EDQ00299920080004, 480V Class 1E Protection, Coordination and Thermal Overload Heater Calculation - Unit 2, Rev. 12 EDQ00023620070003, 125V DC Vital Battery System Analysis, Rev. 12
EDQ00299920080016, 6.9 kV Protection and Coordination Calculation, Rev. 5
EDQ00223620080011, 125V DC Vital Power Control Voltage Analysis - Unit 2, Rev. 6 EDQ00299920080003, Class 1E MCC Control Circuit Voltage Analysis and Transformer Sizing, Rev. 4 EDQ00299920080010, 120VAC Vital Power Load Flow and Voltage Drop Analysis, Rev. 9 EDQ00099920080014, Diesel Generator Loading, Rev. 14
EDQ00299920080004, 480V Class 1E Protection, Coordination and Thermal Overload Heater
EDQ00099920070002, AC Auxiliary Power System Analysis, Rev. 21 EDQ00299920080006, Unit 2 Class 1E V3 Cable Ampacity, Rev. 11 EDQ00299920080002, Unit 2 Class 1E V4 Cable Ampacity, Rev. 17 EDQ00299920080001, Unit 2 V5 Cable Ampacity, Rev. 6 WBNEEBMSTI070018, 120 VAC Short Circuit Coordination Study and Protection to examine the coordination and protection of 120 volt safety related circuits, Rev. 81 WBNEEBMSTI070005, Identifies time-current curves for battery boards I-IV on sheets 84, 85 and 86 or TCC-10, 11, & 12, Rev. 49
Calculation - Unit 2, Rev. 12
EDQ00023620070003, 125V DC Vital Battery System Analysis, Rev. 12
EDQ00223620080011, 125V DC Vital Power Control Voltage Analysis - Unit 2, Rev. 6
EDQ00299920080003, Class 1E MCC Control Circuit Voltage Analysis and Transformer Sizing,
Rev. 4
EDQ00299920080010, 120VAC Vital Power Load Flow and Voltage Drop Analysis, Rev. 9
EDQ00099920080014, Diesel Generator Loading, Rev. 14
EDQ00099920070002, AC Auxiliary Power System Analysis, Rev. 21
EDQ00299920080006, Unit 2 Class 1E V3 Cable Ampacity, Rev. 11
EDQ00299920080002, Unit 2 Class 1E V4 Cable Ampacity, Rev. 17
EDQ00299920080001, Unit 2 V5 Cable Ampacity, Rev. 6
WBNEEBMSTI070018, 120 VAC Short Circuit Coordination Study and Protection to examine
the coordination and protection of 120 volt safety related circuits, Rev. 81
WBNEEBMSTI070005, Identifies time-current curves for battery boards I-IV on sheets 84, 85
and 86 or TCC-10, 11, & 12, Rev. 49
Technical Manuals
Technical Manuals
GE Relay Instruction Manual GEK-34053G Time Overcurrent Relays IAC51.
GE Relay Instruction Manual GEK-34053G Time Overcurrent Relays IAC51.
Drawings 1-45W760-68-3, R12 - Unit 1, Wiring Diagram, Reactor Coolant System, Schematic Diagrams 1-45W724-4, R21 - Units 1 & 2, Wiring Diagrams, 6900V Shutdown Board 2B-B, Single Line
Drawings
45B2766-2E Rev. 5, FCR Number 55769-A page 104 / EDCR Number 53287-A page 141 45B2766-17F Rev. 3, FCR Number 55769-A page 147 / EDCR Number 53287-A page 188
1-45W760-68-3, R12 - Unit 1, Wiring Diagram, Reactor Coolant System, Schematic Diagrams
1-45W724-4, R21 - Units 1 & 2, Wiring Diagrams, 6900V Shutdown Board 2B-B, Single Line
45B2766-2E Rev. 5, FCR Number 55769-A page 104 / EDCR Number 53287-A page 141
45B2766-17F Rev. 3, FCR Number 55769-A page 147 / EDCR Number 53287-A page 188
Miscellaneous
Miscellaneous
Electrical Design Guide DG-E7.1.2 Rev. 0 Titled: Protective Relay System Design for AC Auxiliary Power System, Section 2.1.3.1 Induction Motors Surveillance Procedure 0-SI-82-3, Rev. 0048 WBN Unit 0, 18 Month Loss of Offsite Power With Safety Injection - DG 1A-A, Section 6.2 ESF Actuation - Offsite Power Available DNE Calculation E31850221300, Rev. 4 - 6.9 kV Shutdown Board Normal and Alternate Feeders with EBASCO recommendation letter of February 6, 1992 EB-ALS-92-021; Subject: Watts Bar Nuclear Plant 6.9 kV Board Feeder Relay Settings (DCN M-12051) EDCR 53287 associated with the replacement of obsolete and replacement circuit breakers type ITE model EF3 and FJ3.
Electrical Design Guide DG-E7.1.2 Rev. 0 Titled: Protective Relay System Design for AC
EDCR 54172 for the resolution of a number of motor protection settings and cable sizes EDCR 55229 for the replacement of a number of motor feeders that had been undersized EDCR 53287, Rev. A Section 6.1.7 Obsolete and Replacement Circuit Breakers PEG Package No. 2008-94001, Inverter Specification 0-MI-235.002, 120 V AC Vital Inverter Automatic Transfer Test DS-E12.6.3, Auxiliary and Control Power Cable Sizing, Up to 15,000 Volts, Rev.10
Auxiliary Power System, Section 2.1.3.1 Induction Motors
Integrated Cable and Raceway Design System (ICRDS) Software Requirements Specification, Rev. 5 WB-DC-30-28 titled: Low and Medium Voltage Power Systems, Section 2.10 Protection WBN-EEB-ED-Q000-999-2007-0002, Power System Analysis, Rev. 0 NEDP-2, Design Calculation Process Control, Rev. 15
Surveillance Procedure 0-SI-82-3, Rev. 0048 WBN Unit 0, 18 Month Loss of Offsite Power With
Safety Injection - DG 1A-A, Section 6.2 ESF Actuation - Offsite Power Available
DNE Calculation E31850221300, Rev. 4 - 6.9 kV Shutdown Board Normal and Alternate
Feeders with EBASCO recommendation letter of February 6, 1992 EB-ALS-92-021;
Subject: Watts Bar Nuclear Plant 6.9 kV Board Feeder Relay Settings (DCN M-12051)
EDCR 53287 associated with the replacement of obsolete and replacement circuit breakers
type ITE model EF3 and FJ3.
EDCR 54172 for the resolution of a number of motor protection settings and cable sizes
EDCR 55229 for the replacement of a number of motor feeders that had been undersized
EDCR 53287, Rev. A Section 6.1.7 Obsolete and Replacement Circuit Breakers
PEG Package No. 2008-94001, Inverter Specification
0-MI-235.002, 120 V AC Vital Inverter Automatic Transfer Test
DS-E12.6.3, Auxiliary and Control Power Cable Sizing, Up to 15,000 Volts, Rev.10
Integrated Cable and Raceway Design System (ICRDS) Software Requirements Specification,
Rev. 5
WB-DC-30-28 titled: Low and Medium Voltage Power Systems, Section 2.10 Protection
WBN-EEB-ED-Q000-999-2007-0002, Power System Analysis, Rev. 0
NEDP-2, Design Calculation Process Control, Rev. 15
WBRD-50-391/86-13, Lack of Adequate Calculations to Document Electrical System Design
WBRD-50-391/86-13, Lack of Adequate Calculations to Document Electrical System Design
Basis List of Acronyms
Basis
CCRIS Calculation Cross-Reference Information System CDBI Component Design Basis Inspection
List of Acronyms
CDR   Construction Deficiency Report CFR   Code of Federal Regulations DC Direct Current DCN Design Change Notice EDCR   Engineering Document Construction Release
CCRIS         Calculation Cross-Reference Information System
EDG Emergency Diesel Generator EDS Electrical Distribution System EDSFI Electrical Distribution System Functional Inspection ETAP Electrical Transient Analyzer Program FSAR Final Safety Analysis Report
CDBI           Component Design Basis Inspection
GL Generic Letter IMC   Inspection Manual Chapter IP Inspection Procedure KV Kilovolts MCC Motor Control Center
CDR           Construction Deficiency Report
NRC   Nuclear Regulatory Commission PER Problem Evaluation Report SSER   Supplement Safety Evaluation Report SR   Service Request TI   Temporary Instruction (NRC)
CFR           Code of Federal Regulations
TVA   Tennessee Valley Authority URI   Unresolved Item VAC Volts Alternating Current VDC Volts Direct Current WBN   Watts Bar Nuclear Plant
DC             Direct Current
DCN           Design Change Notice
EDCR           Engineering Document Construction Release
EDG           Emergency Diesel Generator
EDS           Electrical Distribution System
EDSFI         Electrical Distribution System Functional Inspection
ETAP           Electrical Transient Analyzer Program
FSAR           Final Safety Analysis Report
GL             Generic Letter
IMC           Inspection Manual Chapter
IP             Inspection Procedure
KV             Kilovolts
MCC           Motor Control Center
NRC           Nuclear Regulatory Commission
PER           Problem Evaluation Report
SSER           Supplement Safety Evaluation Report
SR             Service Request
TI             Temporary Instruction (NRC)
TVA           Tennessee Valley Authority
URI           Unresolved Item
VAC           Volts Alternating Current
VDC           Volts Direct Current
WBN           Watts Bar Nuclear Plant
}}
}}

Latest revision as of 02:44, 21 December 2019

IR 05000391-11-612, on 10/24/11 - 11/18/11, Watts Bar
ML11348A081
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 12/14/2011
From: Lesser M
NRC/RGN-II/DCI/CIB1
To: Skaggs M
Tennessee Valley Authority
References
IR-11-612
Download: ML11348A081 (14)
v • d • e


Text

UNITED STATES ber 14, 2011

SUBJECT:

WATTS BAR NUCLEAR PLANT UNIT 2 CONSTRUCTION - NRC INSPECTION REPORT 05000391/2011612

Dear Mr. Skaggs:

On November 18, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a team inspection of construction activities at your Watts Bar Unit 2 reactor facility. The enclosed inspection report documents the inspection results, which were discussed on November 18, 2011, with Mr. David Stinson and other members of your staff.

The NRC team performed an Electrical Distribution System Functional Inspection (EDSFI) using selected portions of NRC Temporary Instruction (TI) 2515/107. This inspection examined activities conducted under your Unit 2 construction permit as they relate to safety and compliance with the Commissions rules and regulations, with the conditions of your construction permit, and with fulfillment of Unit 2 regulatory framework commitments. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, no findings or violations of significance were identified.

TVA 2 In accordance with 10 CFR 2.390 of the NRCs 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 NRCs document 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/

Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection Docket No. 50-391 Construction Permit No: CPPR-92

Enclosure:

Inspection Report 05000391/2011612 w/attachment

REGION II==

Docket No.: 50-391 Construction Permit No.: CPPR-92 Report No.: 05000391/2011612 Applicant: Tennessee Valley Authority (TVA)

Facility: Watts Bar Nuclear Plant, Unit 2 Location: 1260 Nuclear Plant Rd Spring City TN 37381 Dates: October 24 - November 18, 2011 Inspectors: Caudle Julian, Team Leader, Construction Inspection Branch 1 (CIB 1), Division of Construction Inspection (DCI)

Region II (RII)

G. Crespo, Senior Construction Inspector, CIB1, DCI, RII R. Mathis, Construction Inspector, CIB1, DCI, RII C. Even, Project Inspector, Construction Projects Branch 3 (CPB 3), Division of Construction Projects (DCP), RII G. Morris, Consultant Approved by: Mark S. Lesser, Chief Construction Inspection Branch 1 Division of Construction Inspection Enclosure

EXECUTIVE SUMMARY

Watts Bar Nuclear Plant, Unit 2

This inspection included aspects of engineering activities performed by TVA associated with the Watts Bar Nuclear (WBN) Plant Unit 2 construction project. This report covered a two week period of inspection in the area of Electrical Distribution System Functional Inspection (EDSFI)as specified in NRC Temporary Instruction (TI) 2515/107. The inspection program for Unit 2 construction activities is described in NRC Inspection Manual Chapter (IMC) 2517. Information regarding the WBN Unit 2 Construction Project and NRC inspections can be found at http://www.nrc.gov/reactors/plant-specific-items/watts-bar.html.

Inspection Results The inspectors assessed the capability of the Electrical Distribution System (EDS) to perform its intended safety function during plant operating and accident conditions. The inspectors reviewed electrical calculations and analyses associated with cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and emergency diesel generator loading. The inspectors interviewed responsible engineering staff to confirm understanding of records. The inspectors determined that in general the calculations were complete, understandable, and technically adequate.

No violations of regulatory requirements were identified.

REPORT DETAILS

II.

Management Oversight and Control E.1 Engineering Activities E.1.1 (Closed) EDSFI Temporary Instruction (TI) 2515/107

a. Inspection Scope

Background: In 1979, the NRC published Generic Letter (GL) 79-36 to ask licensees to examine undervoltage protection of safety related electric equipment for potential damage as a result of sustained degraded voltage from the offsite electric grid system.

This generic letter was issued in response to events at a number of operating nuclear plants that brought into question the conformance of the station electric distribution system to 10 CFR 50, Appendix A - General Design Criteria - 17, Electric Power Systems. TI 2515/107 - EDSFI was issued on October 19, 1990 to provide a comprehensive NRC team inspection focused primarily on the EDS at operating nuclear plants to address the concerns raised by the Safety System Functional Inspections performed between 1986-1990 and Generic Letter 79-36. This inspection performed a portion of TI 2515/107 at Watts Bar 2.

Using the guidance of TI 2515/107, the inspectors examined the electrical distribution system with focus on the path supplying Shutdown Board 2B-B. The inspectors reviewed available design basis information and conducted plant walk-downs as necessary to assess the capacity of the electrical distribution system to perform its safety functions.

The inspectors assessed the capability of the EDS to perform its intended safety function during plant operating and accident conditions and reviewed design basis calculations for the EDS to evaluate whether they were coherent, accurate, and complete for supporting dual unit operation. The inspectors reviewed the calculations documenting the loading on various electrical sources such as emergency diesel generators, batteries, and shutdown boards. Specifically the inspectors performed detailed review of 11 electrical calculations focusing on cable ampacity, voltage analysis, load flow, transformer sizing, circuit protection & coordination, vital battery system, and diesel generator loading. The complete list of electrical calculations reviewed is included in the supplemental information at the end of this report. The inspectors also reviewed Final Safety Analysis Report (FSAR) descriptions, design specifications, drawings, system descriptions, and other design documents to support the assessment of the EDS design.

The inspectors reviewed selected referenced supporting calculations to confirm selected design inputs and assumptions. The inspectors interviewed responsible personnel, performed field walk-downs, and observed software analysis. The supplemental information attachment also includes a list of the documents reviewed in support of the inspection.

The inspection team reviewed the design inputs used in TVAs Electrical Transient Analyzer Program (ETAP) from the emergency diesel generators (EDGs) loading calculation to verify that the ETAP program matched the assumptions and conclusions of the calculation in dealing with the time zero loads in the EDG loading sequence. The inspection teams review of the EDG design calculation focused on the loads that are started at time zero in the loading sequence to verify that all design loads were appropriately captured and analyzed in ETAP. The inspectors took a sample of the time zero components and performed walk-downs of those components to gather nameplate data to verify that the components modeled in ETAP were the same as the components in the plant.

The inspectors interviewed responsible engineering staff to address questions generated from the review of the engineering documentation. The inspectors also reviewed surveillance and test procedures for the 125V DC vital power system and the 125V DC diesel generator system.

The inspectors confirmed that discrepancies found during this inspection were included by the applicant in their corrective action program. A list of the Problem Evaluation Reports (PERs) resulting from this inspection is included in supplemental information attached to this report.

b. Observations and Findings

No findings of significance were identified.

During the review of the DC vital power system, the inspectors found that Battery IV was degraded and there was evidence of problems from the results of the February 2011 performance test that had not been entered into the corrective action program. This issue was followed up by the Unit 1 NRC Senior Resident Inspector for operability concerns and will be appropriately documented in a subsequent inspection report for Unit 1.

The team determined that Degraded Voltage Relay settings and the associated degraded voltage analysis calculation is the subject of Open Item 30 in Appendix HH of NUREG-0847, Supplement 22. This issue will be resolved by the Office of Nuclear Reactor Regulation and was not inspected.

c. Conclusions

The inspectors determined that in general the calculations reviewed were complete, understandable, and technically adequate.

IV.

OTHER ACTIVITIES

OA.1.1 (Discussed) Construction Deficiency Report (CDR) WBRD-50-391/86-13, entitled Lack of Adequate Calculations to Document Electrical System Design Basis

a. Inspection Scope

The inspectors followed up on TVA resolution of Construction Deficiency Report (CDR)

WBRD-50-391/86-13, entitled Lack of Adequate Calculations to Document Electrical System Design Basis and an associated Action Item 7 in Appendix HH of SSER 22.

TVA initiated PER 144072 on February 3, 1989 associated with this issue. The inspectors examined the existing inventory of issued Unit 2 electrical design calculations and compared it to TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15, Appendix E, Electrical/I&C Engineering Calculation Classifications. The purpose was to confirm that all TVA specified essential electrical and I&C calculations have been prepared and issued.

b. Observations and Findings

TVAs method of resolving the CDR was to establish a list which identifies a minimum set of Electrical and Instrumentation and Control (I&C) calculations necessary to fully document the design basis of a TVA nuclear plant. The list was first issued as a memo for electrical branch direction on July 17, 1987, and contained essential and desirable calculations. The content of that list was subsequently issued as Appendix E, Electrical/I&C Engineering Calculation Classifications of TVA NPG Standard Department Procedure NEDP-2, Design Calculation Process Control, Revision 15. TVA calculations are now organized and controlled by the Calculation Cross Reference Information System (CCRIS) computer system. The inspectors examined an index of calculations from CCRIS and found that most of the topics listed in Appendix E had corresponding calculations issued. However the inspectors could not find calculations listed for all of the topics under the headings of Raceway System Calculations or Instrumentation and Control System Calculations. TVA representatives stated that they needed to do more work on this item before it is ready for NRC review and closure and they initiated PER 458200 to track corrective action on this item. No findings of significance were identified.

c. Conclusion TVA representatives concluded that this item requires more work before it is ready for NRC review and closure and they initiated PER 458200 to track corrective actions.

Additional NRC inspection is required to close this item when TVA work is complete.

OA.1.2 (Closed) Unresolved Item 05000391/2011606-01, Ninth Example, Electrical Design Issues Requiring Additional Review

a. Inspection Scope

This unresolved item contained nine examples of electrical issues requiring further inspection to determine if a violation existed. The ninth example concerned a lack of information in calculation EDQ00099920080014, Rev. 8, Diesel Generator Loading

Analysis.

During this inspection inspectors reviewed Revision 14 of that calculation.

b. Observations and Findings

No findings of significance were identified The inspectors determined that the essential information was included and the calculation was technically acceptable.

The inspectors concluded that the failure to include information in previous revisions was a minor violation.

c. Conclusion The ninth example of this unresolved item is closed.

V. Management Meetings X.1

Exit Meeting Summary

On November 18, 2011, the inspectors presented the inspection results to Mr. David Stinson and other members of his staff. The inspectors confirmed that no proprietary information was reviewed during this inspection or included in this inspection report.

SUPPLEMENTAL INFORMATION

Partial List of Persons Contacted

Applicant personnel

A. Bangalore, Electrical Design Manager, Bechtel
D. Beckley, Electrical Design Engineer, TVA Unit 2
D. Charlton, Licensing, TVA
W. Elliott, TVA Oversight
S. Hilmes, Unit 2 Lead Electrical Engineer, TVA
I. Khan, Electrical Engineer, Washington Group
G. Scott, Licensing, TVA
D. Stinson, Vice President, TVA Unit 2

Inspection Procedure Used

TI 2515/107, Electrical Distribution System Functional Inspection (EDSFI)

List of Items Opened, Closed, and Discussed

Closed

2515/107 TI EDSFI - Assess the capacity

of the EDS to perform its

intended functions during all

plant operating and accident

conditions. (Section E.1.1)

2011606-01 (Example #9) URI Diesel Generator Loading

Analysis - Electrical Design

Issues (Section OA.1.2)

Discussed

86-13 CDR Inadequate calculations to

document electrical system

design basis (Section OA.1.1)

Open Item 7 SSER-22 Inadequate calculations to

(App. HH) document electrical system

design basis (Section OA.1.1)

List of Documents Reviewed

Problem Evaluation Reports Generated During This Inspection

PER 458200, NRC identified that not all calculations listed in NEDP-2, Appendix E can be found

in CCRIS

PER 462617, NRC identified discrepancies in calculation EDQ00299920080016, Rev. 5

PER 464997, NRC identified unanalyzed load in calculation EDQ00099920080014, Rev. 14

PER 463429, NRC identified Calculation of Record contradiction in calculation

EDQ00023620070003, Rev. 12

PER 463512, NRC identified incorrect test result value in 1-EI-82-40A

PER 464992, NRC identified errors contained in Unit 2 protection and coordination calculations

Calculations

EDQ00299920080016, 6.9 kV Protection and Coordination Calculation, Rev. 5

EDQ00299920080004, 480V Class 1E Protection, Coordination and Thermal Overload Heater

Calculation - Unit 2, Rev. 12

EDQ00023620070003, 125V DC Vital Battery System Analysis, Rev. 12

EDQ00223620080011, 125V DC Vital Power Control Voltage Analysis - Unit 2, Rev. 6

EDQ00299920080003, Class 1E MCC Control Circuit Voltage Analysis and Transformer Sizing,

Rev. 4

EDQ00299920080010, 120VAC Vital Power Load Flow and Voltage Drop Analysis, Rev. 9

EDQ00099920080014, Diesel Generator Loading, Rev. 14

EDQ00099920070002, AC Auxiliary Power System Analysis, Rev. 21

EDQ00299920080006, Unit 2 Class 1E V3 Cable Ampacity, Rev. 11

EDQ00299920080002, Unit 2 Class 1E V4 Cable Ampacity, Rev. 17

EDQ00299920080001, Unit 2 V5 Cable Ampacity, Rev. 6

WBNEEBMSTI070018, 120 VAC Short Circuit Coordination Study and Protection to examine

the coordination and protection of 120 volt safety related circuits, Rev. 81

WBNEEBMSTI070005, Identifies time-current curves for battery boards I-IV on sheets 84, 85

and 86 or TCC-10, 11, & 12, Rev. 49

Technical Manuals

GE Relay Instruction Manual GEK-34053G Time Overcurrent Relays IAC51.

Drawings

1-45W760-68-3, R12 - Unit 1, Wiring Diagram, Reactor Coolant System, Schematic Diagrams

1-45W724-4, R21 - Units 1 & 2, Wiring Diagrams, 6900V Shutdown Board 2B-B, Single Line

45B2766-2E Rev. 5, FCR Number 55769-A page 104 / EDCR Number 53287-A page 141

45B2766-17F Rev. 3, FCR Number 55769-A page 147 / EDCR Number 53287-A page 188

Miscellaneous

Electrical Design Guide DG-E7.1.2 Rev. 0 Titled: Protective Relay System Design for AC

Auxiliary Power System, Section 2.1.3.1 Induction Motors

Surveillance Procedure 0-SI-82-3, Rev. 0048 WBN Unit 0, 18 Month Loss of Offsite Power With

Safety Injection - DG 1A-A, Section 6.2 ESF Actuation - Offsite Power Available

DNE Calculation E31850221300, Rev. 4 - 6.9 kV Shutdown Board Normal and Alternate

Feeders with EBASCO recommendation letter of February 6, 1992 EB-ALS-92-021;

Subject: Watts Bar Nuclear Plant 6.9 kV Board Feeder Relay Settings (DCN M-12051)

EDCR 53287 associated with the replacement of obsolete and replacement circuit breakers

type ITE model EF3 and FJ3.

EDCR 54172 for the resolution of a number of motor protection settings and cable sizes

EDCR 55229 for the replacement of a number of motor feeders that had been undersized

EDCR 53287, Rev. A Section 6.1.7 Obsolete and Replacement Circuit Breakers

PEG Package No. 2008-94001, Inverter Specification

0-MI-235.002, 120 V AC Vital Inverter Automatic Transfer Test

DS-E12.6.3, Auxiliary and Control Power Cable Sizing, Up to 15,000 Volts, Rev.10

Integrated Cable and Raceway Design System (ICRDS) Software Requirements Specification,

Rev. 5

WB-DC-30-28 titled: Low and Medium Voltage Power Systems, Section 2.10 Protection

WBN-EEB-ED-Q000-999-2007-0002, Power System Analysis, Rev. 0

NEDP-2, Design Calculation Process Control, Rev. 15

WBRD-50-391/86-13, Lack of Adequate Calculations to Document Electrical System Design

Basis

List of Acronyms

CCRIS Calculation Cross-Reference Information System

CDBI Component Design Basis Inspection

CDR Construction Deficiency Report

CFR Code of Federal Regulations

DC Direct Current

DCN Design Change Notice

EDCR Engineering Document Construction Release

EDG Emergency Diesel Generator

EDS Electrical Distribution System

EDSFI Electrical Distribution System Functional Inspection

ETAP Electrical Transient Analyzer Program

FSAR Final Safety Analysis Report

GL Generic Letter

IMC Inspection Manual Chapter

IP Inspection Procedure

KV Kilovolts

MCC Motor Control Center

NRC Nuclear Regulatory Commission

PER Problem Evaluation Report

SSER Supplement Safety Evaluation Report

SR Service Request

TI Temporary Instruction (NRC)

TVA Tennessee Valley Authority

URI Unresolved Item

VAC Volts Alternating Current

VDC Volts Direct Current

WBN Watts Bar Nuclear Plant

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