IR 05000321/2013010: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303
[[Issue date::June 21, 2013]]
-1257 June 21, 2013 Mr. Dennis R. Madison Vice President Southern Nuclear Operating Company, In Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513


Mr. Dennis Vice President Southern Nuclear Operating Company, Inc. Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513
SUBJECT: EDWIN I. HATCH NUCLEAR PLANT
- NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/20 1 3 0 10 AND 05000366/20 1 3 0 1 0 Dear Mr. Madison
:
On Ma y 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and The enclosed inspection report documents the inspection results which were discussed on May 23, 2013 , with you and other members of your staf The inspection examined activities conducted under your license s as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license The team reviewed selected procedures and records, observed activities, and interviewed personne No findings were identified during this inspectio 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 Agency
-wide Document Access and Management System (ADAMS).


SUBJECT: EDWIN I. HATCH NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/2013010 AND 05000366/2013010
D. Madison 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).


==Dear Mr. Madison:==
Sincerely,RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.:
On May 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on May 23, 2013, with you and other members of your staff. The inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your licenses. The team reviewed selected procedures and records, observed activities, and interviewed personnel. No findings were identified during this inspection. 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 Agency-wide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
50-321, 50-366 License Nos.:
 
DPR-57 and NPF
Sincerely,RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5  
-5  


===Enclosure:===
===Enclosure:===
Inspection Report 05000321/2013010, 05000366/2013010
Inspection Report 05000321/20130 10, 05000366/20130 1 0


===w/attachment:===
===w/attachment:===
Supplemental Information Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5 Report Nos.: 05000321/2013010 and 05000366/2013010 Licensee: Southern Nuclear Operating Company, Inc. Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, Georgia 31513 Dates: May 6 - May 23, 2013 Inspectors: E. Stamm, Senior Reactor Inspector (Team Leader) A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)
Supplemental Information
Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure  
 
Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos.:
50-321, 50-366 License Nos.:
DPR-57 and NPF
-5 Report Nos.:
05000321/20 1 3 0 1 0 and 05000366/20 1 3 0 1 0 Licensee: Southern Nuclear Operating Company, In Facility: Edwin I. Hatch Nuclear Plant
 
Location: Baxley, Georgia 31513 Dates: May 6 - Ma y 2 3 , 2013 Inspectors:
E. Stamm, Senior Re ac t or Inspector (Team Leader)
A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)
Approved by:
Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure  


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
IR 05000321/2013010, 05000366/2013010; 05/06/2013-05/23/2013; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications This report covers a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRC's program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4. No findings were identified during this inspection.
IR 05000321/20 1 3 0 10, 05000366/20 1 3 0 1 0; 0 5/0 6/20 1 3-0 5/2 3/20 1 3; Edwin I. Hatch Nuclear Plant, Units 1 and 2
; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications Th is report cover s a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRC's program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process
," Revision 4.
 
No findings were identified during this inspection
.


=REPORT DETAILS=
=REPORT DETAILS=


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity 1R1 7  Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.1 7T)
{{a|1R17}}
==1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications==
{{IP sample|IP=IP 71111.17T}}


====a. Inspection Scope====
====a. Inspection Scope====
Evaluations of Changes, Tests, and Experiments:  From May 6, 2013, through May 23, 2013, the team reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 13 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:   the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issues requiring the changes, tests or experiments were resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation used to support the change was updated to reflect the change. The team used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The team also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments," dated March 2001. This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
Evaluations of Changes, Tests, and Experiments
:  From May 6, 2013, through May 23 , 2013, the team reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 13 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issues requiring the changes, tests or experiments were resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation used to support the change was updated to reflect the change.
 
The team used, in part, Nuclear Energy Institute (NEI) 96
-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The team also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments
," dated March 2001.
 
This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
 
Permanent Plant Modifications
:  From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:
Design Change Package (DCP) 1071694001
, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0 DCP 1072721101
, Reroute Cables out of Fire Area 0014, Ver. 3.0 DCP 1081976501
, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0  DCP 1092321101
, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.
 
DCP 1101786501
, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0 DCP 2039000201
, 4.16kV Breaker Replacement, Ver. 1.1 The modifications were selected based upon risk significance, safety significance, and complexity.
 
The team reviewed the modifications selected to determine if:
the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification ha d been adequately updated; the test documentation as required by the applicable test programs ha d been updated; and post-modification testing adequately verified system operability and/or functionality.


Permanent Plant Modifications:  From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:  Design Change Package (DCP) 1071694001, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0  DCP 1072721101, Reroute Cables out of Fire Area 0014, Ver. 3.0  DCP 1081976501, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0  DCP 1092321101, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walk downs of accessible portions of the modifications. Documents reviewed are listed in the Attachment.


DCP 1101786501, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0  DCP 2039000201, 4.16kV Breaker Replacement, Ver. 1.1  The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if:  the supporting design and licensing basis documentation was updated;  the changes were in accordance with the specified design requirements;  the procedures and training plans affected by the modification had been adequately updated;  the test documentation as required by the applicable test programs had been updated; and  post-modification testing adequately verified system operability and/or functionality. The team also used applicable industry standards to evaluate acceptability of the modifications and performed walk downs of accessible portions of the modifications. Documents reviewed are listed in the Attachment. This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.
This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified
.


{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, Including Exit==
==4OA6 Meetings, Including Exit==
On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.


Line 69: Line 113:


===Licensee personnel===
===Licensee personnel===
: [[contact::B. Anderson]], Health Physics Manager  
: [[contact::B. Anderson]], Health Physics Manager
: [[contact::S. Beverly]], Licensing Engineer  
: [[contact::S. Beverly]], Licensing Engineer
: [[contact::T. Crowell]], Site Design Engineer  
: [[contact::T. Crowell]], Site Design Engineer
: [[contact::E. DelRosario]], Site Design Engineer  
: [[contact::E. DelRosario]], Site Design Engineer
: [[contact::D. Hines]], Site Design Supervisor  
: [[contact::D. Hines]], Site Design Supervisor
: [[contact::B. Hulett]], Site Design Manager
: [[contact::B. Hulett]], Site Design Manager  
: [[contact::C. Lane]], Engineering Director  
: [[contact::C. Lane]], Engineering Director
: [[contact::K. Long]], Operations Director  
: [[contact::K. Long]], Operations Director
: [[contact::D. Madison]], Vice President  
: [[contact::D. Madison]], Vice President
: [[contact::C. McCall]], Project Engineer  
: [[contact::C. McCall]], Project Engineer
: [[contact::M. Peacock]], Designer  
: [[contact::M. Peacock]], Designer
: [[contact::C. Robinson]], ASD Engineer  
: [[contact::C. Robinson]], ASD Engineer
: [[contact::R. Seiter]], Engineering Supervisor  
: [[contact::R. Seiter]], Engineering Supervisor
: [[contact::B. Shuman]], Engineering Programs Manager  
: [[contact::B. Shuman]], Engineering Programs Manager  
: [[contact::S. Tipps]], Licensing Supervisor  
: [[contact::S. Tipps]], Licensing Supervisor
: [[contact::D. Vineyard]], Plant Manager  
: [[contact::D. Vineyard]], Plant Manager
: [[contact::T. Wells]], Principal Engineer  
: [[contact::T. Wells]], Principal Engineer
: [[contact::E. Wonn]], Senior Designer  
: [[contact::E. Wonn]], Senior Designer
: [[contact::F. Zayas]], Site Design Supervisor
: [[contact::F. Zayas]], Site Design Supervisor
 
===NRC personnel===
===NRC personnel===
: [[contact::E. Morris]], Senior Resident Inspector, Hatch  
: [[contact::E. Morris]], Senior Resident Inspector, Hatch
: [[contact::D. Hardage]], Resident Inspector, Hatch  
: [[contact::D. Hardage]], Resident Inspector, Hatch
 
==LIST OF ITEMS==
==LIST OF ITEMS==
OPENED AND CLOSED
OPENED AND CLOSED
===Opened and Closed===
 
===Opened and
Closed===
None       
None       


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
10
CFR 50.59 Evaluations Licensing Document Change Request (LDCR) 2004-022 , TRM/FSAR Revision to Increase
: CFR 50.59 Evaluations Licensing Document Change Request (LDCR) 2004-022, TRM/FSAR Revision to Increase
: RCIC Inboard Isolation Closure Time Acceptance Criteria, Ver. 1.0  
: RCIC Inboard Isolation Closure Time Acceptance Criteria, Ver. 1.0 Action Item (AI)
===Action Item===
: 2008200410, RCIC Accident Temperature and Pressure, dated 2/14/2008
(AI)
: DCP 1040048401, Replacement of Reactor Recirculation Pump Motor Generator Sets with
: 2008200410 , RCIC Accident Temperature and Pressure, dated 2/14/2008
: Adjustable Speed Drives, Ver. 9.0 DCP
: DCP 1040048401, Replacement of Reactor Recirculation Pump Motor Generator Sets with Adjustable Speed Drives, Ver. 9.0
: C062145201, Westinghouse
: DCP C062145201
: SVEA-96 Optima2 Lead Use Assemblies, Ver. 1.0 Technical Evaluation (TE)
, Westinghouse SVEA
-96 Optima2 Lead Use Assemblies, Ver. 1.0
: Technical Evaluation (TE)
: 320565, LDCR for Detector Not Full in Rod Block Function, Rev. 0
: 320565, LDCR for Detector Not Full in Rod Block Function, Rev. 0
: AI 2007205079/RER
: AI 2007205079/RER
: C072813201, Movement of Heavy Loads Over Spent Fuel Pool,    dated 1/9/08 Minor Design Change
: C072813201 , Movement of Heavy Loads Over Spent Fuel Pool ,    dated 1/9/08
: 1101735601, HPCI Turbine Exhaust Drain Line Removal, Ver. 1.0 DCP SNC119724, F River Temperature, dated 12/15/11
: Minor Design Change 1101735601
: 10
, HPCI Turbine Exhaust Drain Line Removal, Ver. 1.0
: DCP SNC119724 , F River Temperature, dated 12/15/11
: CFR 50.59 Screenings
: CFR 50.59 Screenings
: DCP 2072720601, Unit 2 FPCC System Heat Exchanger Replacement, Ver. 5.0
: DCP 2072720601
: DCP 2080067101, Main Steam S/RV Replacement, Ver. 7.0 Equivalency Determination (ED)
, Unit 2 FPCC System Heat Exchanger Replacement, Ver. 5.0
: C110573201, Valve Check 14", 300 lb. Crane Swing Check
: DCP 2080067101
: Valve for RHR Service Water, Ver. 2.0 DCP SNC116958, Remove Unit 2 HPCI Turbine Exhaust Drain Line, Ver. 1.0 ED SNC340426, Relay K3 for EDG Exciter, Ver. 1.0 ED SNC341510, Replacement Parts for General Electric Type
, Main Steam  
: AK-25 Circuit Breaker, Ver. 1.0 ED SNC345576, AVR Assembly for EDG Exciter, Ver. 1.0 DCP SNC429939, Unit 2 Modified 3-stage SRV Replacement, Ver. 1.0 ED SNC452392, Hydraulic Actuator for MSIVs, Ver. 1.0
: S/RV Replacement, Ver. 7.0
: DCP 1042453001, Replacement Obsolete Recorders in Panel 1H11-P614, Ver. 4.0
: Equivalency Determination (ED)
: DCP 1072724101, Replace Modified 36-05 and 44-13 Local Power Range Monitors (LPRMs)   with standard LPRMs, Ver. 2.0
: C110573201, Valve Check 14", 300 lb
: DCP 1081709901, CRD Pump Room Cooler Cooling Coil Replacement, Ver. 2.0
. Crane Swing Check Valve for RHR Service Water, Ver. 2.0
: DCP SNC116958 , Remove Unit 2 HPCI Turbine Exhaust Drain Line, Ver. 1.0 ED SNC340426 , Relay K3 for EDG Exciter, Ver. 1.0
: ED SNC341510 , Replacement Parts for General Electric Type AK
-25 Circuit Breaker, Ver. 1.0
: ED SNC345576 , AVR Assembly for EDG Exciter, Ver. 1.0
: DCP SNC429939 , Unit 2 Modified  
: 3-stage SRV Replacement, Ver. 1.0
: ED SNC452392, Hydraulic Actuator for MSIVs, Ver. 1.0
: DCP 1042453001, Replacement Obsolete Recorders in Panel 1H11
-P614, Ver. 4.0
: DCP 10727 24101, Replace Modified 36
-05 and 44-13 Local Power Range Monitors (LPRMs)
with standard LPRMs, Ver. 2.0
: DCP 1081709901
, CRD Pump Room Cooler Cooling Coil Replacement, Ver. 2.0
: DCP 1081750401, Data Acquisition and Analysis System (DAAS) Replacement, Ver. 3.0  
: DCP 1081750401, Data Acquisition and Analysis System (DAAS) Replacement, Ver. 3.0  
===Calculations===
===Calculations===
: BH1-M-V004-B007-0001, Compartment Long-Term Temperature Analysis, Ver. 10.0
: BH1-M-V004-B007-0001, Compartment Long
: BH2-M-0295, Compartment Long-Term Temperature Analysis, Ver. 9.0
-Term Temperature Analysis, Ver. 10.0
: BH2-M-0295, Compartment Long
-Term Temperature Analysis, Ver. 9.0
: CA-1272, Aerofin Coil Selection Program Verification & Validation Documentation, Rev. 1
: CA-1272, Aerofin Coil Selection Program Verification & Validation Documentation, Rev. 1
: CA-1481, Aerofin Performance Verification for Aerofin Type "W" Coils, Rev. 1
: CA-1481, Aerofin Performance Verification for Aerofin Type "W" Coils, Rev. 1
: CA-529, Aerofin Calculation File, CRD Pump Room Cooling Coil, Ver. 2
: CA-529, Aerofin Calculation File, CRD Pump Room Cooling Coil, Ver. 2
: MC-H-09-019, Southern design Calculation, Cooling Unit Support, Ver. 0 S-53596-A, Shroud Repair Seismic Design Report Unit 1, Rev. 1 S-58367, E. I. Hatch Nuclear Plant - Unit No. 1, Shroud Repair replacement Upper Support
: MC-H-09-019, Southern design Calculation, Cooling Unit Support, Ver. 0
: Stress Analysis Report, Ver. 2.0  
: S-53596-A, Shroud Repair Seismic Design Report Unit 1, Rev. 1
: S-58367 , E. I. Hatch Nuclear Plant  
- Unit No. 1, Shroud Repair replacement Upper Support Stress Analysis Report, Ver. 2.0  
===Condition Reports===
===Condition Reports===
: CAR196955
: CAR196955 CR2002004824
: CR2002004824
: CR2008107088
: CR2008107088
: CR558872   
: CR558872   
: Attachment Drawings 10-502, Reactor Recirculation System Logic Diagrams Sheet 1, Ver. 7.0 10-502, Reactor Recirculation System Logic Diagrams Sheet 2, Ver. 1.0 10-502, Reactor Recirculation System Logic Diagrams Sheet 3, Ver. 25.0 10-502, Logic Diagrams Legend and General Notes H-10167, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Paths, Ver. 11.0 H-10171, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Matrix, Weights   and lifts, Ver. 5.0 H-11600, Unit 1 P&ID for Service Water and Diesel Generator, Sheet 2, Rev. 36 H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 2, Rev. 4 H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 3, Rev. 5 H-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 14 H-26051, Edwin I. Hatch Nuclear Plant Unit 2, Reactor Building - Plant Service Water System
: Attachment  
===Drawings===
: 10-502, Reactor Recirculation System Logic Diagrams Sheet 1, Ver. 7.0
: 10-502, Reactor Recirculation System Logic Diagrams Sheet 2, Ver. 1.0
: 10-502, Reactor Recirculation System Logic Diagrams Sheet 3, Ver. 25.0
: 10-502, Logic Diagrams Legend and General Notes
: H-10167, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Paths, Ver. 11.0 H-10171, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Matrix, Weights and lifts, Ver. 5.0
: H-11600, Unit 1 P&ID for Service Water and Diesel Generator, Sheet 2, Rev. 36
: H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 2, Rev. 4
: H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 3, Rev. 5
: H-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 14
: H-26051, Edwin I. Hatch Nuclear Plant Unit 2, Reactor Building  
- Plant Service Water System  
: P&ID, Ver. 47
: P&ID, Ver. 47
: HB-11004, Edwin I. Hatch Nuclear Plant Unit No. 1, RHR Service Water Outside Building ISI
: HB-11004, Edwin I. Hatch Nuclear Plant Unit No. 1, RHR Service Water Outside Building ISI  
: Boundary Diagram, Ver. 5.0
: Boundary Diagram, Ver. 5.0
: HB-16173, Fission Products Monitoring System ISI Boundary Diagram, Ver. 2
: HB-16173, Fission Products Monitoring System ISI Boundary Diagram, Ver. 2
: HB-21039, Edwin I. Hatch Nuclear Plant Unit No. 2, RHR Service Water Outside Building ISI
: HB-21039, Edwin I. Hatch Nuclear Plant Unit No. 2, RHR Service Water Outside Building ISI  
: Boundary Diagram, Ver. 11.0
: Boundary Diagram, Ver. 11.0
: HL-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 3 S-15484, Reactor Shroud, Rev. 10 S-19638, Edwin I. Hatch Nuclear Plant Unit 1, Cooling Units Design Data, Ver. 2.0 S-28751, Edwin I. Hatch Nuclear Plant No. 2, Cast Steel Swing Check Valve, Ver. 2
: HL-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 3
: S-53593, Shroud Repair Modifications & Installation - Reactor, Sh-2, Rev. 1
: S-15484, Reactor Shroud, Rev. 10
: S-19638, Edwin I. Hatch Nuclear Plant Unit 1, Cooling Units Design Data, Ver. 2.0
: S-28751, Edwin I. Hatch Nuclear Plant No. 2, Cast Steel Swing Check Valve, Ver. 2
: S-53593, Shroud Repair Modifications & Installation  
- Reactor, Sh
-2, Rev. 1
: SA-A018, 20x5 MSIV Actuator, Sheets 1 thru 6 of 6, Rev. 7  
: SA-A018, 20x5 MSIV Actuator, Sheets 1 thru 6 of 6, Rev. 7  
===Miscellaneous Documents===
===Miscellaneous Documents===
: 0000-0154-9209, SNC SRV Specification
: 0000-0154-9209, SNC SRV Specification HM
: HM-S-09-001 Review, Ver. 0 30035-99 Rev A, Wyle Laboratories Test Report, Volumes I thru
-S-09-001 Review, Ver. 0
: VI 34SO-B31-001, Reactor Recirculation System, Ver. 43.2
: 30035-99 Rev A, Wyle Laboratories Test Report, Volumes I thru VI
: CCN-H-09-0004, A46 Evaluation of Cable Spreading Room-cable Tray Support Anchorage
: 34SO-B31-001, Reactor Recirculation System, Ver. 43.2
: Against the Base Calculation
: CCN-H-09-0004, A46 Evaluation of Cable Spreading Room
: SCNH-92-034 (Version 4.0), Ver. 1.0 Code Case N-60-5, Cases of ASME Boiler and Pressure Vessel Code, dated 2/15/94 Copper Development Association, CDA Publication TN31, Copper-Nickel 90/10 and 70/30
-cable Tray Support Anchorage Against the Base Calculation SCNH
: Alloys Technical Data, 1982
-92-034 (Version 4.0
: DOEJ-HD1072721101C001, Seismic Evaluations of Cables added to tray
), Ver. 1.0
: TL8-10, Hatch
: Code Case N
: Nuclear Plant U1, Ver. 1.0
-60-5, Cases of ASME Boiler and Pressure Vessel Code, dated 2/15/94
: DOEJ-HD1072721101-E002, Adequacy of R23-S004-ES8-C06A Reroute cable out of Fire Area
: Copper Development Association, CDA Publication TN31, Copper
-Nickel 90/10 and 70/30  
: Alloys Technical Data , 1982
: DOEJ-HD1072721101C001, Seismic Evaluations of Cables added to tray TL8
-10, Hatch Nuclear Plant U1, Ver. 1.0
: DOEJ-HD1072721101
-E002, Adequacy of R23-S004-ES8-C06A Reroute cable out of Fire Area  
: 0014, Ver. 1.0
: 0014, Ver. 1.0
: DOEJ-HD1081750401-J001, EMI/RFI Evaluation for HPCI/RCIC DAAS Equipment
: DOEJ-HD1081750401
: Replacement, Rev. 0
-J001, EMI/RFI Evaluation for HPCI/RCIC DAAS Equipment Replacement, Rev. 0
: DOEJ-HD1081750401-M001, Heat Load Evaluation for Data Acquisition and Analysis System    (DAAS) Replacement, Ver. 1.0
: DOEJ-HD1081750401
: DOEJ-HD1081976501-C001, Seismic Review of Impact of DCP H1081976501, Ver. 1.0
-M001, Heat Load Evaluation for Data Acquisition and Analysis System    (DAAS) Replacement, Ver. 1.0
: DOEJ-HD2072720601-M001, Evaluation of Replacement Heat Exchanger 2G41-B001
: DOEJ-HD1081976501
-C001, Seismic Review of Impact of DCP H1081976501, Ver. 1.0
: DOEJ-HD2072720601
-M001, Evaluation of Replacement Heat Exchanger 2G41
-B001
: Thermal Performance, Ver. 1.0
: Thermal Performance, Ver. 1.0
: DOEJ-HD2072720601-M001, Evaluation of NRC Regulatory Guide 1.26 Classification for
: DOEJ-HD2072720601
-M001, Evaluation of NRC Regulatory Guide 1.26 Classification for  
: 2G41-B001 Heat Exchanger, Ver. 1.0
: 2G41-B001 Heat Exchanger, Ver. 1.0
: DOEJ-HD2080067101-M003, Evaluation of Platinum coating on Two-Stage Safety Relief Valve
: DOEJ-HD2080067101
: Discs, dated 12/08/11
-M003, Evaluation of Platinum coating on Two
: DOEJ-HRC101439201-M003, Evaluate the Effect of 97F Plant Service Water to the Units 1  
-Stage Safety Relief Valve Discs, dated 12/08/11
: Attachment   and 2 Emergency Diesel Generator Heat Exchangers, Ver. 1.0
: DOEJ-HRC101439201
: DOEJ-HRC101439201-M004, Evaluate the Effect of 97F Plant Service Water to the Units 1   and 2 Plant Service Water and Residual Heat Removal Service Water Pump Motor Coolers,
-M003, Evaluate the Effect of 97F Plant Service Water to the Units 1  
: Attachment and 2 Emergency Diesel Generator Heat Exchangers, Ver. 1.0
: DOEJ-HRC101439201
-M004, Evaluate the Effect of 97F Plant Service Water to the Units 1
and 2 Plant Service Water and Residual Heat Removal Service Water Pump Motor Coolers,
: Ver. 1.0
: Ver. 1.0
: ED 1081709901, Plateau Item Status, Group Report of 50.59 Qualifications for Originators of   the ED
: ED 1081709901, Plateau Item Status, Group Report of 50.59 Qualifications for Originators of the ED
: EE-0380-0029-0806, MPR specification and equivalency of replacement items Engineering Change Request (ECR) No 363, dated 10/11/04
: EE-0380-0029-0806, MPR specification and equivalency of replacement items Engineering Change Request (ECR) No 363, dated 10/11/04
: ES-MIS-145, Materials and Inspection Services, 10CFR 50.55a Evaluation, Ver. 1.0 Evaluation for Reactor Core Shroud Relief Request (TAC No. MD6396), dated 3/26/08 FCR049, Replacement of Recirculation MG sets with adjustable speed drives, Ver. 6.0 FCR058, Replacement of Recirculation MG sets with adjustable speed drives, Ver. 6.0 Fleet-DCM-2013, Nuclear Oversight Audit of Design Changes and Modifications,    dated 03/13/13 Focused Area Self-Assessment - Plant Site Design Process Execution, dated 07/26/12 Focused Area Self-Assessment - 50.59/Modifications Inspection, Ver. 1
: ES-MIS-145, Materials and Inspection Services, 10CFR 50.55a Evaluation, Ver. 1.0
: GEH 0000-0126-6532-R1, Ultimate Heat Sink Temperature Increase to 97F Impact on DBA-
: Evaluation for Reactor Core Shroud Relief Request (TAC No. MD6396), dated 3/26/08
: LOCA Analysis and DW Equipment Qualification Analysis (S75211), Rev. 1 H-DCM-2011, Fleet Oversight Audit of Design Changes and Modifications, dated 03/31/11 Hatch 1& 2, Technical Requirements Manual, Unit 1-Version 91, Unit 2, Ver. 93 Hatch UFSAR Section 18.2, Overhead Crane and Refueling Platform Inspections, Rev. 31 Hatch UFSAR, Unit 1, Chapter 14, Safety Analysis, refers to
: FCR049, Replacement of Recirculation MG sets with adjustable speed drives, Ver. 6.0
: HNP-2-FSAR-15A, Section
: FCR058, Replacement of Recirculation
: MG sets with adjustable speed drives, Ver. 6.0
: Fleet-DCM-2013, Nuclear Oversight Audit of Design Changes and Modifications,    dated 03/13/13
: Focused Area Self-Assessment
- Plant Site Design Process Execution, dated 07/26/12 Focused Area Self-Assessment
- 50.59/Modifications Inspection, Ver. 1
: GEH 0000-0126-6532-R1, Ultimate Heat Sink Temperature Increase to 97F Impact on DBA
-
: LOCA Analysis and DW Equipment Qualification Analysis (S75211), Rev. 1
: H-DCM-2011, Fleet Oversight Audit of Design Changes and Modifications, dated 03/31/11
: Hatch 1& 2, Technical Requirements Manual, Unit 1
-Version 91, Unit 2, Ver. 93
: Hatch UFSAR Section 18.2, Overhead Crane and Refueling Platform Inspections, Rev. 31
: Hatch UFSAR, Unit 1, Chapter 14, Safety Analysis, refers to HNP
-2-FSAR-15A, Section  
: 15A.5.6.3 RHRSW Line Cracks, Rev. 30
: 15A.5.6.3 RHRSW Line Cracks, Rev. 30
: HNP-1-FSAR-3, Section 3.3, Reactor Internals Mechanical Design, Rev. 19
: HNP-1-FSAR-3, Section 3.3, Reactor Internals Mechanical Design, Rev. 19
: HNP-1-FSAR-10, Section 10.18, Equipment Cooling System, Rev. 30
: HNP-1-FSAR-10, Section 10.18, Equipment Cooling System, Rev. 30
: HNP-1-FSAR-C, Appendix "C", Section C.3, Rev. 19
: HNP-1-FSAR-C, Appendix "C", Section C.3, Rev. 19
: HNP-1-FSAR-C, Table C.3-1, Sheet 2 of 24, Rev. 19
: HNP-1-FSAR-C, Table C.3
: HNP-2-FSAR-4, Section 4.2.2, Reactor Core Support Structures and Internals Mechanical
-1, Sheet 2 of 24, Rev. 19
: Design, Rev. 29 LDCR 2004-035, Licensing Document Change Request, Ver. 1.1 LDCR 2008-020, Licensing Document Change Request, Ver. 1.0
: HNP-2-FSAR-4, Section 4.2.2, Reactor Core Support Structures and Internals Mechanical Design, Rev. 29
: LDCR 2008-021, Licensing Document Change Request, Ver. 1.0 LDCR 2008-045, Heavy Loads Movement Conforming FSAR Change, dated 8/14/08 LDCR 2009-028, Licensing Document Change Request, Ver. 1.0 Letter to U.S. Nuclear Regulatory Commission, Subject: Edwin I. Hatch Nuclear Plant Unit 1
: LDCR 2004-035, Licensing Document Change Request, Ver. 1.1
: SVEA-96 Optima2 Lead Use Fuel Assemblies, dated 5/25/10 MATWEB Properties of AISI 1018 Steel, Cold Drawn, dated 1/20/11 MATWEB Properties of AISI 1019 Steel, Cold Drawn, dated 1/20/11 MATWEB Properties of AISI 1021 Steel, Cold Drawn, dated 1/20/11 MATWEB Properties of AISI 1030 Steel, As Rolled, dated 8/29/12
: LDCR 2008-020, Licensing Document Change Request, Ver.
: 1.0
: LDCR 2008-021, Licensing Document Change Request, Ver.
: 1.0 LDCR 2008-045, Heavy Loads Movement Conforming FSAR Change, dated 8/14/08
: LDCR 2009-028, Licensing Document Change Request, Ver. 1.0
: Letter to U.S. Nuclear Regulatory Commission, Subject: Edwin I. Hatch Nuclear Plant Unit 1
: SVEA-96 Optima2 Lead Use Fuel Assemblies, dated  
: 5/25/10 MATWEB Properties of AISI 1018 Steel, Cold Drawn, dated 1/20/11
: MATWEB Properties of AISI 1019 Steel, Cold Drawn, dated 1/20/11
: MATWEB Properties of AISI 1021 Steel, Cold Drawn, dated 1/20/11
: MATWEB Properties of AISI 1030 Steel, As Rolled, dated 8/29/12
: MC-H-09-0020, Anchorage Modification, Rev. 0
: MC-H-09-0020, Anchorage Modification, Rev. 0
: MC-H-09-0044, Fuse/fuse Coordination, Rev. 0
: MC-H-09-0044, Fuse/fuse Coordination, Rev. 0
Line 191: Line 315:
: CFR 50.59 Implementation, Rev. 1
: CFR 50.59 Implementation, Rev. 1
: NEI 98-03, Guidelines for Updating Final safety Analysis reports, Rev. 1
: NEI 98-03, Guidelines for Updating Final safety Analysis reports, Rev. 1
: NL-07-2242, SNC Letter to USNRC, Edwin I. Hatch Nuclear plant Unit No. 1, Response to NRC
: NL-07-2242, SNC Letter to USNRC, Edwin I. Hatch Nuclear plant Unit No. 1, Response to NRC  
: Request for Additional Information Regarding Modification of the Core Shroud Stabilizer
: Request for Additional Information Regarding Modification of the Core Shroud Stabilizer Assemblies, dated 12/18/07
: Assemblies, dated 12/18/07
: NL-08-0350, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant, Core Shroud Stabilizer Assembly Update, dated 3/7/08
: NL-08-0350, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant, Core Shroud Stabilizer
: NL-08-0512, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant
: Assembly Update, dated 3/7/08
: Attachment
: NL-08-0512, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant Attachment QFRC2012-004, Hatch Equipment Qualification Change Package, Ver. 1.0 QFRC2012-005, Hatch Equipment Qualification Change Package, Ver. 1.0 RER
: QFRC2012-004, Hatch Equipment Qualification Change Package, Ver. 1.0
: C070255901, Hatch Thermal Overload Heater Evaluation S-56787, Equipment qualification report of Westinghouse/Cutler-Hammer 50DHP-
: QFRC2012-005, Hatch Equipment Qualification Change Package, Ver. 1.0
: VR250U/1200 AMP replacement circuit breakers for safety application S-57861, DX1000/2000 Seismic Test Report, Ver. 2.0 S-58360, E.I. Hatch Nuclear Plant- Unit No-1, Shroud Repair Hardware Design Specification,
: RER
: Ver. 1.0 S-58361, E.I. Hatch Nuclear Plant- Unit No-1, Shroud Repair Hardware Modification Design
: C070255901, Hatch Thermal Overload Heater Evaluation
: Specification Data Sheet, Ver. 2.0 S-58361, E.I. Hatch Nuclear Plant- Unit No-1, Shroud Repair Parts List, Ver. 2.0 S-58637, Seismic Qualification Report
: S-56787, Equipment qualification report of Westinghouse/Cu tler-Hammer 50DHP
: TRP 5932 1" Square Body, 1" Y-Pattern, and 2" Y-
-
: VR250U/1200 AMP replacement circuit breakers for safety application
: S-57861, DX1000/2000 Seismic Test Report, Ver. 2.0
: S-58360, E.I. Hatch Nuclear Plant
- Unit No-1, Shroud Repair Hardware Design Specification,
: Ver. 1.0 S-58361, E.I. Hatch Nuclear Plant
- Unit No-1, Shroud Repair Hardware Modification Design Specification Data Sheet, Ver. 2.0
: S-58361, E.I. Hatch Nuclear Plant- Unit No-1, Shroud Repair Parts List, Ver. 2.0
: S-58637, Seismic Qualification Report
: TRP 5932 1" Square Body, 1" Y
-Pattern, and 2" Y
-
: Pattern Bolted Bonnet Closure Solenoid Operated Valves, dated 12/08/10
: Pattern Bolted Bonnet Closure Solenoid Operated Valves, dated 12/08/10
: SCNH-99-443, Seismic Evaluation of 1H21-P050, Rev. 0
: SCNH-99-443, Seismic Evaluation of 1H21
: SCNH-10-064, Design Basis Seismic Qualification for MCC 1R24-S022, Ver. 1
-P050, Rev. 0
: Specification
: SCNH-10-064, Design Basis Seismic Qualification for MCC 1R24
: NP-89001, Specification for Replacement Fuel Pool Cooling Heat Exchangers,
-S022, Ver. 1  
: Ver. 3.0 TS Bases, B3.4.7, Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown,
: Specification NP
: Rev. 15 TS Bases, B3.7.1, Residual Heat Removal Service Water (RHRSW) System, Rev. 0 USNRC Information Notice 96-17, Reactor Operation Inconsistent with the Updated Final Safety
-89001, Specification for Replacement Fuel Pool Cooling Heat Exchangers, Ver. 3.0 TS Bases, B3.4.7, Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown,
: Analysis Report, dated 3/18/96
: Rev. 15 TS Bases, B3.7.1, Residual Heat Removal Service Water (RHRSW) System, Rev. 0
: USNRC NUREG 0612, Control of Heavy Loads, Resolution of Generic Technical Activity A-36 USNRC Regulatory Guide 1.181, Content of the Updated Final Safety Analysis Report in
: USNRC Information Notice 96
: Accordance with 10
-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report, dated 3/18/96  
: CFR 50.71(e), dated 9/24/99
: USNRC NUREG 0612, Control of Heavy Loads, Resolution of Generic Technical Activity A
: USNRC Regulatory Information Summary 2005-25, Supplement 1
-36 USNRC Regulatory Guide
: Modifications DCP1071694001, Modification to Isolate Unit 1 Protected Service Water from Turbine Building,
: 1.181, Content of the Updated Final Safety Analysis Report in Accordance with 10
: Rev. 0 DCP1072721101, Reroute Cables out of Fire Area 0014, Ver. 3.0 DCP1081976501, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts,
: CFR 50.71(e), dated 9/24/99  
: Ver. 2.0 DCP1092321101, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022
: USNRC Regulatory Information Summary 2005
: Cubicles 4A, 6A, and 9C, Ver. 2.0 DCP1101786501, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050,
-25, Supplement 1
: Ver. 1.0 DCP2039000201, 4.16kV Breaker Replacement, Ver. 1.1  
: Modifications
: DCP 1071694001
, Modification to Isolate Unit 1 Protected Service Water from Turbine Building,
: Rev. 0 DCP 1072721101
, Reroute Cables out of Fire Area 0014, Ver. 3.0
: DCP 1081976501
, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts,
: Ver. 2.0 DCP1092321101
, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022
: Cubicles 4A, 6A, and 9C, Ver. 2.0
: DCP 1101786501
, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050,
: Ver. 1.0 DCP 2039000201
, 4.16kV Breaker Replacement, Ver. 1.1  
===Procedures===
===Procedures===
: 34SV-SUV-016-1, Cold Shutdown Valve Operability, Ver. 12.1 42FH-ERP-001-0, Control Rod Blade Unlatching, Installation, Removal and Exchange, Ver. 8.0 42IT-TET-014-IS, Safeguard equipment Cooler Data, Revision 0 ED1, dated 1/29/02 42SP-08-01-09-OW-1-1, Functional Test for
: 34SV-SUV-016-1, Cold Shutdown Valve Operability, Ver. 12.1
: DCP 1072721101 - Reroute Cables out of the Fire
: 2FH-ERP-001-0, Control Rod Blade Unlatching, Installation, Removal and Exchange, Ver. 8.0
: Area 0014, Ver. 1.1 42SV-TET-001-0, LLRT Testing Methodology, Ver. 7.3 42SV-TET-001-1, Primary Containment Type B and Type C Leak Rate Testing, Ver. 24.1 51GM-MLH-004-0, NUREG 0612 Heavy Load Movement, Rev. 21.9
: 2IT-TET-014-IS, Safeguard equipment Cooler Data, Revision 0 ED1, dated 1/29/02
: DI-ENG-06-0893, Southern Nuclear Plant, E. I. Hatch Design Change Package (DCP)
: 2SP-08-01-09-OW-1-1, Functional Test for
: DCP 1072721101  
- Reroute Cables out of the Fire Area 0014, Ver. 1.1
: 2SV-TET-001-0, LLRT Testing Methodology, Ver. 7.3
: 2SV-TET-001-1, Primary Containment Type B and Type C Leak Rate Testing, Ver. 24.1
: 51GM-MLH-004-0, NUREG 0612 Heavy Load Movement, Rev. 21.9
: DI-ENG-06-0893, Southern Nuclear Plant, E. I. Hatch Design Change Package (DCP)  
: Implementation User's Guide, Ver. 3.0
: Implementation User's Guide, Ver. 3.0
: NL-006-003, SNC Nuclear Licensing Instruction, Outgoing NRC Correspondence, Ver. 1.0  
: NL-006-003, SNC Nuclear Licensing Instruction, Outgoing NRC Correspondence, Ver. 1.0  
: Attachment
: Attachment
: NL-006-GL04, SNC Nuclear Licensing Guideline, Guidelines for Verification of Submittals,
: NL-006-GL04, SNC Nuclear Licensing Guideline, Guidelines for Verification of Submittals,
Line 234: Line 388:
: NMP-AD-012, Operability Determinations and Functionality Assessments, Ver. 12.0
: NMP-AD-012, Operability Determinations and Functionality Assessments, Ver. 12.0
: NMP-ES-034, Equivalency Determinations, Ver. 14.3
: NMP-ES-034, Equivalency Determinations, Ver. 14.3
: NMP-ES-034-GL01, Equivalency Determinations, Engineering Work Order Processing, Ver. 2.2
: NMP-ES-034-GL01, Equivalency Determinations, Engineering Work Order Processing
, Ver. 2.2
: NMP-ES-038-GL02, Electrical Design Guideline, Ver. 1.0  
: NMP-ES-038-GL02, Electrical Design Guideline, Ver. 1.0  
===Work Orders===
===Work Orders===
: SNC441401
: SNC441401 WO1042453001
: WO1042453001
: WO1071694003
: WO1071694003
: WO1072721105
: WO1072721105
: WO1081709910
: WO1081709910
: WO1081709918
: WO1081709918  
: WO1081709922
: WO1081709922
: WO2039000201 WOC070255901  
: WO2039000201
: WOC070255901  
===Condition Reports===
===Condition Reports===
generated as a result of the inspection
generated as a result of the inspection
: CR636366, Fire door 1L48-C31 sign, dated 5/8/13
: CR636366 , Fire door 1L48
: CR636368, Fire door 1L48-C31 magnet, dated 5/8/13
-C31 sign, dated 5/8/13
: CR636368 , Fire door 1L48
-C31 magnet, dated 5/8/13
: CR637655,
: CR637655,
: NRC 50.59/Modification Inspection request, dated 5/10/13
: NRC 50.59/Modification Inspection request, dated 5/10/13
: CR640166, NRC finds minor violation of 10
: CR640166, NRC finds minor violation of 10
: CFR 50.71(e) for LDCR 2004-22, dated 5/15/13
: CFR 50.71(e) for LDCR 2004
-22, dated 5/15/13
: CR640204, NRC finds minor violation of 10
: CR640204, NRC finds minor violation of 10
: CFR 50.71(e) for LDCR 2004-22, dated 5/15/13
: CFR 50.71(e) for LDCR 2004
: CR642894, Equivalency Determination
-22, dated 5/15/13
: CR642894 , Equivalency Determination
: C110573201 Lacks Answer, dated 5/21/13
: C110573201 Lacks Answer, dated 5/21/13
: CR643169, TRM not updated after
: CR643169 , TRM not updated after
: MDC 1101735601, dated 5/21/13
: MDC 1101735601, dated 5/21/13
: CR643571, NRC Question,
: CR643571, NRC Question,

Revision as of 19:36, 16 July 2018

IR 05000321-13-010, 05000366-13-010, 05/06/2013-05/23/2013, Edwin I. Hatch Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
ML13172A142
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 06/21/2013
From: Nease R L
NRC/RGN-II/DRS/EB1
To: Madison D R
Southern Nuclear Operating Co
References
IR-13-010
Download: ML13172A142 (12)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303

-1257 June 21, 2013 Mr. Dennis R. Madison Vice President Southern Nuclear Operating Company, In Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513

SUBJECT: EDWIN I. HATCH NUCLEAR PLANT

- NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/20 1 3 0 10 AND 05000366/20 1 3 0 1 0 Dear Mr. Madison

On Ma y 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and The enclosed inspection report documents the inspection results which were discussed on May 23, 2013 , with you and other members of your staf The inspection examined activities conducted under your license s as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license The team reviewed selected procedures and records, observed activities, and interviewed personne No findings were identified during this inspectio 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 Agency

-wide Document Access and Management System (ADAMS).

D. Madison 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html (the Public Electronic Reading Room).

Sincerely,RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.:

50-321, 50-366 License Nos.:

DPR-57 and NPF

-5

Enclosure:

Inspection Report 05000321/20130 10, 05000366/20130 1 0

w/attachment:

Supplemental Information

Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos.:

50-321, 50-366 License Nos.:

DPR-57 and NPF

-5 Report Nos.:

05000321/20 1 3 0 1 0 and 05000366/20 1 3 0 1 0 Licensee: Southern Nuclear Operating Company, In Facility: Edwin I. Hatch Nuclear Plant

Location: Baxley, Georgia 31513 Dates: May 6 - Ma y 2 3 , 2013 Inspectors:

E. Stamm, Senior Re ac t or Inspector (Team Leader)

A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)

Approved by:

Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000321/20 1 3 0 10, 05000366/20 1 3 0 1 0; 0 5/0 6/20 1 3-0 5/2 3/20 1 3; Edwin I. Hatch Nuclear Plant, Units 1 and 2

Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications Th is report cover s a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRC's program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG

-1649, "Reactor Oversight Process

," Revision 4.

No findings were identified during this inspection

.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity 1R1 7 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.1 7T)

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments

From May 6, 2013, through May 23 , 2013, the team reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 13 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:

the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issues requiring the changes, tests or experiments were resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation used to support the change was updated to reflect the change.

The team used, in part, Nuclear Energy Institute (NEI) 96

-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The team also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments

," dated March 2001.

This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications

From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:

Design Change Package (DCP) 1071694001

, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0 DCP 1072721101

, Reroute Cables out of Fire Area 0014, Ver. 3.0 DCP 1081976501

, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0 DCP 1092321101

, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.

DCP 1101786501

, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0 DCP 2039000201

, 4.16kV Breaker Replacement, Ver. 1.1 The modifications were selected based upon risk significance, safety significance, and complexity.

The team reviewed the modifications selected to determine if:

the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification ha d been adequately updated; the test documentation as required by the applicable test programs ha d been updated; and post-modification testing adequately verified system operability and/or functionality.

The team also used applicable industry standards to evaluate acceptability of the modifications and performed walk downs of accessible portions of the modifications. Documents reviewed are listed in the Attachment.

This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.

b. Findings

No findings were identified

.

4OA6 Meetings, Including Exit

On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

B. Anderson, Health Physics Manager
S. Beverly, Licensing Engineer
T. Crowell, Site Design Engineer
E. DelRosario, Site Design Engineer
D. Hines, Site Design Supervisor
B. Hulett, Site Design Manager
C. Lane, Engineering Director
K. Long, Operations Director
D. Madison, Vice President
C. McCall, Project Engineer
M. Peacock, Designer
C. Robinson, ASD Engineer
R. Seiter, Engineering Supervisor
B. Shuman, Engineering Programs Manager
S. Tipps, Licensing Supervisor
D. Vineyard, Plant Manager
T. Wells, Principal Engineer
E. Wonn, Senior Designer
F. Zayas, Site Design Supervisor

NRC personnel

E. Morris, Senior Resident Inspector, Hatch
D. Hardage, Resident Inspector, Hatch

LIST OF ITEMS

OPENED AND CLOSED

===Opened and

Closed===

None

LIST OF DOCUMENTS REVIEWED

CFR 50.59 Evaluations Licensing Document Change Request (LDCR) 2004-022 , TRM/FSAR Revision to Increase

RCIC Inboard Isolation Closure Time Acceptance Criteria, Ver. 1.0

Action Item

(AI)

2008200410 , RCIC Accident Temperature and Pressure, dated 2/14/2008
DCP 1040048401, Replacement of Reactor Recirculation Pump Motor Generator Sets with Adjustable Speed Drives, Ver. 9.0
DCP C062145201

, Westinghouse SVEA

-96 Optima2 Lead Use Assemblies, Ver. 1.0

Technical Evaluation (TE)
320565, LDCR for Detector Not Full in Rod Block Function, Rev. 0
AI 2007205079/RER
C072813201 , Movement of Heavy Loads Over Spent Fuel Pool , dated 1/9/08
Minor Design Change 1101735601

, HPCI Turbine Exhaust Drain Line Removal, Ver. 1.0

DCP SNC119724 , F River Temperature, dated 12/15/11
CFR 50.59 Screenings
DCP 2072720601

, Unit 2 FPCC System Heat Exchanger Replacement, Ver. 5.0

DCP 2080067101

, Main Steam

S/RV Replacement, Ver. 7.0
Equivalency Determination (ED)
C110573201, Valve Check 14", 300 lb

. Crane Swing Check Valve for RHR Service Water, Ver. 2.0

DCP SNC116958 , Remove Unit 2 HPCI Turbine Exhaust Drain Line, Ver. 1.0 ED SNC340426 , Relay K3 for EDG Exciter, Ver. 1.0
ED SNC341510 , Replacement Parts for General Electric Type AK

-25 Circuit Breaker, Ver. 1.0

ED SNC345576 , AVR Assembly for EDG Exciter, Ver. 1.0
DCP SNC429939 , Unit 2 Modified
3-stage SRV Replacement, Ver. 1.0
ED SNC452392, Hydraulic Actuator for MSIVs, Ver. 1.0
DCP 1042453001, Replacement Obsolete Recorders in Panel 1H11

-P614, Ver. 4.0

DCP 10727 24101, Replace Modified 36

-05 and 44-13 Local Power Range Monitors (LPRMs)

with standard LPRMs, Ver. 2.0

DCP 1081709901

, CRD Pump Room Cooler Cooling Coil Replacement, Ver. 2.0

DCP 1081750401, Data Acquisition and Analysis System (DAAS) Replacement, Ver. 3.0

Calculations

BH1-M-V004-B007-0001, Compartment Long

-Term Temperature Analysis, Ver. 10.0

BH2-M-0295, Compartment Long

-Term Temperature Analysis, Ver. 9.0

CA-1272, Aerofin Coil Selection Program Verification & Validation Documentation, Rev. 1
CA-1481, Aerofin Performance Verification for Aerofin Type "W" Coils, Rev. 1
CA-529, Aerofin Calculation File, CRD Pump Room Cooling Coil, Ver. 2
MC-H-09-019, Southern design Calculation, Cooling Unit Support, Ver. 0
S-53596-A, Shroud Repair Seismic Design Report Unit 1, Rev. 1
S-58367 , E. I. Hatch Nuclear Plant

- Unit No. 1, Shroud Repair replacement Upper Support Stress Analysis Report, Ver. 2.0

Condition Reports

CAR196955 CR2002004824
CR2008107088
CR558872
Attachment

Drawings

10-502, Reactor Recirculation System Logic Diagrams Sheet 1, Ver. 7.0
10-502, Reactor Recirculation System Logic Diagrams Sheet 2, Ver. 1.0
10-502, Reactor Recirculation System Logic Diagrams Sheet 3, Ver. 25.0
10-502, Logic Diagrams Legend and General Notes
H-10167, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Paths, Ver. 11.0 H-10171, Edwin I. Hatch Nuclear Plant, Unit 1 & 2 Refueling Floor Heavy Load Matrix, Weights and lifts, Ver. 5.0
H-11600, Unit 1 P&ID for Service Water and Diesel Generator, Sheet 2, Rev. 36
H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 2, Rev. 4
H-13388, Unit 1 Plant service water MO valves system diagram, Sheet 3, Rev. 5
H-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 14
H-26051, Edwin I. Hatch Nuclear Plant Unit 2, Reactor Building

- Plant Service Water System

P&ID, Ver. 47
HB-11004, Edwin I. Hatch Nuclear Plant Unit No. 1, RHR Service Water Outside Building ISI
Boundary Diagram, Ver. 5.0
HB-16173, Fission Products Monitoring System ISI Boundary Diagram, Ver. 2
HB-21039, Edwin I. Hatch Nuclear Plant Unit No. 2, RHR Service Water Outside Building ISI
Boundary Diagram, Ver. 11.0
HL-16173, Fission Products Monitoring System P&ID, Sheet 1, Ver. 3
S-15484, Reactor Shroud, Rev. 10
S-19638, Edwin I. Hatch Nuclear Plant Unit 1, Cooling Units Design Data, Ver. 2.0
S-28751, Edwin I. Hatch Nuclear Plant No. 2, Cast Steel Swing Check Valve, Ver. 2
S-53593, Shroud Repair Modifications & Installation

- Reactor, Sh

-2, Rev. 1

SA-A018, 20x5 MSIV Actuator, Sheets 1 thru 6 of 6, Rev. 7

Miscellaneous Documents

0000-0154-9209, SNC SRV Specification HM

-S-09-001 Review, Ver. 0

30035-99 Rev A, Wyle Laboratories Test Report, Volumes I thru VI
34SO-B31-001, Reactor Recirculation System, Ver. 43.2
CCN-H-09-0004, A46 Evaluation of Cable Spreading Room

-cable Tray Support Anchorage Against the Base Calculation SCNH

-92-034 (Version 4.0

), Ver. 1.0

Code Case N

-60-5, Cases of ASME Boiler and Pressure Vessel Code, dated 2/15/94

Copper Development Association, CDA Publication TN31, Copper

-Nickel 90/10 and 70/30

Alloys Technical Data , 1982
DOEJ-HD1072721101C001, Seismic Evaluations of Cables added to tray TL8

-10, Hatch Nuclear Plant U1, Ver. 1.0

DOEJ-HD1072721101

-E002, Adequacy of R23-S004-ES8-C06A Reroute cable out of Fire Area

0014, Ver. 1.0
DOEJ-HD1081750401

-J001, EMI/RFI Evaluation for HPCI/RCIC DAAS Equipment Replacement, Rev. 0

DOEJ-HD1081750401

-M001, Heat Load Evaluation for Data Acquisition and Analysis System (DAAS) Replacement, Ver. 1.0

DOEJ-HD1081976501

-C001, Seismic Review of Impact of DCP H1081976501, Ver. 1.0

DOEJ-HD2072720601

-M001, Evaluation of Replacement Heat Exchanger 2G41

-B001

Thermal Performance, Ver. 1.0
DOEJ-HD2072720601

-M001, Evaluation of NRC Regulatory Guide 1.26 Classification for

2G41-B001 Heat Exchanger, Ver. 1.0
DOEJ-HD2080067101

-M003, Evaluation of Platinum coating on Two

-Stage Safety Relief Valve Discs, dated 12/08/11

DOEJ-HRC101439201

-M003, Evaluate the Effect of 97F Plant Service Water to the Units 1

Attachment and 2 Emergency Diesel Generator Heat Exchangers, Ver. 1.0
DOEJ-HRC101439201

-M004, Evaluate the Effect of 97F Plant Service Water to the Units 1

and 2 Plant Service Water and Residual Heat Removal Service Water Pump Motor Coolers,

Ver. 1.0
ED 1081709901, Plateau Item Status, Group Report of 50.59 Qualifications for Originators of the ED
EE-0380-0029-0806, MPR specification and equivalency of replacement items Engineering Change Request (ECR) No 363, dated 10/11/04
ES-MIS-145, Materials and Inspection Services, 10CFR 50.55a Evaluation, Ver. 1.0
Evaluation for Reactor Core Shroud Relief Request (TAC No. MD6396), dated 3/26/08
FCR049, Replacement of Recirculation MG sets with adjustable speed drives, Ver. 6.0
FCR058, Replacement of Recirculation
MG sets with adjustable speed drives, Ver. 6.0
Fleet-DCM-2013, Nuclear Oversight Audit of Design Changes and Modifications, dated 03/13/13
Focused Area Self-Assessment

- Plant Site Design Process Execution, dated 07/26/12 Focused Area Self-Assessment

- 50.59/Modifications Inspection, Ver. 1

GEH 0000-0126-6532-R1, Ultimate Heat Sink Temperature Increase to 97F Impact on DBA

-

LOCA Analysis and DW Equipment Qualification Analysis (S75211), Rev. 1
H-DCM-2011, Fleet Oversight Audit of Design Changes and Modifications, dated 03/31/11
Hatch 1& 2, Technical Requirements Manual, Unit 1

-Version 91, Unit 2, Ver. 93

Hatch UFSAR Section 18.2, Overhead Crane and Refueling Platform Inspections, Rev. 31
Hatch UFSAR, Unit 1, Chapter 14, Safety Analysis, refers to HNP

-2-FSAR-15A, Section

15A.5.6.3 RHRSW Line Cracks, Rev. 30
HNP-1-FSAR-3, Section 3.3, Reactor Internals Mechanical Design, Rev. 19
HNP-1-FSAR-10, Section 10.18, Equipment Cooling System, Rev. 30
HNP-1-FSAR-C, Appendix "C", Section C.3, Rev. 19
HNP-1-FSAR-C, Table C.3

-1, Sheet 2 of 24, Rev. 19

HNP-2-FSAR-4, Section 4.2.2, Reactor Core Support Structures and Internals Mechanical Design, Rev. 29
LDCR 2004-035, Licensing Document Change Request, Ver. 1.1
LDCR 2008-020, Licensing Document Change Request, Ver.
1.0
LDCR 2008-021, Licensing Document Change Request, Ver.
1.0 LDCR 2008-045, Heavy Loads Movement Conforming FSAR Change, dated 8/14/08
LDCR 2009-028, Licensing Document Change Request, Ver. 1.0
Letter to U.S. Nuclear Regulatory Commission, Subject: Edwin I. Hatch Nuclear Plant Unit 1
SVEA-96 Optima2 Lead Use Fuel Assemblies, dated
5/25/10 MATWEB Properties of AISI 1018 Steel, Cold Drawn, dated 1/20/11
MATWEB Properties of AISI 1019 Steel, Cold Drawn, dated 1/20/11
MATWEB Properties of AISI 1021 Steel, Cold Drawn, dated 1/20/11
MATWEB Properties of AISI 1030 Steel, As Rolled, dated 8/29/12
MC-H-09-0020, Anchorage Modification, Rev. 0
MC-H-09-0044, Fuse/fuse Coordination, Rev. 0
MC-H-10-0142, Appendix R Protective Coordination Study of 250/125V DC Circuits
NEI 96-07, Guidelines for 10
CFR 50.59 Implementation, Rev. 1
NEI 98-03, Guidelines for Updating Final safety Analysis reports, Rev. 1
NL-07-2242, SNC Letter to USNRC, Edwin I. Hatch Nuclear plant Unit No. 1, Response to NRC
Request for Additional Information Regarding Modification of the Core Shroud Stabilizer Assemblies, dated 12/18/07
NL-08-0350, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant, Core Shroud Stabilizer Assembly Update, dated 3/7/08
NL-08-0512, SNC Letter to USNRC, Edwin I. Hatch Nuclear Plant
Attachment
QFRC2012-004, Hatch Equipment Qualification Change Package, Ver. 1.0
QFRC2012-005, Hatch Equipment Qualification Change Package, Ver. 1.0
RER
C070255901, Hatch Thermal Overload Heater Evaluation
S-56787, Equipment qualification report of Westinghouse/Cu tler-Hammer 50DHP

-

VR250U/1200 AMP replacement circuit breakers for safety application
S-57861, DX1000/2000 Seismic Test Report, Ver. 2.0
S-58360, E.I. Hatch Nuclear Plant

- Unit No-1, Shroud Repair Hardware Design Specification,

Ver. 1.0 S-58361, E.I. Hatch Nuclear Plant

- Unit No-1, Shroud Repair Hardware Modification Design Specification Data Sheet, Ver. 2.0

S-58361, E.I. Hatch Nuclear Plant- Unit No-1, Shroud Repair Parts List, Ver. 2.0
S-58637, Seismic Qualification Report
TRP 5932 1" Square Body, 1" Y

-Pattern, and 2" Y

-

Pattern Bolted Bonnet Closure Solenoid Operated Valves, dated 12/08/10
SCNH-99-443, Seismic Evaluation of 1H21

-P050, Rev. 0

SCNH-10-064, Design Basis Seismic Qualification for MCC 1R24

-S022, Ver. 1

Specification NP

-89001, Specification for Replacement Fuel Pool Cooling Heat Exchangers, Ver. 3.0 TS Bases, B3.4.7, Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown,

Rev. 15 TS Bases, B3.7.1, Residual Heat Removal Service Water (RHRSW) System, Rev. 0
USNRC Information Notice 96

-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report, dated 3/18/96

USNRC NUREG 0612, Control of Heavy Loads, Resolution of Generic Technical Activity A

-36 USNRC Regulatory Guide

1.181, Content of the Updated Final Safety Analysis Report in Accordance with 10
CFR 50.71(e), dated 9/24/99
USNRC Regulatory Information Summary 2005

-25, Supplement 1

Modifications
DCP 1071694001

, Modification to Isolate Unit 1 Protected Service Water from Turbine Building,

Rev. 0 DCP 1072721101

, Reroute Cables out of Fire Area 0014, Ver. 3.0

DCP 1081976501

, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts,

Ver. 2.0 DCP1092321101

, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022

Cubicles 4A, 6A, and 9C, Ver. 2.0
DCP 1101786501

, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050,

Ver. 1.0 DCP 2039000201

, 4.16kV Breaker Replacement, Ver. 1.1

Procedures

34SV-SUV-016-1, Cold Shutdown Valve Operability, Ver. 12.1
2FH-ERP-001-0, Control Rod Blade Unlatching, Installation, Removal and Exchange, Ver. 8.0
2IT-TET-014-IS, Safeguard equipment Cooler Data, Revision 0 ED1, dated 1/29/02
2SP-08-01-09-OW-1-1, Functional Test for
DCP 1072721101

- Reroute Cables out of the Fire Area 0014, Ver. 1.1

2SV-TET-001-0, LLRT Testing Methodology, Ver. 7.3
2SV-TET-001-1, Primary Containment Type B and Type C Leak Rate Testing, Ver. 24.1
51GM-MLH-004-0, NUREG 0612 Heavy Load Movement, Rev. 21.9
DI-ENG-06-0893, Southern Nuclear Plant, E. I. Hatch Design Change Package (DCP)
Implementation User's Guide, Ver. 3.0
NL-006-003, SNC Nuclear Licensing Instruction, Outgoing NRC Correspondence, Ver. 1.0
Attachment
NL-006-GL04, SNC Nuclear Licensing Guideline, Guidelines for Verification of Submittals,
Ver. 1.0
NMP-AD-008, Applicability Determinations, Ver. 15.2
NMP-AD-010, 10
CFR 50.59 Screenings and Evaluations, Ver. 11.0
NMP-AD-012, Operability Determinations and Functionality Assessments, Ver. 12.0
NMP-ES-034, Equivalency Determinations, Ver. 14.3
NMP-ES-034-GL01, Equivalency Determinations, Engineering Work Order Processing

, Ver. 2.2

NMP-ES-038-GL02, Electrical Design Guideline, Ver. 1.0

Work Orders

SNC441401 WO1042453001
WO1071694003
WO1072721105
WO1081709910
WO1081709918
WO1081709922
WO2039000201
WOC070255901

Condition Reports

generated as a result of the inspection

CR636366 , Fire door 1L48

-C31 sign, dated 5/8/13

CR636368 , Fire door 1L48

-C31 magnet, dated 5/8/13

CR637655,
NRC 50.59/Modification Inspection request, dated 5/10/13
CR640166, NRC finds minor violation of 10
CFR 50.71(e) for LDCR 2004

-22, dated 5/15/13

CR640204, NRC finds minor violation of 10
CFR 50.71(e) for LDCR 2004

-22, dated 5/15/13

CR642894 , Equivalency Determination
C110573201 Lacks Answer, dated 5/21/13
CR643169 , TRM not updated after
MDC 1101735601, dated 5/21/13
CR643571, NRC Question,
HNP-1
FSAR-C Section C.3, Vessel Internals, dated 5/22/13
CR643956,
NRC 50.59/Mods Inspection Question, MSIV Documentation, dated 5/22/13
CR644213,
NRC 2013 Mods Inspection Question, CRD Cooler Coils, dated 5/23/13
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