ML110040468
| ML110040468 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 12/22/2010 |
| From: | Arent G Tennessee Valley Authority |
| To: | Document Control Desk, Office of New Reactors |
| Spink T | |
| References | |
| BELLEFONTE.P02.NP, BELLEFONTE.P02.NP.3, TENNVALLEY, TENNVALLEY.SUBMISSION.6, +reviewedmmc1 | |
| Download: ML110040468 (171) | |
Text
CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT TABLE OF CONTENTS Section Title Page
1.1 INTRODUCTION
................................................................................. 1.1-1 1.1.1 PLANT LOCATION........................................................................ 1.1-1 1.1.5 SCHEDULE ................................................................................... 1.1-2 1.1.6.1 Regulatory Guide 1.70 ............................................................ 1.1-2 1.1.6.3 Text, Tables and Figures ......................................................... 1.1-2 1.1.6.5 Proprietary Information ............................................................ 1.1-3 1.1.6.6 Acronyms................................................................................. 1.1-3 1.1.7 COMBINED LICENSE INFORMATION......................................... 1.1-4 1.
1.8 REFERENCES
.............................................................................. 1.1-4 1.2 GENERAL PLANT DESCRIPTION ..................................................... 1.2-1 1.2.2 SITE DESCRIPTION ..................................................................... 1.2-1 1.2.3 PLANT ARRANGEMENT DESCRIPTION..................................... 1.2-3 1.3 COMPARISONS WITH SIMILAR FACILITY DESIGNS ...................... 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS..................... 1.4-1 1.4.1 APPLICANT - PROGRAM MANAGER ......................................... 1.4-1 1.4.2.8 Other Contractors .................................................................... 1.4-1 1.4.2.8.1 MACTEC Engineering and Consulting, Inc.............................. 1.4-2 1.4.2.8.2 William Lettis & Associates, Inc. .............................................. 1.4-2 1.4.2.8.3 Enercon Services, Inc.............................................................. 1.4-2 1.4.2.8.4 Burns & Roe Enterprises, Inc. ................................................. 1.4-2 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION ..... 1.5-1 1.6 MATERIAL REFERENCED................................................................. 1.6-1 1.7 DRAWINGS AND OTHER DETAILED INFORMATION...................... 1.7-1 1.7.2 PIPING AND INSTRUMENTATION DIAGRAMS .......................... 1.7-1 1.8 INTERFACES FOR STANDARD DESIGN.......................................... 1.8-1 1.9 COMPLIANCE WITH REGULATORY CRITERIA ............................... 1.9-1 1.9.1 REGULATORY GUIDES ............................................................... 1.9-1 1-i Revision 3
TABLE OF CONTENTS (Continued)
Section Title Page 1.9.1.1 Division 1 Regulatory Guides - Power Reactors ..................... 1.9-1 1.9.1.2 Division 4 Regulatory Guides - Environmental and Siting ....... 1.9-2 1.9.1.3 Division 5 Regulatory Guides - Materials and Plant Protection................................................................................. 1.9-2 1.9.1.4 Division 8 Regulatory Guides - Occupational Health............... 1.9-3 1.9.1.5 Combined License Information ................................................ 1.9-3 1.9.2 COMPLIANCE WITH STANDARD REVIEW PLAN (NUREG-0800) .............................................................................. 1.9-4 1.9.4.1 Review of NRC List of Unresolved Safety Issues and Generic Safety Issues ........................................................................... 1.9-4 1.9.4.2.3 New Generic Issues................................................................. 1.9-4 1.9.5.1.5 Station Blackout....................................................................... 1.9-6 1.9.5.2.15 Severe Accident Mitigation Design Alternatives ...................... 1.9-7 1.9.5.5 Operational Experience ........................................................... 1.9-7 1.
9.6 REFERENCES
.............................................................................. 1.9-8 1.10 NUCLEAR POWER PLANTS TO BE OPERATED ON MULTI-UNIT SITES........................................................................... 1.10-1 1.10.1 POTENTIAL CONSTRUCTION ACTIVITY HAZARDS ............... 1.10-1 1.10.2 POTENTIALLY IMPACTED SSCS AND LIMITING CONDITIONS FOR OPERATION ............................................... 1.10-2 1.10.3 MANAGERIAL AND ADMINISTRATIVE CONTROLS ................ 1.10-2 APP. 1A CONFORMANCE WITH REGULATORY GUIDES .................1A-1 APP. 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES ......................................................................1B-1 APP. 1AA CONFORMANCE WITH REGULATORY GUIDES .............. 1AA-1 1-ii Revision 3
LIST OF TABLES Number Title 1.1-201 Acronyms Used in the FSAR 1.1-202 Left Margin Annotations 1.1-203 Anticipated Schedule for Construction and Operation of Two AP1000 Units at the BLN Site 1.6-201 Additional Material Referenced 1.7-201 AP1000 System Designators and System Drawings 1.8-201 Summary of FSAR Departures from the DCD 1.8-202 COL Item Tabulation 1.8-203 Summary of FSAR Discussions of AP1000 Plant Interfaces 1.9-201 Regulatory Guide/FSAR Section Cross-References 1.9-202 Conformance with SRP Acceptance Criteria 1.9-203 Listing Of Unresolved Safety Issues And Generic Safety Issues 1.9-204 Generic Communications Assessment 1.10-201 Potential Hazards from Construction Activities 1.10-202 Hazards During Construction Activities 1.10-203 Managerial and Administrative Construction Controls 1-iii Revision 3
LIST OF FIGURES Number Title 1.1-201 Site Location Map 1.1-202 Site Layout 1.2-201 Annex Building General Arrangement Plan at Elevation 100-0 & 107-2 1-iv Revision 3
CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT
1.1 INTRODUCTION
This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
Add the following paragraphs to the end of DCD Section 1.1 SUP 1.1-1 This Final Safety Analysis Report (FSAR) incorporates the Design Control Document (DCD) (as identified in Table 1.6-201) for a simplified passive advanced light water reactor plant provided by Westinghouse Electric Company, the entity originally sponsoring and obtaining the AP1000 design certification documented in 10 CFR Part 52, Appendix D. Throughout this FSAR, the "referenced DCD" is the AP1000 DCD submitted by Westinghouse as Revision 17 including any supplemental material as identified in Table 1.6-201. Unless otherwise specified, reference to the DCD refers to Tier 2 information.
SUP 1.1-2 This Final Safety Analysis Report (FSAR) is hereby submitted under Section 103 of the Atomic Energy Act by the Tennessee Valley Authority (TVA) to the NRC as part of the application for two Class 103 combined licenses (COLs) to construct and operate two nuclear power plants under the provisions of 10 CFR Part 52 Subpart C.
1.1.1 PLANT LOCATION COL 2.1-1 Add the following text at the beginning of DCD Subsection 1.1.1:
Bellefonte Nuclear Plant Units 3 and 4 (hereafter referred to as BLN) are located in Jackson County, in Northeast Alabama, on a site previously utilized for construction of Bellefonte Nuclear Plant Units 1 and 2. Construction of these plants was halted prior to their completion. The BLN Site is situated on a peninsula bounded on the west by the Town Creek embayment and on the east by Guntersville Lake at Tennessee River mile 392, approximately 7 miles northeast of Scottsboro, Alabama (Reference 201).
1.1-1 Revision 3
Figure 1.1-201 identifies the site location. Figure 1.1-202 shows the plant arrangement within the site.
1.1.5 SCHEDULE Add the following text to the end of DCD Subsection 1.1.5:
COL 1.1-1 Table 1.1-203 displays the anticipated schedule for construction and operation of two AP1000 units at the BLN site. A site-specific construction plan and startup schedule will be provided to the NRC after issuance of the COL and when a positive decision has been made to construct the plant.
1.1.6.1 Regulatory Guide 1.70 Add the following text to the end of DCD Subsection 1.1.6.1.
SUP 1.1-6 This FSAR generally follows the AP1000 DCD organization and numbering. Some organization and numbering differences are adopted where necessary to include additional material, such as additional content identified in Regulatory Guide 1.206. Any exceptions are identified with the appropriate left margin annotation as discussed in Subsection 1.1.6.3 and Table 1.1-202.
1.1.6.3 Text, Tables and Figures Add the following text to the end of DCD Subsection 1.1.6.3.
SUP 1.1-3 Table 1.1-202 describes the left margin annotations used in this document to identify departures, supplementary information, COL items, and conceptual design information.
FSAR tables, figures, and references are numbered in the same manner as the DCD, but the first new FSAR item is numbered as 201, the second 202, the third 203, and consecutively thereafter. When a table, figure, or reference in the DCD is changed, the change is appropriately left margin annotated as identified above.
1.1-2 Revision 3
New appendices are included in the FSAR with double letter designations following the pertinent chapter (e.g., 12AA).
When it provides greater contextual clarity, an existing DCD table or figure is revised by adding new information to the table or figure and replacing the DCD table or figure with a new one in the FSAR. In this instance, the revised table or figure clearly identifies the information being added, and retains the same numbering as in the DCD, but the table or figure number is revised to end with the designation "R" to indicate that the table or figure has been revised and replaced.
For example, revised "Table 4.2-1" would become "Table 4.2-1R." New and revised tables and figures are labeled in the left margin as described in Table 1.1-202.
1.1.6.5 Proprietary Information Insert the following text to the end of DCD Subsection 1.1.6.5.
SUP 1.1-4 Some portions of this FSAR may be considered as proprietary, personal, or sensitive and withheld from public disclosure pursuant to 10 CFR 2.390 and Regulatory Issue Summary (RIS) 2005-026. Such material is clearly marked and the withheld material is separately provided for NRC review.
1.1.6.6 Acronyms Add the following text to the end of DCD Subsection 1.1.6.6.
SUP 1.1-5 Table 1.1-201 provides a list of acronyms used in the BLN FSAR in addition to the acronyms identified in DCD Table 1.1-1 and system designation identified in Table 1.7-201 and DCD Table 1.7-2.
1.1-3 Revision 3
1.1.7 COMBINED LICENSE INFORMATION Add the following text to the end of DCD Subsection 1.1.7.
COL 1.1-1 This COL item is addressed in Subsection 1.1.5.
Add the following after DCD Subsection 1.1.7.
1.
1.8 REFERENCES
201. United States Geological Survey (USGS) 1980, Hollywood Quadrangle, Alabama, 7.5 Minute Series Topographic Map.
1.1-4 Revision 3
TABLE 1.1-201 (Sheet 1 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition AADT Annual Average Daily Traffic AE Architect Engineer AFDD Accumulated Freezing Degree Days AGL Above Ground Level AMCOM U.S. Army Aviation and Missile Command AMSL Above Mean Sea Level ANSS Advanced National Seismograph System API Antecedent Precipitation Index AST Aboveground Storage Tank BHTV Borehole Televiewer BLN Bellefonte Nuclear Plant Units 3 and 4 BFN Browns Ferry Nuclear BFZ Blytheville Fault Zone BGS Below Ground Surface BL Bootheel Lineament BLNP Bellefonte Nuclear Plant Units 1 and 2 BPT Brownian Passage Time BRP Blue Ridge-Piedmont CAM Continuous Air Monitor CAV Cumulative Absolute Velocity CBA Cost Benefit Analysis CDF Core Damage Frequency CECC Central Emergency Control Center CEDE Committed Effective Dose Equivalent CEO Chief Executive Officer CERI Center for Earthquake Research and Information CEUS Central and Eastern United States CG Cloud-to-Ground CNO Chief Nuclear Officer COCORP Consortium for Continental Reflection Profiling COLA Combined License Application 1.1-5 Revision 3
TABLE 1.1-201 (Sheet 2 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition CPT Cone Penetrometer Test CSDRS Certified Seismic Design Response Spectrum DAC Derived Air Concentration DDE Deep Dose Equivalent DNAG Decade of North American Geology DOD Department of Defense DRS Design Response Spectra DSP Dam Safety Program EAB Exclusion Area Boundary ECFS East Coast Fault System EDR Environmental Data Resources Inc.
EDS Environmental Data Station EHOT Effluent Holdup Tank ENA Eastern North America ENS Emergency Notification System EOF Emergency Operations Facility EOP Emergency Operating Procedures EPC Engineering, Procurement & Construction EP-ITAAC Emergency Planning ITAAC EPRI-SOG Electric Power Research Institute - Seismicity Owners Group EPZ Emergency Planning Zone EQ Environmental Qualification EQMEL EQ Master Equipment List ERDS Emergency Response Data System ERO Emergency Response Organization ESP Early Site Permit ESW ESW - Electro-slag Weld ETSZ East Tennessee Seismic Zone FAA Federal Aviation Administration FAC Flow Accelerated Corrosion FEIS Final Environmental Impact Statement FEMA Federal Emergency Management Agency FERC Federal Energy Regulatory Commission 1.1-6 Revision 3
TABLE 1.1-201 (Sheet 3 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition FHA Fire Hazards Analysis FIRS Foundation Input Response Spectra FSAR Final Safety Analysis Report FTS Federal Telephone System GC Clayey Gravel GCVSZ Giles County, Virginia, Seismic Zone GFD Ground Flash Density GG&S Geotechnical, Geological and Seismic Evaluations GIS Geographic Information System GMAW Gas Metal Arc Welding GMRS Ground Motion Response Spectrum GSI Geological Strength Index GSU Main Step-up Transformer GTAW Gas Tungsten Arc Welding GTS Generic Technical Specifications HCLPF High Confidence, Low Probability of Failure HF High Frequency HiRAT Hi-Resolution Acoustic Televiewer HMR Hydrometeorological Report HPN Health Physics Network HV High Voltage IDLH Immediately Dangerous to Life and Health ITA Inspections, Tests, Analyses ITAAC Inspections, Tests, Analyses and Acceptance Criteria ITP Initial Test Program JTWG Joint Test Working Group LAN Local Area Network LBB Leak-Before-Break LER Licensee Event Report LF Low Frequency LIDAR Light Detection and Ranging LL Liquid Limit LLNL Lawrence Livermore National Laboratory 1.1-7 Revision 3
TABLE 1.1-201 (Sheet 4 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition LLW Low Level Waste LOPP Loss of Preferred Power MCL Management Counterpart Link MDD Standard Proctor Maximum Dry Density MPSSZ Middleton Place-Summerville Seismic Zone MSL Mean Sea Level NCDC National Climatic Data Center NCEER National Center for Earthquake Engineering Research NDCT Natural Draft Cooling Tower NDE Non-destructive Examination NEC Not Elsewhere Classified NEIC National Earthquake Information Center NERC North American Electric Reliability Corporation NESDIS National Environmental Satellite, Data, and Information Services N-Gamma Natural-Gamma NGD&C Nuclear Generation Development & Construction NIOSH National Institute for Occupational Safety and Health NLDN National Lightning Detection Network NMSZ New Madrid Seismic Zone NN New Madrid North Fault NNE New Madrid North Extension NOAA National Oceanographic and Atmospheric Administration NS New Madrid South Fault NSA Nuclear Safety Assurance NY-AL New York-Alabama OBE Operating Basis Earthquake OCL Operations Center Local Area Network ODCM Offsite Dose Calculation Manual OM Operations and Maintenance OMC Standard Proctor Optimum Moisture Content OPTV Optical Televiewer OSC Operations Support Center OSHA Occupational Safety and Health Administration 1.1-8 Revision 3
TABLE 1.1-201 (Sheet 5 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition PAW Plasma Arc Welding PCB Power Circuit-Breakers PCP Process Control Program PDE Preliminary Determination of Epicenters PF Performance Goal PGA Peak Ground Acceleration PGP Procedure Generation Package PI Plasticity Index PMCL Protective Measures Counterpart Link PMF Probable Maximum Flood PMH Probable Maximum Hurricane PMP Probable Maximum Precipitation PMWS Probable Maximum Windstorm PSHA Probabilistic Seismic Hazard Analysis PSIA Pounds Per Square Inch Absolute PSIG Pounds Per Square Inch Gauge PS-ITAAC Physical Security ITAAC PSO Power System Operations PT&O Plant Test and Operations PVC Polyvinyl Chloride PZR Pressurizer QAPD Quality Assurance Program Description QC Quality Control QMS Quality Management System RAT Reserve Auxiliary Transformer RCA Radiological Controlled Area RCP Reactor Coolant Pump RCTS Resonant Column / Torsional Shear RF Reelfoot Fault RHR Residual Heat Removal RIS Regulatory Issue Summary RO Reactor Operator RP Radiation Protection 1.1-9 Revision 3
TABLE 1.1-201 (Sheet 6 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition RPT Radiation Protection Technician RQD Rock Quality Designation RS RF Scarp RSCL Reactor Safety Counterpart Link RSO Release for System Operation RT Radiography Techniques RTD Resistance Temperature Detector RTDP Revised Thermal Design Procedure SAMDA Severe Accident Mitigation Design Alternatives SAMG Severe Accident Management Guidance SAW Submerged Arc Welding SCADA Supervisory Control and Data Acquisition SCBA Self Contained Breathing Apparatus SCPT Seismic Cone Penetrometer Test SDB Seismic Design Basis SDC Seismic Design Criteria SERC Southeastern Electric Reliability Council SEUSS Southeastern U.S. Seismic Network SEUSSN Southeast U.S. Seismic Network SGMP Steam Generator Management Program SHmax Maximum Horizontal Shear SLAR Side-Looking Airborne Radar SMAW Shielded Metal Arc Welding SNM Special Nuclear Material SOCH Simulated Open Channel Hydraulics SPT Standard Penetration Test SQN Sequoyah Nuclear SRO Senior Reactor Operator SSC Seismic Source Characterization SSC(s) Structure(s), System(s), and Component(s)
SSHAC Senior Seismic Hazard Analysis Committee SS-ITAAC Site-Specific ITAAC STA Shift Technical Advisor 1.1-10 Revision 3
TABLE 1.1-201 (Sheet 7 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition TC Thermocouple TEDE Total Effective Dose Equivalent TFI Technical/Facilitator/Integrator TGA Thermogravimetric Analysis TIP Trial Implementation Project TNT Trinitrotoluene TRM Tennessee River Mile TS Technical Specification(s)
TSD Thunderstorm Days per Year TSO Transmission System Operator TSP Transmission System Provider TVA Tennessee Valley Authority TVAN TVA Nuclear TZ Transverse Zone UAT Unit Auxiliary Transformer UCS Unconfined Compressive Strength UHRS Uniform Hazard Response Spectra UHS Ultimate Heat Sink USCS Unified Soil Classification System USDA U. S. Department of Agriculture USGS U.S. Geological Survey UST Underground Storage Tank UT Ultrasonic Techniques V&V Verification and Validation WAC Waste Acceptance Criteria WBN Watts Bar Nuclear WCSC Waterborne Commerce Statistics Center WEC Westinghouse Electric Company WHUT Waste Holdup Tank WLA William Lettis & Associates WN Natural Moisture Content YBP Years Before Present 1.1-11 Revision 3
TABLE 1.1-201 (Sheet 8 of 8)
SUP 1.1-5 ACRONYMS USED IN THE FSAR Acronym Definition ZIT Zone of Intense Thinning ZRA Zone of River Anomalies ZRA-S Zone of River Anomalies in South Carolina 1.1-12 Revision 3
SUP 1.1-3 TABLE 1.1-202 (Sheet 1 of 2)
LEFT MARGIN ANNOTATIONS MARGIN NOTATION DEFINITION AND USE STD DEP X.Y.Z-# FSAR information that departs from the generic DCD and is common for parallel applicants. Each Standard Departure is numbered separately at an appropriate level, e.g.,
STD DEP 9.2-1, or STD DEP 9.2.1-1 NPP DEP X.Y.Z-# FSAR information that departs from the generic DCD and is plant specific. NPP is replaced with a plant specific identifier. Each Departure item is numbered separately at an appropriate subsection level, e.g.,
NPP DEP 9.2-2, or NPP DEP 9.2.1-2 STD COL X.Y-# FSAR information that addresses a DCD Combined License Information item and is common to other COL applicants. Each COL item is numbered as identified in DCD Table 1.8-2 and FSAR Table 1.8-202, e.g.,
STD COL 4.4-1, or STD COL 19.59.10.5-1 NPP COL X.Y-# FSAR information that addresses a DCD Combined License Information item and is plant specific. NPP is replaced with a plant specific identifier. Each COL item is numbered as identified in DCD Table 1.8-2 and FSAR Table 1.8-202, e.g.,
NPP COL 4.4-1, or NPP COL 19.59.10.5-1 NPP CDI FSAR information that addresses DCD Conceptual or Design Information (CDI). Replacement design STD CDI information is generally plant specific; however, some may be common to other applicants. NPP is replaced with a plant specific identifier. STD is used if it is common. CDI information replacements are not numbered.
1.1-13 Revision 3
SUP 1.1-3 TABLE 1.1-202 (Sheet 2 of 2)
LEFT MARGIN ANNOTATIONS STD SUP X.Y-# FSAR information that supplements the material in the DCD and is common to other COL applicants. Each SUP item is numbered separately at an appropriate subsection level, e.g.,
STD SUP 1.10-1, or STD SUP 9.5.1-1 NPP SUP X.Y-# FSAR information that supplements the material in the DCD and is plant specific. NPP is replaced with a plant specific identifier. Each SUP item is numbered separately at an appropriate subsection level, e.g.,
NPP SUP 3.10-1, or NPP SUP 9.2.5-1 DCD FSAR information that duplicates material in the DCD.
Such information from the DCD is repeated in the FSAR only in instances determined necessary to provide contextual clarity.
1.1-14 Revision 3
TABLE 1.1-203 ANTICIPATED SCHEDULE FOR CONSTRUCTION AND COL1.1-1 OPERATION OF TWO AP1000 UNITS AT THE BLN SITE Activity Start(1)(2) Finish(1)(2) Duration UNIT 3 Early Procurement Activities 3rd Q 2009 -- --
Site Preparation 3rd Q 2011 3rd Q 2013 24 Months Commence Construction (Safety- 3rd Q 2013 related activities) -- --
Fuel Load, Commence Start-Up 3rd Q 2017 -- 6 Months UNIT 4 Early Procurement Activities 3rd Q 2010 -- --
Site Preparation 3rd Q 2012 3rd Q 2014 24 Months Commence Construction (Safety- 3rd Q 2014 related activities) -- --
Fuel Load, Commence Start-Up 3rd Q 2018 -- 6 Months Notes:
(1) Quarters shown are for government fiscal year.
(2) Activities that do not indicate a start or finish date are milestones, and represent the anticipated commencement (start) or completion (finish) of the activity.
1.1-15 Revision 3
1.2 GENERAL PLANT DESCRIPTION This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
1.2.2 SITE DESCRIPTION In Subsection 1.2.2 of the DCD, replace the information entitled "Site Plan" with the following text.
COL 2.1-1 COL 3.3-1 Site Plan COL 3.5-1 A typical site plan for a single unit AP1000 reference unit is shown in DCD Figure 1.2-2. The directions north, south, east, and west used in this description are the conventions used in the DCD for the orientation of AP1000 structures and equipment and differ from geographic north, south, east and west.
The site plan for BLN is shown on Figure 1.1-202. Principal structures and facilities, parking areas, roads, and transmission lines are illustrated. Orientation of the two AP1000 units is such that "plant north" faces 219 degrees from true north. Unless otherwise noted, directions in this subsection are based on true north. Similarly, design plant grade in the DCD is 100 feet (ft.), whereas the design plant grade for BLN is 628.6 ft.; therefore DCD elevations are to be increased by 528.6 ft. to be actual site elevations.
As stated in DCD Subsection 1.2.1.6.1, the power block complex consists of five principal building structures; the nuclear island, the turbine building, the annex building, the diesel generator building and the radwaste building. Each of these building structures is constructed on an individual basemat. The nuclear island consists of the containment building, the shield building, and the auxiliary building, all of which are constructed on a common basemat.
The power block complex for both units is within a common perimeter fence approximately 1588 ft. x 2425 ft. (88 ac.). Also contained within the perimeter fence is the maintenance building which is located directly northeast of Unit 3.
Access to the fenced area is accomplished either through the primary access portal east of the maintenance building or through the security access building south of Unit 4.
DCD Figure 1.2-3 provides a functional representation of the principal systems and components that are located in each of the key AP1000 buildings. This figure identifies major systems and components that are contained in these structures.
Each of the two main cooling tower-circulating water pump complexes consist of a natural draft cooling tower, a pump basin, circulating water pumps and associated piping. The cooling towers are located southwest of the reactors. The circulating 1.2-1 Revision 3
pumps are located near each cooling tower. The pumps circulate the cooling water from the pump basin to the main condensers and back to the respective cooling tower. Each complex uses a pre-cast concrete supply pipe and return pipe, both of which are below grade.
East of the perimeter area is the intake pumping station. This structure was originally built to support the cancelled Bellefonte Units 1 and 2.
The transformer area is located immediately adjacent to and southwest of the turbine building. The unit auxiliary transformers, the reserve auxiliary transformer and the main step-up transformers are located in this area. The main switchyard area is located to the southwest of Bellefonte Unit 3.
Situated between Units 3 and 4 and the cooling towers are the structures remaining from the cancelled Bellefonte Unit 1 and Unit 2 plants. There are no interfaces between these structures and the AP1000 units.
An administrative building is located outside of the perimeter fence northeast of Unit 3. This building houses management, administration and support functions for the site. The training and simulator buildings are located northeast of the perimeter area.
The gatehouse at the main gate controls ingress and egress to and from the site.
Parking facilities are provided adjacent to the administrative building and adjacent to the material receiving area. Additional parking for outage support personnel is provided to the east of the perimeter fence.
Road access to the site is from the north and from the south. The North Access Road connects to U.S. Highway 72 and the South Access Road connects to Jackson County Highway 33. An on-site road provides access to the Barge Unloading Facility, which is located southeast of the plants on the Guntersville Reservoir. Other on-site roads are provided, as necessary, to support plant operation, maintenance, security and other activities.
Rail access to the site is from the northwest. A spur line, which is owned and controlled by TVA, connects the site to a Norfolk Southern Railway Company mainline. Additional lines are provided on-site as necessary to allow movement of equipment and materials.
During construction, a heavy lift crane is used to place major pieces of equipment such as the turbine-generator, the reactor vessel, the steam generators, containment ring sections, large structural modules and other large or heavy equipment modules.
1.2-2 Revision 3
1.2.3 PLANT ARRANGEMENT DESCRIPTION DEP 18.8-1 Add the following information at the end of the first paragraph of DCD Subsection 1.2.3.
Figure 1.2-201 replaces DCD Figure 1.2-18 to reflect the relocation of the Operations Support Center.
1.2-3 Revision 3
1.3 COMPARISONS WITH SIMILAR FACILITY DESIGNS This section of the referenced DCD is incorporated by reference with no departures or supplements.
1.3-1 Revision 3
1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
1.4.1 APPLICANT - PROGRAM MANAGER Add the following paragraphs as the first two paragraphs in DCD Subsection 1.4.1:
SUP 1.4-1 The Tennessee Valley Authority (TVA) is the applicant for a Combined License for the BLN and will own and operate Units 3 and 4. TVA is one of the nations largest public power producers. TVA was established by Congress, in 1933, primarily to provide navigation, flood control, agricultural and industrial development and to promote the use of electric power in the Tennessee Valley region. TVA is wholly owned by the United States Government. Through 158 public power utilities, TVA supplies electricity to approximately 8.7 million people in the TVA service area.
TVA began building nuclear power plants in the 1960s and has operated nuclear power plants since 1974. Currently, TVA has three nuclear sites consisting of six operating units.
Add the following paragraphs to the end of DCD Subsection 1.4.1:
SUP 1.4-2 Contractors participating in the preparation of the COL Application are addressed in Subsection 1.4.2.8.
Not all participants have been identified at this time. In particular, the AP1000 NSSS provider, architect-engineer, and constructor have not yet contracted. This section of the FSAR will be revised to include information identifying the NSSS provider, the architect-engineer, and the constructor following the establishment of contracts for these purposes. This information will include descriptions of the technical qualifications of the NSSS provider, the architect-engineer, and the constructor, and address the division of responsibility among them and the operator.
Add the following new subsection after DCD Subsection 1.4.2.7:
SUP 1.4-3 1.4.2.8 Other Contractors Contractual relationships have been established with specialized consulting firms to assist in preparing the COL Application for BLN.
1.4-1 Revision 3
1.4.2.8.1 MACTEC Engineering and Consulting, Inc.
MACTEC Engineering and Consulting, Inc. is a leader in the engineering, environmental, and remedial construction industries and provides a full range of engineering consulting services to clients worldwide. These services include site development, planning and engineering design, construction phase services, environmental services, and facilities operations and maintenance services.
MACTEC Engineering and Consulting, Inc. has performed geotechnical field investigations and laboratory testing in support of the COL Application for BLN.
This includes performing standard penetration tests, obtaining core samples and rock cores, and installing ground water observation wells.
1.4.2.8.2 William Lettis & Associates, Inc.
William Lettis & Associates, Inc. is a consulting firm specializing in applied earth sciences and has extensive experience in earthquake-related services, engineering geology, and geotechnical services. The firm has conducted earth science investigations for a wide spectrum of clients and provides a range of services including detailed site characterization, assessment of capable tectonic features, seismic source zones, and probabilistic seismic hazard assessment studies.
William Lettis & Associates, Inc. has performed the investigations and analyses required to prepare the geology, seismology, and geotechnical engineering section of the COL Application for BLN. This includes investigating the subsurface materials present at the site, performing a comprehensive geotechnical exploration, and performing geophysical surveys to assess the dynamic response of soil and rock.
1.4.2.8.3 Enercon Services, Inc.
Enercon Services, Inc. is a diversified, multi-disciplined engineering services firm with extensive experience in providing services to the United States commercial nuclear power industry. The firms capabilities and expertise includes design engineering, regulatory compliance, environmental management, and management services.
Enercon Services, Inc. has provided engineering, management, and consulting services to prepare the COL Application for BLN. This included providing project management and engineering services, developing selected COL Application sections, and preparing the COL Application.
1.4.2.8.4 Burns & Roe Enterprises, Inc.
Burns & Roe Enterprises, Inc. is an architect-engineering firm with considerable nuclear expertise. The firm has provided design, construction management, and modernization services to a wide variety of domestic and foreign operating 1.4-2 Revision 3
utilities. Burns & Roe Enterprises, Inc. contributed to the design and installation of a number of commercial nuclear power plants. The firm has also been involved with the development of advanced light water reactors since their inception.
Burns & Roe Enterprises, Inc. has participated in document development, including preparation of the FSAR for the COL Application for BLN. This includes preparing topical reports and performing technical reviews of COL Application documents.
1.4-3 Revision 3
1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION This section of the referenced DCD is incorporated by reference with no departures or supplements.
1.5-1 Revision 3
1.6 MATERIAL REFERENCED This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
Add the following text to the end of DCD Section 1.6.
SUP 1.6-1 Table 1.6-201 provides a list of the various technical documents incorporated by reference in the FSAR in addition to those technical documents incorporated by reference in the AP1000 DCD.
1.6-1 Revision 3
Part 2, FSAR TABLE 1.6-201 1.6-1 ADDITIONAL MATERIAL REFERENCED ADAMS Author / FSAR Document Accession Report Number(a) Title Revision Section Transmittal Number Westinghouse / AP1000 Design Control Document 17 All September ML083230868 APP-GW-GL-700 2008 NEI 07-08A Generic FSAR Template Guidance for 0 12.1 October 2009 ML093220164 Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA)
NEI 07-03A Generic FSAR Template Guidance for 0 Appendix May 2009 ML091490684 Radiation Protection Program Description 12AA NEI 06-13A Template for an Industry Training Program 2 13.2 March 2009 ML090910554 Description NEI 07-02A Generic FSAR Template Guidance for 0 17.6 March 2008 ML080910149 Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52 1.6-2 Emergency Plan Bellefonte Nuclear Station Combined License 2 13.3 December ML100151002 Application Emergency Plan 2009 Cyber Security Plan Bellefonte Nuclear Plant Units 3 & 4 Cyber 0 13.6 August 2009 Not Applicable Security Plan (SUNSI)
QAPD TVA Bellefonte Units 3 and 4 Quality 1 17.5 January 2009 ML090290406 Assurance Program Description a) The NRC-accepted NEI documents identified by the A in the document number include the accepted template, the NRC safety evaluation, and corresponding responses to the NRC Requests for Additional Information. Only the accepted template is incorporated by reference. The remainder of the document is referenced but not incorporated into the FSAR.
(A) Denotes NRC approved document.
1.6-2 Revision 3
1.7 DRAWINGS AND OTHER DETAILED INFORMATION This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
1.7.2 PIPING AND INSTRUMENTATION DIAGRAMS Add the following text to the end of DCD Subsection 1.7.2.
SUP 1.7-1 Table 1.7-201 contains a list of piping and instrumentation diagrams (P&IDs) or system diagrams and the corresponding FSAR figure numbers that supplement the DCD.
1.7-1 Revision 3
TABLE 1.7-201 SUP 1.7-1 AP1000 SYSTEM DESIGNATORS AND SYSTEM DRAWINGS FSAR Designator System Section FSAR Figure CWS Circulating Water System 10.4.5 10.4-201 10.4-202 10.4-203 RWS Raw Water System 9.2.11 9.2-201 SWS Service Water System 9.2.1 9.2-202 ZBS Offsite Power System One 8.2 8.2-201 Line Diagram 1.7-2 Revision 3
1.8 INTERFACES FOR STANDARD DESIGN This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
Add the following paragraphs to the end of DCD Section 1.8.
SUP 1.8-1 Departures from the referenced DCD are summarized in Table 1.8-201.
Table 1.8-201 lists each departure and the FSAR section or subsection impacted.
SUP 1.8-2 DCD Table 1.8-2 presents Combined License Information for the AP1000. Items requiring COL Applicant or COL Holder action are presented in Table 1.8-202.
FSAR section(s) addressing these COL items are tabulated in this table. COL Holder items listed in Table 1.8-202 are regulatory commitments of the COL Holder and these actions will be completed as specified in the appropriate section of the referenced DCD. Completion of these COL Holder items is the subject of a Combined License Condition as presented in a separate document submitted as part of this COL application.
SUP 1.8-3 DCD Table 1.8-1 presents interface items for the AP1000. FSAR section(s) addressing these interface items are tabulated in Table 1.8-203.
1.8-1 Revision 3
TABLE 1.8-201 (Sheet 1 of 3)
SUP 1.8-1
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure FSAR Section or Number Departure Description Summary Subsection STD DEP 1.1-1 An administrative departure is established to 2.1.1 identify instances where the renumbering of 2.1.4 FSAR sections is necessary to effectively 2.2.1 include content consistent with Regulatory 2.2.4 Guide 1.206, as well as NUREG-0800.(a) 2.4.1 2.4.15 2.5 2.5.6 9.2.11 9.2.12 9.2.13 9.5.1.8 9.5.1.9 13.1 13.5 13.7 17.5 17.6 17.7 17.8 1.8-2 Revision 3
TABLE 1.8-201 (Sheet 2 of 3)
SUP 1.8-1
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure FSAR Section or Number Departure Description Summary Subsection BLN DEP 2.3-1 In Revision 17 of the DCD the EAB Table 1.9-202, atmospheric dispersion coefficients were 6.2.6 revised to values that did not bound the BLN Table 2.0-201 site-specific values. This departure provides Table 2.0-202 the evaluation associated with the BLN site- 6.2.5.1.2 specific parameter values. 6.5 Table 6.5-201 Table 14.3-202 15.0 15.0.3.2 Table 15.0-201 15.6.5.3.1.2 15.6.5.3.7.3 Table 15.6-201 Table 15.6-202 15A.3.1.3 15A.3.3 Table 15A-201 Table 15A-202 16.1 TS 5.5.8 TS B3.6.1 TS B3.6.2 BLN DEP 8.2-1 In Revision 17 of the DCD the transformer area Figure 1.1-202 was rearranged to simplify the design. The Figure 8.2-202 transformer area contains the main stepup transformers. This rearrangement is implemented for BLN Unit 4; however, it is not implemented for BLN Unit 3. BLN Unit 3 retains the transformer area arrangement as presented in Revision 16 of the DCD. The departure is for BLN Unit 3 only.
BLN DEP 9.2-1 The Service Water Cooling Tower blowdown 9.2.1.2.1 flow will only be routed to the Waste Water Retention Basin.
1.8-3 Revision 3
TABLE 1.8-201 (Sheet 3 of 3)
SUP 1.8-1
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure FSAR Section or Number Departure Description Summary Subsection BLN DEP 18.8- At Bellefonte, the Technical Support Center 18.8.3.5 1 (TSC) is not located in the control support area 18.8.3.6 (CSA) as identified in DCD 12.5.2.2 Subsection 18.8.3.5; the TSC location is as 12.3 described in the Emergency Plan. Additionally, 9A the Operations Support Center (OSC) is also 1.2 being moved from the location identified in DCD Subsections 18.8.3.6 and 12.5.2.2 and as identified on DCD figures in Subsections 1.2 and 12.3, and Appendix 9A; the OSC location is as described in the Emergency Plan.
a) The Departure is standard for AP1000 COLAs but the applicable FSAR Sections or Subsections may vary in the AP1000 Subsequent COLAs.
1.8-4 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 1 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 1.1-1 Construction and Startup Schedule 1.1.7 1.1.5 A 1.1.7 1.9-1 Regulatory Guide Conformance 1.9.1.5 1.9.1 A 1.9.1.1 1.9.1.2 1.9.1.3 1.9.1.4 1.9.1.5 Appendix 1A Appendix 1AA 1.9-2(a) Bulletins and Generic Letters 1.9.5.5 1.9.5.5 A 1.9-3(a) Unresolved Safety Issues and Generic Safety Table 1.9-2 1.9.4.1 A Issues 1.9.4.1 1.9.4.2.3 2.1-1 Geography and Demography 2.1.1 1.1.1 A 1.2.2 2.1 2.2-1 Identification of Site-specific Potential Hazards 2.2.1 2.2 A 2.3-1 Regional Climatology 2.3.6.1 2.3.1 A 2.3.6.1 1.8-5 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 2 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.3-2 Local Meteorology 2.3.6.2 2.3.2 A 2.3.6.2 2.3-3 Onsite Meteorological Measurements Program 2.3.6.3 2.3.3 A 2.3.6.3 2.3-4 Short-Term Diffusion Estimates 2.3.6.4 2.3.4 A 2.3.6.4 15.6.5.3.7.3 15A.3.3 2.3-5 Long-Term Diffusion Estimates 2.3.6.5 2.3.5 A 2.3.6.5 2.4-1 Hydrological Description 2.4.1.1 2.4.1 A 2.4.8 2.4.15.1 2.4-2 Floods 2.4.1.2 2.4.2 A 2.4.3 2.4.4 2.4.5 2.4.6 2.4.7 2.4.10 2.4.15.2 1.8-6 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 3 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.4-3 Cooling Water Supply 2.4.1.3 2.4.9 A 2.4.11 2.4.15.3 2.4-4 Groundwater 2.4.1.4 2.4.12.1 A 2.4.12.2 2.4.12.4 2.4.12.5 2.4.15.4 2.4-5 Accidental Release of Liquid Effluents into Ground 2.4.1.5 2.4.12.3 A and Surface Water 2.4.13 2.4.15.5 2.4-6 Flood Protection Emergency Operation Procedures 2.4.1.6 2.4.14 A 2.4.15.6 2.5-1 Basic Geologic and Seismic Information 2.5.1 2.5 A 2.5.1 2.5.2.1 2.5.2.1.1 2.5.2.1.2 2.5.4 2.5.4.6 2.5.6.1 1.8-7 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 4 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.5-2 Site Seismic and Tectonic Characteristics 2.5.2.1 2.5.2 A Information 2.5.2.1 2.5.2.1.1 2.5.2.1.2 2.5.2.2 2.5.2.3 2.5.2.4 2.5.2.5 2.5.2.6 2.5.4.9 2.5.6.2 2.5-3 Geoscience Parameters 2.5.2.3 2.5.2.6 A 2.5.4.11 2.5.6.3 2.5-4 Surface Faulting 2.5.3 2.5.3 A 2.5.6.4 1.8-8 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 5 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.5-5 Site and Structures 2.5.4.6.1 2.5.4 A 2.5.4.1 2.5.4.2.2.4 2.5.4.2.2.5 2.5.4.3.5 2.5.4.11 2.5.6.5 2.5-6 Properties of Underlying Materials 2.5.4.6.2 2.5.4.2.1 A 2.5.4.2.2 2.5.4.2.2.4 2.5.4.2.3 2.5.4.3 2.5.4.3.5 2.5.4.4 2.5.4.6.2 2.5.4.7 2.5.4.10.2 2.5.4.11 2.5.6.6 1.8-9 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 6 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.5-7 Excavation and Backfill 2.5.4.6.3 2.5.4.5 A 2.5.4.5.3 2.5.4.5.4 2.5.4.6.4 2.5.4.10.1 2.5.4.12 2.5.6.7 2.5-8 Ground Water Conditions 2.5.4.6.4 2.5.4.5.2.2 A 2.5.4.6 2.5.4.6.3 2.5.4.6.8 2.5-9 Liquefaction Potential 2.5.4.6.5 2.5.4.8 A 2.5.4.6.9 2.5-10 Bearing Capacity 2.5.4.6.6 2.5.4.10 A 2.5.4.11 2.5.6.10 2.5-11 Earth Pressures 2.5.4.6.7 2.5.4.10.5 A 2.5.6.11 1.8-10 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 7 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 2.5-12 Static and Dynamic Stability of Facilities 2.5.4.6.9 2.5.4.5.5 A 2.5.4.10.3 2.5.4.10.4 2.5.6.12 2.5-13 Subsurface Instrumentation 2.5.4.6.10 2.5.4.5.5 A 2.5.6.13 2.5-14 Stability of Slopes 2.5.5 2.5.5 A 2.5.6.14 2.5-15 Embankments and Dams 2.5.6 2.5.5 A 2.5.6.15 2.5-16 Settlement of Nuclear Island 2.5.4.6.11 2.5.4.10.4 A 2.5.6.16 3.3-1 Wind and Tornado Site Interface Criteria 3.3.3 1.2.2 A 2.2 2.2.1 3.3.1.1 3.3.2.1 3.3.2.3 3.3.3 3.5.1.5 3.5.1.6 1.8-11 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 8 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 3.4-1 Site-Specific Flooding Hazards Protective Measures 3.4.3 3.4.1.3 A 3.4.3 3.5-1 External Missile Protection Requirements 3.5.4 1.2.2 A 2.2 2.2.1 3.3.1.1 3.3.2.1 3.3.2.3 3.5.1.5 3.5.1.6 3.5.4 3.6-1 Pipe Break Hazards Analysis 3.6.4.1 3.6.4.1 H 3.6-4 Primary System Inspection Program for Leak- 3.6.4.4 3.6.4.4 A Before-Break Piping 3.7-1 Seismic Analysis of Dams 3.7.5.1 3.7.2.12 A 3.7.5.1 3.7-2 Post-Earthquake Procedures 3.7.5.2 3.7.4.4 A 3.7.5.2 3.7-3 Seismic Interaction Review 3.7.5.3 3.7.5.3 H 1.8-12 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 9 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 3.7-4 Reconciliation of Seismic Analyses of Nuclear Island 3.7.5.4 3.7.5.4 H Structures 3.7-5 Location of Free-Field Acceleration Sensor 3.7.5.5 3.7.4.2.1 A 3.7.5.5 3.9-2 Design Specification and Reports 3.9.8.2 3.9.8.2 H 3.9-3 Snubber Operability Testing 3.9.8.3 3.9.3.4.4 A 3.9.8.3 3.9-4 Valve Inservice Testing 3.9.8.4 3.9.6 A 3.9.6.2.2 3.9.6.2.4 3.9.6.2.5 3.9.6.3 3.9.8.4 3.9-5 Surge Line Thermal Monitoring 3.9.8.5 3.9.3.1.2 A 3.9.8.5 3.11-1 Equipment Qualification File 3.11.5 3.11.5 H 4.4-2 Confirm Assumptions for Safety Analyses DNBR 4.4.7.2 4.4.7 H Limits 5.2-1 ASME Code and Addenda 5.2.6.1 5.2.1.1 A 5.2.6.1 1.8-13 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 10 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 5.2-2 Plant Specific Inspection Program 5.2.6.2 5.2.4 A 5.2.4.1 5.2.4.3 5.2.4.4 5.2.4.5 5.2.4.6 5.2.4.8 5.2.4.9 5.2.4.10 5.2.6.2 5.3-1 Reactor Vessel Pressure - Temperature Limit 5.3.6.1 5.3.6.1 H Curves 5.3-2 Reactor Vessel Materials Surveillance Program 5.3.6.2 5.3.2.6 A 5.3.2.6.3 5.3.6.2 5.3-4 Reactor Vessel Materials Properties Verification 5.3.6.4.1 5.3.6.4.1 H 5.4-1 Steam Generator Tube Integrity 5.4.15 5.4.2.5 A 5.4.15 6.1-1 Procedure Review for Austenitic Stainless Steels 6.1.3.1 6.1.1.2 A 6.1.3.1 1.8-14 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 11 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 6.1-2 Coating Program 6.1.3.2 6.1.2.1.6 A 6.1.3.2 6.2-1 Containment Leak Rate Testing 6.2.6 6.2.5.1 A 6.2.5.2.2 6.2.6 6.3-1 Containment Cleanliness Program 6.3.8.1 6.3.8.1 A 6.4-1 Local Hazardous Gas Services and Monitoring 6.4.7 6.4.4.2 A 6.4.7 6.4-2 Procedures for Training for Control Room 6.4.7 6.4.3 A Habitability 6.4.7 6.6-1 Inspection Programs 6.6.9.1 6.6 A 6.6.1 6.6.3 6.6.4 6.6.6 6.6.9.1 6.6-2 Construction Activities 6.6.9.2 6.6.2 A 6.6.9.2 1.8-15 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 12 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 8.2-1 Offsite Electrical Power 8.2.5 8.2.1 A 8.2.1.1 8.2.1.2 8.2.1.3 8.2.1.4 8.2.5 8.2-2 Technical Interfaces 8.2.5 8.2.1.2.2 A 8.2.2 8.2.5 8.3-1 Grounding and Lightning Protection 8.3.3 8.3.1.1.7 A 8.3.1.1.8 8.3.3 8.3-2 Onsite Electrical Power Plant Procedures 8.3.3 8.3.1.1.2.4 A 8.3.1.1.6 8.3.2.1.4 8.3.3 9.1-5 Inservice Inspection Program of Cranes 9.1.6.5 9.1.4.4 A 9.1.5.4 9.1.6 1.8-16 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 13 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 9.1-6 Radiation Monitor 9.1.6.6 9.1.4.3.8 A 9.1.5.3 9.1.6 9.1.7 Metamic Monitoring Program 9.1.6.7 9.1.6 H 9.2-1 Potable Water 9.2.11.1 9.2.5.2.1 A 9.2.5.3 9.2.12.1 9.2-2 Waste Water Retention Basins 9.2.11.2 9.2.9.2.2 A 9.2.12.2 9.3-1 Air Systems (NUREG-0933 Issue 43) 9.3.7 9.3.7 A 9.4-1 Ventilation Systems Operations 9.4.12 9.4.1.4 A 9.4.7.4 9.4.12 1.8-17 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 14 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 9.5-1 Qualification Requirements for Fire Protection 9.5.1.8.1 9.5.1.6 A Program 9.5.1.8 9.5.1.8.1 9.5.1.8.1.2 9.5.1.8.2 9.5.1.8.3 9.5.1.8.4 9.5.1.8.5 9.5.1.8.6 9.5.1.8.7 9.5.1.9.1 13.1.1.2.10 13.1.2.1.2.9 9.5-2 Fire Protection Analysis Information 9.5.1.8.2 9.5.1.9.2 A 9A.3.3 9.5-3 Regulatory Conformance 9.5.1.8.3 9.5.1.8.8 A 9.5.1.8.9 9.5.1.9.3 9A.3.3 9.5-4 NFPA Exceptions 9.5.1.8.4 9.5.1.8.1.1 A 9.5.1.9.4 1.8-18 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 15 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 9.5-6 Verification of Field Installed Fire Barriers 9.5.1.8.6 9.5.1.8.6 H 9.5.1.9.6 9.5-8 Establishment of Procedures to Minimize Risk for 9.5.1.8.7 9.5.1.8.1.2.a.3.vi A Fire Areas Breached During Maintenance 9.5.1.9.7 9.5-9 Offsite Interfaces 9.5.2.5.1 9.5.2.2.3.1 A 9.5.2.5.1 9.5-10 Emergency Offsite Communications 9.5.2.5.2 9.5.2.2.3.2 A 9.5.2.5.2 9.5-11 Security Communications 9.5.2.5.3 9.5.2.5.3 A 9.5-13 Fuel Degradation Protection 9.5.4.7.2 9.5.4.5.2 A 9.5.4.7.2 10.1-1 Erosion-Corrosion Monitoring 10.1.3 10.1.3.1 H 10.2-1 Turbine Maintenance and Inspection 10.2.6 10.2.6 H 10.4-1 Circulating Water Supply 10.4.12.1 10.4.5.2.1 A 10.4.5.2.2 10.4.5.5 10.4.12.1 10.4-2 Condensate, Feedwater and Auxiliary Steam 10.4.12.2 10.4.7.2.1 A System Chemistry Control 10.4.12.2 1.8-19 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 16 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 10.4-3 Potable Water 10.4.12.3 10.4.12.3 A 11.2-1 Liquid Radwaste Processing by Mobile Equipment 11.2.5.1 11.2.1.2.5.2 A 11.2.5.1 11.2-2 Cost Benefit Analysis of Population Doses 11.2.5.2 11.2.3.3 A 11.2.3.5 11.2.5.2 11.3-1 Cost Benefit Analysis of Population Doses 11.3.5.1 11.3.3.4 A 11.3.5.1 11.4-1 Solid Waste Management System Process Control 11.4.6 11.4.6 A Program 11.5-1 Plant Offsite Dose Calculation Manual (ODCM) 11.5.7 11.5.7 A 11.5-2 Effluent Monitoring and Sampling 11.5.7 11.5.1.2 A 11.5.2.4 11.5.3 11.5.4 11.5.4.1 11.5.4.2 11.5.6.5 11.5.7 1.8-20 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 17 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 11.5-3 10 CFR 50, Appendix I 11.5.7 11.2.3.5 A 11.3.3.4 11.5.7 12.1-1 ALARA and Operational Policies 12.1.3 12.1 A 12.1.3 Appendix 12AA 12.2-1 Additional Contained Radiation Sources 12.2.3 12.2.1.1.10 A 12.2.3 12.3-1 Administrative Controls for Radiological Protection 12.3.5.1 12.3.5.1 A Appendix 12AA 12.3-2 Criteria and Methods for Radiological Protection 12.3.5.2 12.3.4 A 12.3.5.2 12.3-3 Groundwater Monitoring Program 12.3.5.3 12.3.5.3 A Appendix 12AA 12.3-4 Record of Operational Events of Interest for 12.3.5.4 12.3.5.4 A Decommissioning Appendix 12AA 12.5-1 Radiological Protection Organization and 12.5.5 12.5.5 A Procedures Appendix 12AA 1.8-21 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 18 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 13.1-1 Organizational Structure of Combined License 13.1.1 13.1 A Applicant 13.1.4 Appendix 13AA 13.2-1 Training Program for Plant Personnel 13.2.1 13.2 A 13.2.1 13.3-1 Emergency Planning and Communications 13.3.1 13.3 A 13.3.1 13.3-2 Activation of Emergency Operations Facility 13.3.1 13.3 A 13.3.1 13.4-1 Operational Review 13.4.1 13.4 A 13.4.1 13.5-1 Plant Procedures 13.5.1 13.5 A 13.5.3 13.6-1 Security 13.6 13.6 A 13.6.1 13.6-5 Cyber Security Program 13.6.1 13.6 H 13.6.1 14.4-1 Organization and Staffing 14.4.1 14.2.2 A 14.4.1 1.8-22 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 19 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 14.4-2 Test Specifics and Procedures 14.4.2 14.4.2 H 14.4-3 Conduct of Test Program 14.4.3 14.4.3 H 14.4-4 Review and Evaluation of Test Results 14.4.4 14.2.3.2 H 14.4.4 14.4-5 Testing Interface Requirements 14.4.5 14.2.9.4.15 A 14.2.9.4.22 14.2.9.4.23 14.2.9.4.24 14.2.9.4.25 14.2.9.4.26 14.2.9.4.27 14.2.10.4.29 14.4.5 14.4-6 First-Plant-Only and Three-Plant-Only Tests 14.4.6 14.4.6 B 15.7-1 Consequences of Tank Failure 15.7.6 2.4.13 A 15.7.6 16.1-1 Technical Specification Preliminary 16.1 16.1.1 A Information 16.3-1 Procedure to Control Operability of Investment 16.3.2 16.3.1 A Protection Systems, Structures and Components 16.3.2 1.8-23 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 20 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 17.5-1 Quality Assurance Design Phase 17.5.1 17.1 A 17.5 17.7 17.5-2 Quality Assurance for Procurement, 17.5.2 17.5 A Fabrication, Installation, Construction and Testing 17.7 17.5-4 Quality Assurance Program for Operations 17.5.4 17.5 A 17.7 17.5-8 Operational Reliability Assurance Program 17.5.8 17.5 A Integration with Quality Assurance Program 17.7 18.2-2 Design of the Emergency Operations Facility 18.2.6.2 18.2.1.3 A 18.2.6.2 18.6-1 Plant Staffing 18.6.1 13.1.1.4 A 13.1.3.1 13.1.3.2 18.6 18.6.1 18.10-1 Training Program Development 18.10.1 13.1.1.3.1.9 A 13.1.1.3.2.4 13.2 18.10 18.10.1 1.8-24 Revision 3
Part 2, FSAR TABLE 1.8-202 (Sheet 21 of 21) 1.8-2 COL ITEM TABULATION COL APPLICANT (A),
ITEM SUBJECT SUBSECTION SECTION(S) OR BOTH (B) 18.14-1 Human Performance Monitoring 18.14 18.14 A 19.59.10-1 As-Built SSC HCLPF Comparison to Seismic Margin 19.59.10.5 19.59.10.5 H Evaluation 19.59.10-2 Evaluation of As-Built Plant Versus Design in 19.59.10.5 19.59.10.5 B AP1000 PRA and Site-Specific PRA External Events 19.59.10-3 Internal Fire and Internal Flood Analyses 19.59.10.5 19.59.10.5 H 19.59.10-4 Implement Severe Accident Management Guidance 19.59.10.5 19.59.10.5 H 19.59.10-5 Equipment Survivability 19.59.10.5 19.59.10.5 H a) COL Items 1.9-2 and 1.9-3 are un-numbered in the DCD.
1.8-25 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 1 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Envelope of AP1000 plant site related Site specific 2.1 Site Interface Table 2.0-201 parameters parameters 2.2.2.2, External missiles from man-made hazards and Site specific 2.2 Site Interface 2.2.3.1, accidents parameters 3.5 Maximum loads from man-made hazards and Site specific 2.3 Site Interface Table 2.0-201 accidents parameters Limiting meteorological parameters (/Q) for design basis accidents and for routine releases Site specific 2.4 and other extreme meteorological conditions Site Interface Table 2.0-201 parameters for the design of systems and components exposed to the environment.
Site specific 2.5 Tornado and operating basis wind loadings Site Interface Table 2.0-201 parameters External missiles generated by natural Site specific 2.6 Site Interface Table 2.0-201 phenomena parameters Site specific 2.7 Snow, ice and rain loads Site Interface 2.3.1.2 parameters Site specific 2.8 Ambient air temperatures Site Interface Table 2.0-201 parameters 1.8-26 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 2 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Requirement of Combined License 2.9 Onsite meteorological measurement program 2.3.3 AP1000 applicant program Site specific 2.10 Flood and ground water elevations Site Interface Table 2.0-201 parameters Hydrostatic loads on systems, components and Site specific 2.11 Site Interface Table 2.0-201 structures parameters Seismic parameters peak ground acceleration Site specific 2.12 Site Interface Table 2.0-201 response spectra shear wave velocity parameters Required bearing capacity of foundation Site specific 2.13 Site Interface Table 2.0-201 materials parameters 3.1 Deleted N/A N/A N/A Operating procedures to minimize water Requirement of Combined License 10.3.2.2.1, 3.2 hammer AP1000 applicant procedure 10.4.7.2.1 Requirement of Onsite 3.7.4.2.1 3.3 Site seismic sensor location and "trigger" value AP1000 implementation Requirement of Onsite 3.8.5.1, 3.4 Depth of overburden AP1000 implementation 2.5.4 Requirement of Onsite 3.8.5.1, 3.5 Depth of embedment AP1000 implementation 2.5.4 1.8-27 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 3 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Requirement of Onsite 3.6 Specific depth of waterproofing 2.5.4.1 AP1000 implementation Combined License Requirement of 3.7 Foundation Settlement Monitoring applicant 2.5.4.10.4 AP1000 coordination 3.8 Lateral earth pressure loads Not an Interface N/A N/A 3.9 Preoperational piping vibration test parameters Not an Interface N/A N/A 3.9.6, Inservice Inspection requirements and Requirement of Combined License 3.10 5.2.4, locations AP1000 applicant program 6.6 Maintenance of preservice and reference test Requirement of Combined License 3.11 3.9.6 data for inservice testing of pumps and valves AP1000 applicant program Requirement of Combined License 3.12 Earthquake response procedures 3.7.4.4 AP1000 applicant program Steam Generator Tube Surveillance Requirement of Combined License 5.1 5.4.2.5 Requirements AP1000 applicant program Inservice Inspection requirements for the Requirement of Combined License 6.1 6.6 containment AP1000 applicant program 1.8-28 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 4 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Off site environmental conditions assumed for Site specific 2.2.3, 6.2 Main Control Room and control support area AP1000 Interface parameter 6.4 habitability design Listing of all design criteria applied to the 7.1 Not an Interface N/A N/A design of the I&C systems Power required for site service water NNS and 7.2 N/A N/A instrumentation Not an Interface Other provisions for site service water NNS and 7.3 N/A N/A instrumentation Not an Interface Combined License Listing of design criteria applied to the design of 8.1 NNS applicant 8.1.4.3 the offsite power system coordination Offsite ac requirements:
- Steady-state load;
- Inrush kVA for motors;
- Nominal voltage; Combined License 8.2 - Allowable voltage regulation; NNS applicant 8.2.2
- Nominal frequency; coordination
- Allowable frequency fluctuation;
- Maximum frequency decay rate;
- Limiting under frequency value for RCP 1.8-29 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 5 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Offsite transmission system analysis:
- Loss of AP1000 or largest unit;
- Voltage operating range;
- Transient stability must be maintained and the RCP bus voltage must remain above the voltage required to maintain the flow assumed Combined License 8.2.2, 8.3 NNS in Chapter 15 analyses for a minimum of three applicant analysis 8.2.1.2.2 (3) seconds following a turbine trip.;
- The protective devices controlling the switchyard breakers are set with consideration given to preserving the plant grid connection following a turbine trip.
Listing of design criteria applied to the design of NNS and 8.4 N/A N/A onsite ac power systems Not an Interface NNS and 8.5 Onsite ac requirements N/A N/A Not an Interface NNS and 8.6 Diesel generator room coordination N/A N/A Not an Interface Listing of design criteria applied to the design of 8.7 Not an Interface N/A N/A onsite dc power systems Provisions of dc power systems to NNS and 8.8 N/A N/A accommodate the site service water system Not an Interface 1.8-30 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 6 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Listing of design criteria applied to the design of NNS and 9.1 N/A N/A portions of the site service water within AP1000 Not an Interface Integrated heat load to site service water NNS and 9.2 N/A N/A system Not an Interface NNS and 9.3 Plant cooling water systems parameters N/A N/A Not an Interface Site specific 9.4 Plant makeup water quality limits NNS 9.2.11 parameter Requirements for location and arrangement of 9.2.5, 9.5 NNS Site implementation raw and sanitary water systems 9.2.11 Ventilation requirements for diesel-generator NNS and 9.6 N/A N/A room Not an Interface Combined License 9.7 Requirements to satisfy fire protection program AP1000 Interface 9.5.1 applicant program Expected release rates of radioactive material from the Liquid Waste System including:
- Location of release points Site specific 11.1 Site Interface 11.2
- Effluent temperature parameters
- Effluent flow rate
- Size and shape of flow orifices 1.8-31 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 7 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Expected release rates of radioactive materials from the Gaseous Waste System including:
- Location of release points
- Height above grade Site specific 11.2 - Height relative to adjacent buildings Site Interface 11.3 parameters
- Effluent temperature
- Effluent flow rate
- Effluent velocity
- Size and shape of flow orifices Expected release rates of radioactive material from the Solid Waste System including:
- Location of release points Site specific 11.3 Site Interface 11.4.6
- Material types parameters
- Material qualities
- Size and shape of material containers Requirements for offsite sampling and Combined License 11.5.3, 11.4 AP1000 Interface monitoring of effluent concentrations applicant program 11.5.7 Identification of miscellaneous radioactive Combined License 12.1 AP1000 Interface 12.2.1 sources applicant program Features that may affect plans for coping with Combined License 13.1 emergencies as specified in 10 CFR 50, AP1000 Interface 13.3 applicant program Appendix O 1.8-32 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 8 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Physical Security Plan consistent with AP1000 Combined License 13.2 AP1000 Interface 13.6 plant applicant program Identification of special features to be Requirement of Combined License 14.1 considered in development of the initial test 14 AP1000 applicant program program Maintenance of preoperational test data and Combined License 14.2 AP1000 Interface 14 inservice inspection baseline data applicant program Administrative requirements associated with Combined License 16.1 AP1000 Interface 16 reliability information maintenance applicant program Combined License Administrative requirements associated with Requirement of 16.2 applicant 16 the Technical Specifications AP1000 implementation Site and operator related information Requirement of Combined License 16.3 associated with the Reliability Assurance 16.2 AP1000 applicant program Program (D-RAP)
Operating staff consistent with Human Factors Combined License 18.1 AP1000 Interface 18.6 evaluations applicant program Operator training consistent with Human Combined License 18.8, 18.2 AP1000 Interface Factors evaluations applicant program 18.10 1.8-33 Revision 3
Part 2, FSAR TABLE 1.8-203 (Sheet 9 of 9) 1.8-3
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Matching Interface Section(1) or Item No. Interface Interface Type Item Subsection Operating Procedures consistent with Human Combined License 18.8, 18.3 AP1000 Interface Factors evaluations applicant program 18.10 Note 1 - This table supplements DCD Table 1.8-1 by providing additional information in the Section or Subsection column.
1.8-34 Revision 3
1.9 COMPLIANCE WITH REGULATORY CRITERIA This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
1.9.1 REGULATORY GUIDES Add the following paragraphs to the end of DCD Subsection 1.9.1:
COL 1.9-1 Divisions 2, 3, 6, 7, 9, and 10 of the regulatory guides do not apply to the construction or operational safety considerations and are not addressed in the FSAR.
Division 4 of the regulatory guides applies to the Environmental Report and the topics are addressed in the Environmental Report. Two Division 4 Regulatory Guides are addressed in Appendix 1AA.
Division 5 of the regulatory guides applies to the Physical Security Plan and the topics are addressed in the Physical Security Plan. Three Division 5 Regulatory Guides are addressed in Appendix 1AA.
Applicable Division 8 Regulatory Guides are addressed in Appendix 1AA.
Appendix 1AA provides a discussion of plant specific regulatory guide conformance, addressing new Regulatory Guides and new revisions not addressed by the referenced DCD. Regulatory Guides that are completely addressed by the DCD are not listed.
The following subsections provide a summary discussion of Divisions 1, 4, 5 and 8 of the regulatory guides as applicable to the content of this FSAR, or to the construction and/or operations phases.
1.9.1.1 Division 1 Regulatory Guides - Power Reactors Add the following paragraphs to the end of DCD Subsection 1.9.1.1:
COL 1.9-1 Appendix 1AA provides an evaluation of the degree of compliance with Division 1 regulatory guides as applicable to the content of this FSAR, or to the site-specific design, construction and/or operational aspects. The revisions of the regulatory guides against which the degree of compliance is evaluated are indicated. Any exceptions or alternatives to the provisions of the regulatory guides are identified and justification is provided. One such general alternative is the use of previous 1.9-1 Revision 3
revisions of the Regulatory Guide for design aspects as stated in the DCD in order to preserve the finality of the certified design (see Notes at the end of Appendix 1AA). Table 1.9-201 identifies the appropriate regulatory guide to FSAR cross-references. The cross-referenced sections contain descriptive information applicable to the regulatory guide positions found in Appendix 1AA.
Superseded or canceled regulatory guides are not considered in Appendix 1AA or Table 1.9-201.
1.9.1.2 Division 4 Regulatory Guides - Environmental and Siting Add the following as the first paragraph in DCD Subsection 1.9.1.2:
COL 1.9-1 Division 4 of the regulatory guides applies to the Environmental Report and the topics are addressed in the Environmental Report. Appendix 1AA provides an evaluation of the degree of compliance with Division 4 regulatory guides as applicable to the content of this FSAR, or to the site-specific design, construction and/or operational aspects. The revisions of the regulatory guides against which the plant is evaluated are indicated. Any exceptions or alternatives to the provisions of the regulatory guides are identified and justification is provided. One such general alternative is the use of previous revisions of the Regulatory Guide for design aspects as stated in the DCD in order to preserve the finality of the certified design (see Notes at the end of Appendix 1AA). For those regulatory guides applicable, Table 1.9-201 identifies the appropriate FSAR cross-references. The cross-referenced sections contain descriptive information applicable to the regulatory guide positions found in Appendix 1AA.
1.9.1.3 Division 5 Regulatory Guides - Materials and Plant Protection Add the following as the first paragraph in DCD Subsection 1.9.1.3:
COL 1.9-1 Division 5 of the regulatory guides applies to the Physical Security Plan and the topics are addressed in the Physical Security Plan. Appendix 1AA provides an evaluation of the degree of compliance with Division 5 regulatory guides as applicable to the content of this FSAR, or to the site-specific design, construction and/or operational aspects. The revisions of the regulatory guides against which the plant is evaluated are indicated. Any exceptions or alternatives to the provisions of the regulatory guides are identified and justification is provided. One such general alternative is the use of previous revisions of the Regulatory Guide for design aspects as stated in the DCD in order to preserve the finality of the 1.9-2 Revision 3
certified design (see Notes at the end of Appendix 1AA). The cross-referenced sections contain descriptive information applicable to the regulatory guide positions found in Appendix 1AA.
1.9.1.4 Division 8 Regulatory Guides - Occupational Health Add the following paragraphs to the end of DCD Subsection 1.9.1.4:
COL 1.9-1 Appendix 1AA provides an evaluation of the degree of compliance with Division 8 regulatory guides as applicable to the content of this FSAR, or to the site-specific design, construction and/or operational aspects. The revisions of the regulatory guides against which the plant is evaluated are indicated. Any exceptions or alternatives to the provisions of the regulatory guides are identified and justification is provided. One such general alternative is the use of previous revisions of the Regulatory Guide for design aspects as stated in the DCD in order to preserve the finality of the certified design (see Notes at the end of Appendix 1AA). For those regulatory guides applicable, Table 1.9-201 identifies the appropriate FSAR cross-references. The cross-referenced sections contain descriptive information applicable to the regulatory guide positions found in Appendix 1AA.
Superseded or canceled regulatory guides are not considered in Appendix 1AA or Table 1.9-201.
1.9.1.5 Combined License Information Add the following as the first paragraph in DCD Subsection 1.9.1.5:
COL 1.9-1 Division 1, 4, 5 and 8 Regulatory Guides applicable to the content of this FSAR, or to the site-specific design, construction and/or operational aspects are listed in Table 1.9-201 and Appendix 1AA.
1.9-3 Revision 3
1.9.2 COMPLIANCE WITH STANDARD REVIEW PLAN (NUREG-0800)
Add the following paragraph to the end of DCD Subsection 1.9.2:
SUP 1.9-1 Table 1.9-202 provides the required assessment of conformance with the applicable acceptance criteria and the associated FSAR cross-references.
The design related SRP acceptance criteria addressed by the certified design are identified as such in Table 1.9-202.
1.9.4.1 Review of NRC List of Unresolved Safety Issues and Generic Safety Issues Add the following paragraphs to the end of DCD Subsection 1.9.4.1:
COL 1.9-3 Table 1.9-203 addresses the second un-numbered COL Information Item identified at the end of DCD Table 1.8-2 and listed in Table 1.8-202 as COL Information Item 1.9-3, "Unresolved Safety Issues and Generic Safety Issues." As such, Table 1.9-203 lists those issues on DCD Table 1.9-2 identified by Note "d,"
which apply to other than design issues, Note "f," which apply either to resolution of Combined License (COL) Information Items or to nuclear power plant operations issues, Note "h," which apply to issues unresolved pending generic resolution at the time of submittal of the AP1000 DCD, and any new Unresolved Safety Issues and Generic Safety Issues that have been included in NUREG-0933 (through supplement 30) since the DCD was developed. Many of these have since been resolved and incorporated into the applicable licensing regulations or guidance (e.g., the standard review plans). These resolved items (as indicated by NUREG-0933) are identified only as "Resolved per NUREG-0933." Many others are not in the list of items in NUREG-0933 Appendix B identified as applicable to new plants. These items are identified only as "Not applicable to new plants." For the remaining items, the table provides the FSAR sections that address the topic.
1.9.4.2.3 New Generic Issues COL 1.9-3 Add the following text in DCD Subsection 1.9.4.2.3., following the AP1000 Position for Issue 185.
1.9-4 Revision 3
Issue 186 Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants Discussion:
This issue concerns licensees operating within the regulatory guidelines of Generic Letter 85-11 that may not have taken adequate measures to assess and mitigate the consequences of dropped heavy loads.
FSAR Position:
There are no planned heavy load lifts outside those already described in the DCD. However, over the plant life there may be occasions when heavy loads not presently addressed need to be lifted (i.e. in support of special maintenance/ repairs). For these occasions, special procedures are generated that address to the activity. Further discussion is provided in Subsection 9.1.5.3.
Issue 189 Susceptibility of Ice Condenser and Mark III Containments to Early Failure From Hydrogen Combustion During a Severe Accident Description Discussion:
This issue concerns the early containment failure probability for ice condenser and BWR MARK III containments given the relatively low containment free volume and low containment strength in these designs.
FSAR Position:
The AP1000 design does not have an ice condenser containment or a Mark III containment. Therefore, this issue is not addressed in this FSAR.
Add the following text in DCD Subsection 1.9.4.2.3 following the AP1000 Position for Issue 191.
COL 1.9-3 Issue 191 Assessment of Debris Accumulation on PWR Sump Performance (REV. 1)
Discussion:
Results of research on BWR ECCS suction strainer blockage identified new phenomena and failure modes that were not 1.9-5 Revision 3
considered in the resolution of Issue A-43. In addition, operating experience identified new contributors to debris and possible blockage of PWR sumps, such as degraded or failed containment paint coatings.
FSAR Position:
The design aspects of this issue are addressed by the DCD. The protective coatings program controls the procurement, application, inspection, and monitoring of Service Level I and Service Level III coatings with the quality assurance features discussed above. The protective coatings program complies with Regulatory Guide 1.54, and is controlled and implemented by administrative procedures.
The program is discussed in Subsection 6.1.2.1.6.
Administrative procedures implement the containment cleanliness program. Implementation of the program minimizes the amount of debris that might be left in containment following refueling and maintenance outages. The program is consistent with the containment cleanliness program used in the evaluation discussed in DCD Subsection 6.3.8.2. The program is discussed in Subsection 6.3.8.1.
Issue 196 Boral Degradation Discussion:
The issue specifically addresses the use of Boral in long-term dry storage casks for spent reactor fuel.
FSAR Position:
Long-term dry storage casks for spent reactor fuel are not used and therefore this issue is not addressed in this FSAR.
1.9.5.1.5 Station Blackout SUP 1.9-3 Add the following text to the end of DCD Subsection 1.9.5.1.5.
Training and procedures to mitigate a 10 CFR 50.63 "loss of all alternating current power" (or station blackout (SBO)) event are implemented in accordance with Sections 13.2 and 13.5, respectively. As recommended by NUMARC 87-00 (Reference 201), the SBO event mitigation procedures address response (e.g.,
restoration of onsite power sources), ac power restoration (e.g., coordination with 1.9-6 Revision 3
transmission system load dispatcher), and severe weather guidance (e.g.,
identification of actions to prepare for the onset of severe weather such as an impending tornado), as applicable. The AP1000 is a passive design and does not rely on offsite or onsite ac sources of power for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after an SBO event, as described above. In addition, there are no nearby large power sources, such as a gas turbine or black start fossil fuel plant, that can directly connect to the station to mitigate the event.
Restoration from an SBO event will be contingent upon ac power being made available from any one of the transmission lines described in Section 8.2 or any one of the standby diesel generators.
1.9.5.2.15 Severe Accident Mitigation Design Alternatives Add the following text to the end of DCD Subsection 1.9.5.2.15.
FSAR Position:
SUP 1.9-2 The severe accident mitigation design alternatives (SAMDA) evaluation for AP1000 contained in DCD Appendix 1B is not incorporated into this FSAR, but is addressed in the COL application Environmental Report.
1.9.5.5 Operational Experience Add the following paragraph to the end of DCD Subsection 1.9.5.5.
COL 1.9-2 Table 1.9-204 lists the Bulletins and Generic Letters addressed by topical discussion in this FSAR. Table 1.9-204 also lists Bulletins and Generic Letters categorized as part of the first un-numbered COL Information Item identified at the end of DCD Table 1.8-2 and listed in Table 1.8-202 as COL Information Item 1.9-2.
Table 1.9-204 provides the appropriate FSAR cross-references for the discussion of the topics addressed by those Bulletins and Generic Letters. Bulletins or Generic Letters issued after those listed in the DCD are also included in Table 1.9-204. Issues identified as procurement or maintenance or surveillance in WCAP-15800 are addressed as part of the scope of the certified design and are not specifically identified in Table 1.9-204. Issues identified as procedural in WCAP-15800 are addressed by the procedures discussed in DCD Section 13.5 and are not specifically identified in Table 1.9-204. Other items in WCAP-15800, including the Circulars and Information Notices, are considered to 1.9-7 Revision 3
have been adequately addressed based on the guidance identified in Regulatory Guide 1.206 and the NRC Standard Review Plans.
1.
9.6 REFERENCES
Add the following text to the end of DCD Subsection 1.9.6.
201. NUMARC 87-00, Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors, Revision 1, August 1991.
1.9-8 Revision 3
TABLE 1.9-201 (Sheet 1 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona Division 1 Regulatory Guides 1.6 Independence Between Redundant 16 (TS Bases 3.8.1)
Standby (Onsite) Power Sources and Between Their Distribution Systems (Rev. 0, March 1971) 1.7 Control of Combustible Gas DCD discussion only; Concentrations in Containment see DCD Table 1.9-1 (Rev. 3, March 2007) 1.8 Qualification and Training of Personnel 12.1 (NEI 07-08A) for Nuclear Power Plants (Rev. 3, May Appendix 12AA 2000) Appendix 12AA (NEI 07-03A) 13.1.1.4 13.1.3.1 13.2 (NEI 06-13A) 16 (TS 5.3.1) 17.5 (QAPD, IV) 1.12 Nuclear Power Plant Instrumentation 3.7.4.1 for Earthquakes (Rev. 2, March 1997) 1.13 Spent Fuel Storage Facility Design 16 (TS Bases 3.7.11)
Basis (Rev. 2, March 2007) 16 (TS Bases 3.7.12) 1.20 Comprehensive Vibration Assessment DCD discussion only; Program for Reactor Internals During see DCD Table 1.9-1 Preoperational and Initial Startup Testing (Rev. 3, March 2007) 1.21 Measuring, Evaluating, and Reporting 2.3.3.2.3 Radioactivity in Solid Wastes and 11.5.1.2 Releases of Radioactive Materials in 11.5.4.1 Liquid and Gaseous Effluents From 12.3.4 Light-Water-Cooled Nuclear Power Plants (Rev.1, June 1974) 1.23 Meteorological Monitoring Program for 2.3.3.2 Nuclear Power Plants (Rev. 1, March 2.3.4.2 2007) 2.3.4.3 1.9-9 Revision 3
TABLE 1.9-201 (Sheet 2 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.26 Quality Group Classifications and 5.2.4.1 Standards for Water-, Steam-, and 17.5 (QAPD IV)
Radioactive-Waste-Containing Components of Nuclear Power Plants (Rev. 4, March 2007) 1.27 Ultimate Heat Sink for Nuclear Power 2.4.11.6 Plants (Rev. 2, January 1976) 1.28 Quality Assurance Program 17.5 (QAPD, II, 17.1)
Requirements (Design and 17.5 (QAPD, IV)
Construction) (Rev. 3, August 1985) 1.29 Seismic Design Classification 17.5 (QAPD IV)
(Rev. 4, March 2007) 1.30 Quality Assurance Requirements for Not referenced; the Installation, Inspection, and see Appendix 1AA Testing of Instrumentation and Electric Equipment (Rev. 0, August 1972) 1.31 Control of Ferrite Content in Stainless 6.1.1.2 Steel Weld Metal (Rev. 3, April 1978) 1.32 Criteria for Power Systems for Nuclear 16 (TS Bases 3.8.1)
Power Plants (Rev. 3, March 2004) 1.33 Quality Assurance Program 16 (TS 5.4.1)
Requirements (Operation) (Rev. 2, 17.5 (QAPD, IV)
February 1978) 1.37 Quality Assurance Requirements for 17.5 (QAPD IV)
Cleaning of Fluid Systems and 17.5 (QAPD, II, 13.2)
Associated Components of Water Cooled Nuclear Power Plants (Rev. 1, March 2007) 1.38 Quality Assurance Requirements for DCD discussion only; Packaging, Shipping, Receiving, see DCD Table 1.9-1 Storage and Handling of Items for Water- Cooled Nuclear Power Plants (Rev. 2, May 1977) 1.9-10 Revision 3
TABLE 1.9-201 (Sheet 3 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.39 Housekeeping Requirements for DCD discussion only; Water- Cooled Nuclear Power Plants see DCD Table 1.9-1 (Rev. 2, September 1977) 1.44 Control of the Use of Sensitized 6.1.1.2 Stainless Steel (Rev. 0, May 1973) 1.45 Reactor Coolant Pressure Boundary 16 (TS Bases 3.4.7)
Leakage Detection Systems (Rev. 0, 16 (TS Bases 3.4.9)
May 1973) 1.53 Application of the Single-Failure DCD discussion only; Criterion to Nuclear Power Plant see DCD Table 1.9-1 Protection Systems (Rev. 2, November 2003) 1.54 Service Level I, II, and III Protective 1.9.4.2.3 Coatings Applied to Nuclear Power 6.1.2.1.6 Plants (Rev. 1, July 2000) 1.57 Design Limits and Loading DCD discussion only; Combinations for Metal Primary see DCD Table 1.9-1 Reactor Containment System Components (Rev. 1, March 2007) 1.59 Design Basis Floods for Nuclear 2.4.2.2 Power Plants (Rev. 2, August 1977) 2.4.3 2.4.4 2.4.4.1 2.4.5 1.60 Design Response Spectra for Seismic Table 2.0-201 Design of Nuclear Power Plants (Rev. 1, December 1973) 1.61 Damping Values for Seismic Design of DCD discussion only; Nuclear Power Plants (Rev. 1, March see DCD Table 1.9-1 2007) 1.68 Initial Test Program for Water-Cooled 14.2.1 Nuclear Power Plants (Rev. 3, March 14.2.3 2007) 14.2.5.2 14.2.8 16 (TS Bases 3.1.8) 1.9-11 Revision 3
TABLE 1.9-201 (Sheet 4 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.70 Standard Format and Content of 1.1.6.1 Safety Analysis Reports for Nuclear Power Plants (LWR Edition) (Rev. 3, November 1978) 1.71 Welder Qualification for Areas of DCD discussion only; Limited Accessibility (Rev 1, March see DCD Table 1.9-1 2007) 1.75 Criteria for Independence of Electrical DCD discussion only; Safety Systems (Rev 3, February see DCD Table 1.9-1 2005) 1.76 Design-Basis Tornado and Tornado Table 2.0-201 Missiles for Nuclear Power Plants 2.3.1.4 (Rev. 1, March 2007) 1.77 Assumptions Used for Evaluating a 16 (TS Bases 3.2.1)
Control Rod Ejection Accident for 16 (TS Bases 3.2.2)
Pressurized Water Reactors (Rev 0, 16 (TS Bases 3.2.4)
May 1974) 16 (TS Bases 3.2.5) 1.78 Evaluating the Habitability of a Nuclear 2.2.3.1.3 Power Plant Control Room During a 6.4.3 Postulated Hazardous Chemical 6.4.4.2 Release (Rev. 1, December 2001) 16 (TS Bases 3.7.6) 1.82 Water Sources for Long-Term DCD discussion only; Recirculation Cooling Following a see DCD Table 1.9-1 Loss-of-Coolant Accident (Rev. 3, November 2003) 1.83 Inservice Inspection of Pressurized DCD discussion only; Water Reactor Steam Generator see DCD Table 1.9-1 Tubes (Rev. 1, July 1975) 1.84 Design, Fabrication, and Materials DCD discussion only; Code Case Acceptability, ASME see DCD Table 1.9-1 Section III (Rev. 33, August 2005) 1.86 Termination of Operating Licenses for Not referenced; Nuclear Reactors (Rev. 0, June 1974) see Appendix 1AA 1.9-12 Revision 3
TABLE 1.9-201 (Sheet 5 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.91 Evaluations of Explosions Postulated 2.2.3.1.1 To Occur on Transportation Routes 2.2.3.2 Near Nuclear Power Plants (Rev. 1, 3.5.1.5 February 1978) Table 19.58-201 1.92 Combining Modal Responses and DCD discussion only; Spatial Components in Seismic see DCD Table 1.9-1 Response Analysis (Rev. 2, July 2006) 1.93 Availability of Electric Power Sources 16 (TS Bases 3.8.1)
(Rev. 0, December 1974) 16 (TS Bases 3.8.5) 1.94 Quality Assurance Requirements for Not referenced; Installation, Inspection and Testing of see Appendix 1AA Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Rev. 1, April 1976) 1.97 Criteria For Accident Monitoring Not refererenced; Instrumentation For Nuclear Power see Appendix 1AA Plants (Rev. 4, June 2006) 1.97 Instrumentation for Light-Water- Table 7.5-201 Cooled Nuclear Power Plants to Appendix 12AA Assess Plant Environs Conditions 16 (TS Bases 3.3.3)
During and Following an Accident (Rev. 3, May 1983) 1.99 Radiation Embrittlement of Reactor 16 (TS Bases 3.4.3)
Vessel Materials (Rev. 2, May 1988) 1.101 Emergency Response Planning and Not referenced; Preparedness for Nuclear Power see Appendix 1AA Reactors (Rev. 5, June 2005) 1.101 Emergency Planning and Not referenced; Preparedness for Nuclear Power see Appendix 1AA Reactors (Rev. 4, July 2003) 1.101 Emergency Planning and 9.5.1.8.2.2 Preparedness for Nuclear Power Table 9.5-201 Reactors (Rev. 3, August 1992) 13.3 (Emergency Plan I.C.1) 1.9-13 Revision 3
TABLE 1.9-201 (Sheet 6 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.109 Calculation of Annual Doses to Man 11.2.3.5 from Routine Releases of Reactor 11.3.3.4 Effluents for the Purpose of Evaluating 12.4.1.9.3 Compliance with 10 CFR Part 50, Table 12.4-201 Appendix I (Rev. 1, October 1977) 1.110 Cost-Benefit Analysis for Radwaste 11.2.3.5.3 Systems for Light-Water-Cooled 11.3.3.4.3 Nuclear Power Reactors (Draft Rev. 0, March 1976) 1.111 Methods for Estimating Atmospheric 2.3.5.1 Transport and Dispersion of Gaseous 12.4.1.9.3 Effluents in Routine Releases from Light-Water-Cooled Reactors (Rev. 1, July 1977) 1.112 Calculation of Releases of Radioactive DCD discussion only; Materials in Gaseous or Liquid see DCD Table 1.9-1 Effluents from Light-Water-Cooled Nuclear Power Reactors (Rev. 1, March 2007) 1.113 Estimating Aquatic Dispersion of 11.2.3.3 Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I (Rev. 1, April 1977) 1.114 Guidance to Operators at the Controls 13.1.2.1.2.6 and to Senior Operators in the Control 13.1.2.1.3 Room of a Nuclear Power Unit (Rev. 2, May 1989) 1.115 Protection Against Low-Trajectory 3.5.1.3 Turbine Missiles (Rev. 1, July 1977) 1.116 Quality Assurance Requirements for Not referenced; Installation, Inspection, and Testing of see Appendix 1AA Mechanical Equipment and Systems (Rev. 0-R, May 1977) 1.9-14 Revision 3
TABLE 1.9-201 (Sheet 7 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.121 Bases for Plugging Degraded PWR 16 (TS Bases 3.4.18)
Steam Generator Tubes (Rev. 0, August 1976) 1.124 Service Limits and Loading DCD discussion only; Combinations for Class 1 Linear-Type see DCD Table 1.9-1 Supports (Rev. 2, February 2007) 1.128 Installation Design and Installation of DCD discussion only; Vented Lead-Acid Storage Batteries see DCD Table 1.9-1 for Nuclear Power Plants (Rev. 2, February 2007) 1.129 Maintenance, Testing, and Table 8.1-201 Replacement of Vented Lead-Acid 8.3.2.1.4 Storage Batteries for Nuclear Power 16 (TS Bases 3.8.1)
Plants (Rev. 2, February 2007) 1.130 Service Limits and Loading DCD discussion only; Combinations for Class 1 Plate-And- see DCD Table 1.9-1 Shell-Type Supports (Rev. 2, March 2007) 1.132 Site Investigations for Foundations of 2.5.4.2.1 Nuclear Power Plants (Rev. 2, October 2.5.4.4 2003) 1.133 Loose-Part Detection Program for the Not referenced; Primary System of Light-Water-Cooled see Appendix 1AA Reactors (Rev. 1, May 1981) 1.134 Medical Evaluation of Licensed Not referenced; Personnel at Nuclear Power Plants see Appendix 1AA (Rev. 3, March 1998) 1.135 Normal Water Level and Discharge at Not referenced; Nuclear Power Plants (Rev. 0, see Appendix 1AA September 1977) 1.138 Laboratory Investigations of Soils and 2.5.4.2.1 Rocks for Engineering Analysis and Design of Nuclear Power Plants (Rev. 2, December 2003) 1.9-15 Revision 3
TABLE 1.9-201 (Sheet 8 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.139 Guidance for Residual Heat Removal DCD discussion only; (Rev. 0, May 1978) see DCD Table 1.9-1 1.140 Design, Inspection, and Testing 9.4.1.4 Criteria for Air Filtration and 9.4.7.4 Adsorption Units of Normal 16 (TS Bases 3.9.6)
Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants (Rev. 2, June 2001) 1.143 Design Guidance for Radioactive 11.2.1.2.5.2 Waste Management Systems, 11.2.3.6 Structures, and Components Installed 11.3.3.6 in Light-Water-Cooled Nuclear Power 11.4.5 Plants (Rev. 2, November 2001) 11.4.6.2 1.145 Atmospheric Dispersion Models for 2.3.4.1 Potential Accident Consequence 2.3.4.2 Assessments at Nuclear Power Plants (Rev. 1, November 1982) 1.147 Inservice Inspection Code Case 5.2.4 Acceptability, ASME section XI, 6.6 Division 1 (Rev. 15, October 2007) 1.149 Nuclear Power Plant Simulation 13.2 (NEI 06-13A)
Facilities for Use in Operator Training and License Examinations (Rev. 3, October 2001) 1.150 Ultrasonic Testing of Reactor Vessel DCD discussion only; Welds During Preservice and Inservice see DCD Table 1.9-1 Examinations (Rev. 1, February 1983) 1.152 Criteria for Use of Computers in Safety Not referenced; Systems of Nuclear Power Plants see Appendix 1AA (Rev. 2, January 2006) 1.154 Format and Content of Plant-Specific Not referenced; Pressurized Thermal Shock Safety see Appendix 1AA Analysis Reports for Pressurized Water Reactors (Rev. 0, January 1987) 1.9-16 Revision 3
TABLE 1.9-201 (Sheet 9 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.155 Station Blackout (Rev. 0, August 1998) Table 8.1-201 1.159 Assuring the Availability of Funds for Not referenced; Decommissioning Nuclear Reactors see Appendix 1AA (Rev. 1, October 2003) 1.160 Monitoring the Effectiveness of 17.6 (NEI 07-02A)
Maintenance at Nuclear Power Plants (Rev. 2, March 1997) 1.162 Format and Content of Report for Not referenced; Thermal Annealing of Reactor see Appendix 1AA Pressure Vessels (Rev. 0, February 1996) 1.163 Performance-Based Containment 6.2.5.1 Leak-Test Program (Rev. 0, 6.2.5.2.2 September 1995) 16 (TS 5.5.8) 1.165 Identification and Characterization of Not referenced; see Seismic Sources and Determination of Appendix 1AA Safe Shutdown Earthquake Ground Motion (Rev. 0, March 1997) 1.166 Pre-Earthquake Planning and 3.7.4.4 Immediate Nuclear Power Plant Operator Post Earthquake Actions (Rev. 0, March 1997) 1.167 Restart of a Nuclear Power Plant Shut 3.7.4.4 Down by a Seismic Event (Rev. 0, March 1997) 1.168 Verification, Validation, Reviews, and DCD discussion only; Audits for Digital Computer Software see DCD Table 1.9-1 Used in Safety Systems of Nuclear Power Plants (Rev. 1, February 2004) 1.174 An Approach for Using Probabilistic Not referenced; Risk Assessment in Risk-Informed see Appendix 1AA Decisions on Plant-Specific Changes to the Licensing Basis (Rev. 1, November 2002) 1.9-17 Revision 3
TABLE 1.9-201 (Sheet 10 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.175 An Approach for Plant-Specific, Risk- Not referenced; Informed Decisionmaking: Inservice see Appendix 1AA Testing (Rev. 0, August 1998) 1.177 An Approach for Plant-Specific, Risk- 16 (TS Bases 3.5.1)
Informed Decisionmaking: Technical 16 (TS Bases 3.7.10)
Specifications (Rev. 0, August 1998) 1.178 An Approach for Plant-Specific Risk- Not referenced; Informed Decisionmaking for Inservice see Appendix 1AA Inspection of Piping (Rev. 1, September 2003) 1.179 Standard Format and Content of Not referenced; License Termination Plans for Nuclear see Appendix 1AA Power Reactors (Rev. 0, January 1999) 1.180 Guidelines for Evaluating DCD discussion only; Electromagnetic and Radio-Frequency see DCD Table 1.9-1 Interference in Safety-Related Instrumentation and Control Systems (Rev. 1, October 2003) 1.181 Content of Updated Final Safety Not referenced; Analysis Report in Accordance with see Appendix 1AA 10 CFR 50.71(e) (Rev. 0, September 1999) 1.182 Assessing and Managing Risk Before 16 (TS Bases SR 3.0.3)
Maintenance Activities at Nuclear 17.6 (NEI 07-02A)
Power Plants (Rev. 0, May 2000) 1.183 Alternative Radiological Source Terms 16 (TS Bases 3.7.5) for Evaluating Design Basis Accidents 16 (TS Bases 3.9.4) at Nuclear Power Reactors (Rev. 0, 16 (TS Bases 3.9.7)
July 2000) 1.184 Decommissioning of Nuclear Power Not referenced; Reactors (Rev. 0, July 2000) see Appendix 1AA 1.185 Standard Format and Content for Post- Not referenced; shutdown Decommissioning Activities see Appendix 1AA Report (Rev. 0, July 2000) 1.9-18 Revision 3
TABLE 1.9-201 (Sheet 11 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.186 Guidance and Examples for Identifying Not referenced; 10 CFR 50.2 Design Bases (Rev. 0, see Appendix 1AA December 2000) 1.187 Guidance for Implementation of Not referenced; 10 CFR 50.59, Changes, Tests, and see Appendix 1AA Experiment (Rev. 0, November 2000) 1.188 Standard Format and Content for Not referenced; Applications To Renew Nuclear Power see Appendix 1AA Plant Operating Licenses (Rev. 1, September 2005) 1.189 Fire Protection for Nuclear Power 9.5.1.8.1.1 Plants (Rev. 1, March 2007) 9.5.1.8.2.2 Appendix 9A 13.1.2.1.2.9 17.5 (QAPD III.2) 1.191 Fire Protection Program for Nuclear Not referenced; Power Plants During see Appendix 1AA Decommissioning and Permanent Shutdown (Rev. 0, May 2001) 1.192 Operation and Maintenance Code 3.9.6.3 Case Acceptability, ASME OM Code (Rev. 0, June 2003) 1.193 ASME Code Cases Not Approved for Not referenced; Use (Rev 1, August 2005) see Appendix 1AA 1.194 Atmospheric Relative Concentrations 2.3.4.3 for Control Room Radiological Habitability Assessments at Nuclear Power Plants (Rev. 0, June 2003) 1.195 Methods and Assumptions for Not referenced; Evaluating Radiological see Appendix 1AA Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors (Rev. 0, May 2003) 1.9-19 Revision 3
TABLE 1.9-201 (Sheet 12 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.196 Control Room Habitability at Light- 6.4.3 Water Nuclear Power Reactors (Rev. 1, January 2007) 1.197 Demonstrating Control Room DCD discussion only; Envelope Integrity at Nuclear Power see DCD Table 1.9-1 Reactors (Rev. 0, February 2003) 1.198 Procedures and Criteria for Assessing 2.5.4.8 Seismic Soil Liquefaction at Nuclear Power Plant Sites (Rev. 0, November 2003) 1.199 Anchoring Components and Structural Not referenced; Supports in Concrete (Rev. 0, see Appendix 1AA November 2003) 1.200 An Approach for Determining the 19.59.10.6 Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (Rev. 1, January 2007) 1.201 Guidelines for Categorizing Structures, Not referenced; Systems, and Components in Nuclear see Appendix 1AA Power Plants According to Their Safety Significance (Rev. 1, May 2006) 1.202 Standard Format and Content of Not referenced; Decommissioning Cost Estimates for see Appendix 1AA Nuclear Power Reactors (Rev. 0, February 2005) 1.203 Transient and Accident Analysis Not referenced; Methods (Rev. 0, December 2005) see Appendix 1AA 1.204 Guidelines for Lightning Protection of Table 8.1-201 Nuclear Power Plants (Rev. 0, November 2005) 1.205 Risk-Informed, Performance-Based Not referenced; Fire Protection for Existing Light-Water see Appendix 1AA Nuclear Power Plants (Rev. 0, May 2006) 1.9-20 Revision 3
TABLE 1.9-201 (Sheet 13 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 1.206 Combined License Applications for See Appendix 1AA.
Nuclear Power Plants (LWR Edition) 1.1.6.1 (Rev. 0, June 2007) 2.0 2.5 2.5.1 2.5.4 14.3.2.3.1 14.3.2.3.2 Table 8.1-201 Appendix 12AA (NEI 07-03A) 1.207 Guidelines for Evaluating Fatigue Not referenced; Analyses Incorporating the Life see Appendix 1AA Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Rev. 0, March 2007) 1.208 A Performance-Based Approach to 2.5.1 Define the Site-Specific Earthquake 2.5.2 Ground Motion (Rev. 0, March 2007) 2.5.3 2.5.4 1.209 Guidelines for Environmental Not referenced; Qualification of Safety-Related see Appendix 1AA Computer-Based Instrumentation and Control Systems in Nuclear Power Plants (Rev. 0, March 2007)
Division 4 Regulatory Guides 4.7 General Site Suitability Criteria for Not referenced; Nuclear Power Stations (Rev. 2, April see Appendix 1AA 1998) 4.15 Quality Assurance for Radiological 11.5.3 Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent Streams and the Environment (Rev. 2, July 2007) 1.9-21 Revision 3
TABLE 1.9-201 (Sheet 14 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 4.15 Quality Assurance for Radiological 11.5.1.2 Monitoring Programs (Inception 11.5.3 through Normal Operations to License 11.5.4 Termination) Effluent Streams and 11.5.6.5 the Environment (Rev. 1, February 1979)
Division 5 Regulatory Guides 5.9 Guidelines for Germanium Not referenced; Spectroscopy Systems for see Appendix 1AA Measurements of Special Nuclear Material (Rev. 2, December 1983) 5.12 General Use of Locks in the Protection Not referenced; and Controls of Facilities and Special see Appendix 1AA Nuclear Materials (Rev. 0, November 1973) 5.65 Vital Area Access Controls, Protection Not referenced; of Physical Security Equipment, and see Appendix 1AA Key and Lock Controls (Rev. 0, September 1986)
Division 8 Regulatory Guides 8.2 Guide for Administrative Practices in 12.1 (NEI 07-08A)
Radiation Monitoring (Rev. 0, February 12.3.4 1973) Appendix 12AA (NEI 07-03A) 8.4 Direct-Reading and Indirect-Reading Appendix 12AA (NEI 07-03A)
Pocket Dosimeters (Rev. 0, February 1973) 8.5 Criticality and Other Interior Appendix 12AA (NEI 07-03A)
Evacuation Signals (Rev. 1, March 1981) 8.6 Standard Test Procedure for Geiger- Appendix 12AA (NEI 07-03A)
Muller Counters (Rev. 0, May 1973) 8.7 Instructions for Recording and 12.1 (NEI 07-08A)
Reporting Occupational Radiation Appendix 12AA (NEI 07-03A)
Exposure Data (Rev. 2, November 2005) 1.9-22 Revision 3
TABLE 1.9-201 (Sheet 15 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 8.8 Information Relevant to Ensuring That 12.1 (NEI 07-08A)
Occupational Radiation Exposures at 12.3.4 Nuclear Power Stations Will Be as Low Appendix 12AA as Is Reasonably Achievable (Rev. 3, Appendix 12AA (NEI 07-03A)
June 1978) 13.1.2.1.1 13.1.2.1.1.5 8.9 Acceptable Concepts, Models, 12.1 (NEI 07-08A)
Equations, and Assumptions for a Appendix 12AA (NEI 07-03A)
Bioassay Program (Rev. 1, July 1993) 8.10 Operating Philosophy for Maintaining 12.1 (NEI 07-08A)
Occupational Radiation Exposures as 12.3.4 Low as Is Reasonably Achievable Appendix 12AA (Rev. 1-R, May 1977) Appendix 12AA (NEI 07-03A) 13.1.2.1.1 13.1.2.1.1.5 8.13 Instruction Concerning Prenatal 12.1 (NEI 07-08A)
Radiation Exposure (Rev. 3, June Appendix 12AA (NEI 07-03A) 1999) 8.15 Acceptable Programs for Respiratory 12.1 (NEI 07-08A)
Protection (Rev. 1, October 1999) Appendix 12AA (NEI 07-03A) 8.27 Radiation Protection Training for 12.1 (NEI 07-08A)
Personnel at Light-Water-Cooled Appendix 12AA (NEI 07-03A)
Nuclear Power Plants (Rev. 0, March 1981) 8.28 Audible-Alarm Dosimeters (Rev. 0, 12.1 (NEI 07-08A)
August 1981) Appendix 12AA (NEI 07-03A) 8.29 Instruction Concerning Risks from 12.1 (NEI 07-08A)
Occupational Radiation Exposure Appendix 12AA (NEI 07-03A)
(Rev. 1, February 1996) 8.34 Monitoring Criteria and Methods To 12.1 (NEI 07-08A)
Calculate Occupational Radiation Appendix 12AA (NEI 07-03A)
Doses (Rev. 0, July 1992) 8.35 Planned Special Exposures (Rev. 0, 12.1 (NEI 07-08A)
June 1992) Appendix 12AA (NEI 07-03A) 1.9-23 Revision 3
TABLE 1.9-201 (Sheet 16 of 16)
COL 1.9-1 REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES FSAR Chapter, Section, or Regulatory Guides Subsectiona 8.36 Radiation Dose to the Embryo/Fetus 12.1 (NEI 07-08A)
(Rev. 0, July 1992) Appendix 12AA (NEI 07-03A) 8.38 Control of Access to High and Very 12.1 (NEI 07-08A)
High Radiation Areas of Nuclear Appendix 12AA Plants (Rev. 1, May 2006) Table 12AA-201 Appendix 12AA (NEI 07-03A)
- a. NEI templates are incorporated by reference. See Table 1.6-201.
1.9-24 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 1 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 1 Introduction and Interfaces, Initial Issuance, N/A No specific acceptance 03/2007 criteria associated with these general requirements.
2.0 Site Characteristics and Site Parameters, Initial N/A No specific acceptance Issuance, 03/2007 criteria are identified.
2.1.1 Site Location and Description Acceptable 2.1.2 Exclusion Area Authority and Control Acceptable 2.1.3 Population Distribution Exception For consistency between the ER and the FSAR, population calculations are based upon distance units of kilometers rather than miles.
2.2.1 - 2.2.2 Identification of Potential Hazards in Site Vicinity Acceptable 2.2.3 Evaluation of Potential Accidents Acceptable 2.3.1 Regional Climatology Acceptable 2.3.2 Local Meteorology Acceptable 2.3.3 Onsite Meteorological Measurements Programs Acceptable 2.3.4 Short-Term Atmospheric Dispersion Estimates Acceptable for Accident Releases 2.3.5 Long-Term Atmospheric Dispersion Estimates Acceptable for Routine Releases 2.4.1 Hydrologic Description Acceptable 2.4.2 Floods, Rev. 4, 03/2007 Acceptable 1.9-25 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 2 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 2.4.3 Probable Maximum Flood (PMF) on Streams and Acceptable Rivers, Rev. 4, 03/2007 2.4.4 Potential Dam Failures Acceptable 2.4.5 Probable Maximum Surge and Seiche Flooding Acceptable 2.4.6 Probable Maximum Tsunami Hazards Acceptable 2.4.7 Ice Effects Acceptable 2.4.8 Cooling Water Canals and Reservoirs Acceptable 2.4.9 Channel Diversions Acceptable 2.4.10 Flooding Protection Requirements Acceptable 2.4.11 Low Water Considerations Acceptable 2.4.12 Groundwater Acceptable 2.4.13 Accidental Releases of Radioactive Liquid Acceptable Effluents in Ground and Surface Waters 2.4.14 Technical Specifications and Emergency Acceptable Operation Requirements 2.5.1 Basic Geologic and Seismic Information, Rev.4, Acceptable 03/2007 1.9-26 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 3 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 2.5.2 Vibratory Ground Motion, Rev. 4, 03/2007 Exception Exception is taken to the guidance in RG 1.206 (C.III.1-2.5.2.4) that 0.05 and 0.95 fractile hazard curves be provided. These were not run. Hazard curves were run at 0.15 and 0.85th percentile instead of 0.16 and 0.84th as they are very close approximations (+/- 1 sigma).
100Hz amplitude frequencies for mean and fractile rock UHS were not run; instead 0.5Hz was run.
Exception Exception is taken to the guidance in RG 1.206 (C.III.1-2.5.2.5) for providing a table showing frequencies ranging from 0.1 to 100 Hertz. The table is not provided because site response of bedcode was not run and is insignificant.
2.5.3 Surface Faulting, Rev. 4, 03/2007 Acceptable 2.5.4 Stability of Subsurface Materials and Acceptable Foundations 1.9-27 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 4 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 2.5.5 Stability of Slopes Acceptable 3.2.1 Seismic Classification, Rev. 2, 03/2007 See Notes d and e.
3.2.2 System Quality Group Classification, Rev. 2, See Notes d and e.
03/2007 3.3.1 Wind Loadings Acceptable See Notes d, e, and f.
3.3.2 Tornado Loadings Acceptable See Notes d, e, and f.
3.4.1 Internal Flood Protection for Onsite Equipment Acceptable See Notes d, e, and f.
Failures 3.4.2 Analysis Procedures See Notes d and e.
3.5.1.1 Internally Generated Missiles (Outside See Notes d and e.
Containment) 3.5.1.2 Internally Generated Missiles (Inside See Notes d and e.
Containment) 3.5.1.3 Turbine Missiles Acceptable See Notes d, e, and f.
3.5.1.4 Missiles Generated by Tornadoes and Extreme See Notes d and e.
Winds 3.5.1.5 Site Proximity Missiles (Except Aircraft), Rev.4, Acceptable See Notes d, e, and f.
03/2007 3.5.1.6 Aircraft Hazards Acceptable See Notes d, e, and f. Aircraft hazard event probability is consistent with SRP 2.2.3, Rev. 3, Technical Rationale 2.
1.9-28 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 5 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 3.5.2 Structures, Systems, and Components to be See Notes d and e.
Protected from Externally-Generated Missiles 3.5.3 Barrier Design Procedures See Notes d and e.
3.6.1 Plant Design for Protection Against Postulated See Notes d and e.
Piping Failures in Fluid Systems Outside Containment 3.6.2 Determination of Rupture Locations and Acceptable See Notes d, e, and f.
Dynamic Effects Associated with the Postulated Rupture of Piping, Rev. 2, 03/2007 3.6.3 Leak-Before-Break Evaluation Procedures, Acceptable See Notes d, e, and f.
Rev. 1, 03/2007 3.7.1 Seismic Design Parameters See Notes d and e.
3.7.2 Seismic System Analysis Acceptable See Notes d, e, and f.
3.7.3 Seismic Subsystem Analysis See Notes d and e.
3.7.4 Seismic Instrumentation, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
3.8.1 Concrete Containment, Rev. 2, 03/2007 See Notes d and e.
3.8.2 Steel Containment, Rev. 2, 03/2007 See Notes d and e.
3.8.3 Concrete and Steel Internal Structures of Steel or See Notes d and e.
Concrete Containments, Rev. 2, 03/2007 3.8.4 Other Seismic Category I Structures, Rev. 2, See Notes d and e.
03/2007 3.8.5 Foundations, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
3.9.1 Special Topics for Mechanical Components See Notes d and e.
1.9-29 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 6 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 3.9.2 Dynamic Testing and Analysis of Systems, See Notes d and e.
Structures, and Components 3.9.3 ASME Code Class 1, 2, and 3 Components, Acceptable See Notes d, e, and f.
Component Supports, and Core Support Structures, Rev. 2, 03/2007 3.9.4 Control Rod Drive Systems See Notes d and e.
3.9.5 Reactor Pressure Vessel Internals See Notes d and e.
3.9.6 Functional Design, Qualification, and Inservice Acceptable See Notes d, e, and f.
Testing Programs for Pumps, Valves, and Dynamic Restraints 3.9.7 Risk-Informed Inservice Testing, Rev. 0, 08/1998 N/A 3.9.8 Risk-Informed Inservice Inspection of Piping, N/A Rev.0, 09/2003 3.10 Seismic and Dynamic Qualification of See Notes d and e.
Mechanical and Electrical Equipment 3.11 Environmental Qualification of Mechanical and Acceptable See Notes d, e, and f.
Electrical Equipment 3.12 ASME Code Class 1, 2, and 3 Piping Systems, See Note g.
Piping Components and their Associated Supports, Initial Issuance, 03/2007 3.13 Threaded Fasteners - ASME Code Class 1, 2, See Note g.
and 3, Initial Issuance, 03/2007 4.2 Fuel System Design See Notes d and e.
4.3 Nuclear Design See Notes d and e.
1.9-30 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 7 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 4.4 Thermal and Hydraulic Design, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
4.5.1 Control Rod Drive Structural Materials See Notes d and e.
4.5.2 Reactor Internal and Core Support Structure See Notes d and e.
Materials 4.6 Functional Design of Control Rod Drive System, See Notes d and e.
Rev. 2, 03/2007 5.2.1.1 Compliance with the Codes and Standards Rule, Acceptable See Notes d, e, and f.
10 CFR 50.55a 5.2.1.2 Applicable Code Cases See Notes d and e.
5.2.2 Overpressure Protection See Notes d and e.
5.2.3 Reactor Coolant Pressure Boundary Materials Acceptable See Notes d, e, and f.
5.2.4 Reactor Coolant Pressure Boundary Inservice Acceptable See Notes d, e, and f.
Inspection and Testing, Rev. 2, 03/2007 5.2.5 Reactor Coolant Pressure Boundary Leakage See Notes d and e.
Detection, Rev. 2, 03/2007 5.3.1 Reactor Vessel Materials, Rev. 2, 03/2007 See Notes d and e.
5.3.2 Pressure-Temperature Limits, Upper-Shelf Acceptable See Notes d, e, and f.
Energy, and Pressurized Thermal Shock, Rev. 2, 03/2007 5.3.3 Reactor Vessel Integrity, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
5.4 Reactor Coolant System Component and N/A No specific acceptance Subsystem Design, Rev. 2, 03/2007 criteria associated with these general requirements.
5.4.1.1 Pump Flywheel Integrity (PWR), Rev. 2, 03/2007 See Notes d and e.
1.9-31 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 8 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 5.4.2.1 Steam Generator Materials See Notes d and e.
5.4.2.2 Steam Generator Program, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
5.4.6 Reactor Core Isolation Cooling System (BWR), N/A Rev. 4, 03/2007 5.4.7 Residual Heat Removal (RHR) System, Rev. 4, See Notes d and e.
03/2007 5.4.8 Reactor Water Cleanup System (BWR) N/A 5.4.11 Pressurizer Relief Tank See Notes d and e.
5.4.12 Reactor Coolant System High Point Vents, See Notes d and e.
Rev. 1, 03/2007 5.4.13 Isolation Condenser System (BWR), Initial N/A Issuance, 03/2007 6.1.1 Engineered Safety Features Materials, Rev. 2, Acceptable See Notes d, e, and f.
03/2007 6.1.2 Protective Coating Systems (Paints) - Organic Acceptable See Notes d, e, and f.
Materials 6.2.1 Containment Functional Design See Notes d and e.
6.2.1.1.A PWR Dry Containments, Including See Notes d and e.
Subatmospheric Containments 6.2.1.1.B Ice Condenser Containments, Rev. 2, 07/1981 N/A 6.2.1.1.C Pressure-Suppression Type BWR Containments, N/A Rev. 7, 03/2007 6.2.1.2 Subcompartment Analysis See Notes d and e.
1.9-32 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 9 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 6.2.1.3 Mass and Energy Release Analysis for See Notes d and e.
Postulated Loss-of-Coolant Accidents (LOCAs) 6.2.1.4 Mass and Energy Release Analysis for See Notes d and e.
Postulated Secondary System Pipe Ruptures, Rev. 2, 03/2007 6.2.1.5 Minimum Containment Pressure Analysis for See Notes d and e.
Emergency Core Cooling System Performance Capability Studies 6.2.2 Containment Heat Removal Systems, Rev. 5, See Notes d and e.
03/2007 6.2.3 Secondary Containment Functional Design See Notes d and e.
6.2.4 Containment Isolation System See Notes d and e.
6.2.5 Combustible Gas Control in Containment Acceptable See Notes d, e, and f.
1.9-4 6.2.6 Containment Leakage Testing Exception See Notes d, e, and f. The Exception is taken to the guidance in SRP Section II, item 4 in that the proposed acceptable containment leakage rate is less than 0.10% of containment air by weight.
6.2.7 Fracture Prevention of Containment Pressure See Notes d and e.
Boundary, Rev. 1, 03/2007 6.3 Emergency Core Cooling System Acceptable See Notes d, e, and f.
6.4 Control Room Habitability System Acceptable See Notes d, e, and f.
1.9-33 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 10 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 6.5.1 ESF Atmosphere Cleanup Systems See Notes d and e.
6.5.2 Containment Spray as a Fission Product See Notes d and e.
Cleanup System, Rev. 4, 03/2007 6.5.3 Fission Product Control Systems and Structures See Notes d and e.
6.5.4 Ice Condenser as a Fission Product Cleanup N/A System, Rev. 3, 12/1988 6.5.5 Pressure Suppression Pool as a Fission Product N/A Cleanup System, Rev. 1, 03/2007 6.6 Inservice Inspection and Testing of Class 2 and 3 Acceptable See Notes d, e, and f.
Components, Rev. 2, 03/2007 6.7 Main Steam Isolation Valve Leakage Control N/A System (BWR), Rev. 2, 07/1981 7 Instrumentation and Controls -Overview of See Notes d and e.
Review Process, Rev. 5, 03/2007 Appendix 7.0-A Review Process for Digital Instrumentation and See Notes d and e.
Control Systems, Rev. 5, 03/2007 7.1 Instrumentation and Controls -Introduction, See Notes d and e.
Rev. 5, 03/2007 7.1-T Table 7-1 Regulatory Requirements, Acceptance Criteria, See Notes d and e.
and Guidelines for Instrumentation and Control Systems Important to Safety, Rev. 5, 03/2007 Appendix 7.1-A Acceptance Criteria and Guidelines for See Notes d and e.
Instrumentation and Controls Systems Important to Safety, Rev. 5, 03/2007 1.9-34 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 11 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions Appendix 7.1-B Guidance for Evaluation of Conformance to IEEE See Notes d and e.
Std 279, Rev. 5, 03/2007 Appendix 7.1-C Guidance for Evaluation of Conformance to IEEE See Notes d and e.
Std 603, Rev. 5, 03/2007 Appendix 7.1-D Guidance for Evaluation of the Application of See Notes d and e.
IEEE Std 7-4.3.2 Initial Issuance 03/2007 7.2 Reactor Trip System, Rev. 5, 03/2007 See Notes d and e.
7.3 Engineered Safety Features Systems, Rev. 5, See Notes d and e.
03/2007 7.4 Safe Shutdown Systems, Rev. 5, 03/2007 See Notes d and e.
7.5 Information Systems Important to Safety, Rev. 5, See Notes d and e.
03/2007 7.6 Interlock Systems Important to Safety, Rev. 5, See Notes d and e.
03/2007 7.7 Control Systems, Rev. 5, 03/2007 See Notes d and e.
7.8 Diverse Instrumentation and Control Systems, See Notes d and e.
Rev. 5, 03/2007 7.9 Data Communication Systems, Rev. 5, 03/2007 See Notes d and e.
8.1 Electric Power - Introduction N/A No specific acceptance criteria associated with these general requirements.
8.2 Offsite Power System, Rev. 4, 03/2007 Acceptable See Notes d, e, and f 8.3.1 A-C Power Systems (Onsite) Acceptable See Notes d, e, and f.
8.3.2 D-C Power Systems (Onsite) Acceptable See Notes d, e, and f.
1.9-35 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 12 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 8.4 Station Blackout, Initial Issuance, 03/2007 See Note g.
9.1.1 Criticality Safety of Fresh and Spent Fuel See Notes d and e.
Storage and Handling 9.1.2 New and Spent Fuel Storage, Rev. 4, 03/2007 See Notes d and e.
9.1.3 Spent Fuel Pool Cooling and Cleanup System, See Notes d and e.
Rev. 2, 03/2007 9.1.4 Light Load Handling System (Related to Acceptable See Notes d, e, and f.
Refueling) 9.1.5 Overhead Heavy Load Handling Systems, Acceptable See Notes d, e, and f.
Rev. 1, 03/2007 9.2.1 Station Service Water System, Rev. 5, 03/2007 Acceptable See Notes d, e, and f.
9.2.2 Reactor Auxiliary Cooling Water Systems, See Notes d and e.
Rev. 4, 03/2007 9.2.4 Potable and Sanitary Water Systems See Notes d and e.
9.2.5 Ultimate Heat Sink Acceptable See Notes d, e, and f.
9.2.6 Condensate Storage Facilities Acceptable See Notes d, e, and f.
9.3.1 Compressed Air System, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
9.3.2 Process and Post-accident Sampling Systems See Notes d and e.
9.3.3 Equipment and Floor Drainage System See Notes d and e.
9.3.4 Chemical and Volume Control System (PWR) See Notes d and e.
(Including Boron Recovery System) 9.3.5 Standby Liquid Control System (BWR) N/A 9.4.1 Control Room Area Ventilation System Acceptable See Notes d, e, and f.
1.9-36 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 13 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 9.4.2 Spent Fuel Pool Area Ventilation System See Notes d and e.
9.4.3 Auxiliary and Radwaste Area Ventilation System See Notes d and e.
9.4.4 Turbine Area Ventilation System See Notes d and e.
9.4.5 Engineered Safety Feature Ventilation System See Notes d and e.
9.5.1 Fire Protection Program, Rev. 5, 03/2007 Acceptable See Notes d, e, and f.
9.5.2 Communications Systems Acceptable See Notes d, e, and f.
9.5.3 Lighting Systems See Notes d and e.
9.5.4 Emergency Diesel Engine Fuel Oil Storage and Acceptable See Notes d, e, and f.
Transfer System 9.5.5 Emergency Diesel Engine Cooling Water System See Notes d and e.
9.5.6 Emergency Diesel Engine Starting System See Notes d and e.
9.5.7 Emergency Diesel Engine Lubrication System See Notes d and e.
9.5.8 Emergency Diesel Engine Combustion Air Intake See Notes d and e.
and Exhaust System 10.2 Turbine Generator Acceptable See Notes d, e, and f.
10.2.3 Turbine Rotor Integrity, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
10.3 Main Steam Supply System, Rev. 4, 03/2007 Acceptable See Notes d, e, and f.
10.3.6 Steam and Feedwater System Materials Acceptable See Notes d, e, and f.
10.4.1 Main Condensers See Notes d and e.
10.4.2 Main Condenser Evacuation System Acceptable See Notes d, e, and f.
10.4.3 Turbine Gland Sealing System See Notes d and e.
10.4.4 Turbine Bypass System See Notes d and e.
10.4.5 Circulating Water System Acceptable See Notes d, e, and f.
1.9-37 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 14 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 10.4.6 Condensate Cleanup System See Notes d and e.
10.4.7 Condensate and Feedwater System, Rev. 4, Acceptable See Notes d, e, and f.
03/2007 10.4.8 Steam Generator Blowdown System (PWR) See Notes d and e.
10.4.9 Auxiliary Feedwater System (PWR) See Notes d and e.
11.1 Source Terms See Notes d and e.
11.2 Liquid Waste Management System Acceptable See Notes d, e, and f.
11.3 Gaseous Waste Management System Acceptable See Notes d, e, and f.
11.4 Solid Waste Management System Acceptable See Notes d, e, and f.
11.5 Process and Effluent Radiological Monitoring Acceptable See Notes d, e, and f.
Instrumentation and Sampling Systems, Rev. 4, 03/2007 1.9-38 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 15 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 12.1 Assuring that Occupational Radiation Exposures Exception See Notes d, e, and f.
Are As Low As Is Reasonably Achievable An exception is taken to following the guidance of RG 1.206 to address RG 8.20, 8.25, and RG 8.26.
NUREG-1736, Final Report (published 2001) lists RG 8.20 and RG 8.26 as outdated and recommends the methods of RG 8.9 R1.
RG 8.25 states it is not applicable to nuclear facilities licensed under 10 CFR Part 50, and, by extension, to 10 CFR Part 52.
An exception is taken to RG 8.8 C.3.b. RG 1.16 C.1.b (3) data is no longer reported.
Reporting per C.1.b (2) is also no longer required.
1.9-39 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 16 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 12.2 Radiation Sources Exception See Notes d, e, and f.
A general description of miscellaneous sealed sources related to radiography is provided in FSAR text. Other requested details are maintained on-site for NRC review and audit upon their procurement.
12.3 - 12.4 Radiation Protection Design Features Acceptable See Notes d, e, and f.
12.5 Operational Radiation Protection Program Acceptable See Notes d, e, and f.
1.9-40 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 17 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 13.1.1 Management and Technical Support Exception See Notes d, e, and f.
Organization, Rev. 5, 03/2007 Design and construction responsibilities are not defined in numbers.
The experience requirements of corporate staff are set by corporate policy and not provided here in detail, however the experience level of the corporate staff, as discussed Subsections 13.1.1, 13.1.1.1, and Appendix 13AA, in the area of nuclear plant development, construction, and management establishes that the applicant has the necessary capability and staff to ensure that design and construction of the facility will be performed in an acceptable manor.
1.9-41 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 18 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions Resumes and/or other documentation of qualification and experience of initial appointees to appropriate management and supervisory positions are available for NRC after position vacancies are filled.
13.1.2 - 13.1.3 Operating Organization, Rev. 6, 03/2007 Exception See Notes d, e, and f. The SRP requires resumes of personnel holding plant managerial and supervisory positions to be included in the FSAR. Current industry practice is to have the resumes available for review by the regulator when requested but not be kept in the FSAR. Additionally, at time of COLA, most positions are unfilled.
1.9-42 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 19 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 13.2.1 Reactor Operator Requalification Program; Exception See Notes d, e, and f. SRP Reactor Operator Training requires meeting the guidance of NUREG-0711.
NEI 06-13A, Technical Report on a Template for an Industry Training Program Description, which is incorporated by reference in FSAR 13.2, does not address meeting the guidance of NUREG-0711. NEI 06-13A, is approved by NRC to meet the regulatory requirements for the FSAR description of the Training Program.
SRP requires meeting the guidance of Regulatory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations RG 1.149 is not addressed in NEI 06-13A. Level of detail is consistent with NEI 06-13A.
1.9-43 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 20 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b) (c)
Criteria Section Criteria Position Exceptions 13.2.2 Non-Licensed Plant Staff Training Exception See Notes d, e, and f. Level of detail is consistent with NEI 06-13A.
13.3 Emergency Planning Acceptable See Notes d, e, and f.
13.4 Operational Programs Acceptable See Notes d, e, and f.
13.5.1.1 Administrative Procedures - General, Initial Exception The procedure development Issuance, 03/2007 schedule is addressed in the COL application (not in the SAR as requested by this SRP).
13.5.2.1 Operating and Emergency Operating Exception See Notes d, e, and f.
Procedures, Rev. 2, 03/2007 Procedures are generally identified in this section by topic, type, or classification in lieu of the specific title and represent general areas of procedural coverage.
13.6 Physical Security Acceptable See Security Plan developed in accordance with NEI 03-12.
13.6.1 Physical Security - Combined License Review Acceptable See Security Plan developed Responsibilities, Initial Issuance, 03/2007 in accordance with NEI 03-12 13.6.2 Physical Security - Design Certification, Initial See notes d and e.
Issuance, 03/2007 1.9-44 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 21 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 13.6.3 Physical Security - Early Site Permit, Initial N/A Issuance, 03/2007 14.2 Initial Plant Test Program - Design Certification Exception See Notes d, e, and f. The and New License Applicants level of detail is consistent with DCD section content addressing nonsafety-related systems.
14.2.1 Generic Guidelines for Extended Power Uprate N/A No power uprate is sought.
Testing Programs, Initial Issuance, 08/2006 14.3 Inspections, Tests, Analyses, and Acceptance Acceptable Criteria, Initial Issuance, 03/2007 14.3.1 [Reserved]
14.3.2 Structural and Systems Engineering - See Notes d and e.
Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.3 Piping Systems and Components - Inspections, See Notes d and e.
Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.4 Reactor Systems - Inspections, Tests, Analyses, See Notes d and e.
and Acceptance Criteria, Initial Issuance, 03/2007 14.3.5 Instrumentation and Controls - Inspections, See Notes d and e.
Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 1.9-45 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 22 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 14.3.6 Electrical Systems - Inspections, Tests, See Notes d and e.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.7 Plant Systems - Inspections, Tests, Analyses, Acceptable See Notes d, e, and f.
and Acceptance Criteria, Initial Issuance, 03/2007 14.3.8 Radiation Protection - Inspections, Tests, See Notes d and e.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.9 Human Factors Engineering - Inspections, Tests, See Notes d and e.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.10 Emergency Planning - Inspections, Tests, Acceptable See Notes d, e, and f.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.11 Containment Systems - Inspections, Tests, See Notes d and e.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 14.3.12 Physical Security Hardware - Inspections, Tests, Acceptable See Notes d, e, and f.
Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 15 Introduction - Transient and Accident Analysis See Notes d and e.
15.0.1 Radiological Consequence Analyses Using See Notes d and e.
Alternative Source Terms, Rev. 0, 07/2000 1.9-46 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 23 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 15.0.2 Review of Transient and Accident Analysis See Notes d and e.
Method, Rev. 0, 12/2005 15.0.3 Design Basis Accident Radiological See Notes d and e.
Consequences of Analyses for Advanced Light Water Reactors, Initial Issuance, 03/2007 15.1.1 - 15.1.4 Decrease in Feedwater Temperature, Increase in See Notes d and e.
Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve, Rev. 2, 03/2007 15.1.5 Steam System Piping Failures Inside and See Notes d and e.
Outside of Containment (PWR) 15.2.1 - 15.2.5 Loss of External Load; Turbine Trip; Loss of See Notes d and e.
Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed), Rev. 2, 03/2007 15.2.6 Loss of Nonemergency AC Power to the Station See Notes d and e.
Auxiliaries, Rev. 2, 03/2007 15.2.7 Loss of Normal Feedwater Flow See Notes d and e.
15.2.8 Feedwater System Pipe Breaks Inside and See Notes d and e.
Outside Containment (PWR), Rev. 2, 03/2007 15.3.1 - 15.3.2 Loss of Forced Reactor Coolant Flow Including See Notes d and e.
Trip of Pump Motor and Flow Controller Malfunctions, Rev. 2, 03/2007 15.3.3 - 15.3.4 Reactor Coolant Pump Rotor Seizure and See Notes d and e.
Reactor Coolant Pump Shaft Break 1.9-47 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 24 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 15.4.1 Uncontrolled Control Rod Assembly Withdrawal See Notes d and e.
from a Subcritical or Low Power Startup Condition 15.4.2 Uncontrolled Control Rod Assembly Withdrawal See Notes d and e.
at Power 15.4.3 Control Rod Misoperation (System Malfunction See Notes d and e.
or Operator Error) 15.4.4 - 15.4.5 Startup of an Inactive Loop or Recirculation Loop See Notes d and e.
at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate, Rev. 2, 03/2007 15.4.6 Inadvertent Decrease in Boron Concentration in See Notes d and e.
the Reactor Coolant System (PWR), Rev. 2, 03/2007 15.4.7 Inadvertent Loading and Operation of a Fuel See Notes d and e.
Assembly in an Improper Position, Rev. 2, 03/2007 15.4.8 Spectrum of Rod Ejection Accidents (PWR) See Notes d and e.
15.4.8.A Radiological Consequences of a Control Rod See Notes d and e.
Ejection Accident (PWR), Rev. 1, 07/1981 15.4.9 Spectrum of Rod Drop Accidents (BWR) N/A 15.5.1 - 15.5.2 Inadvertent Operation of ECCS and Chemical See Notes d and e.
and Volume Control System Malfunction that Increases Reactor Coolant Inventory, Rev. 2, 03/2007 1.9-48 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 25 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 15.6.1 Inadvertent Opening of a PWR Pressurizer See Notes d and e.
Pressure Relief Valve or a BWR Pressure Relief Valve, Rev. 2, 03/2007 15.6.5 Loss-of-Coolant Accidents Resulting From See Notes d and e.
Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary 15.8 Anticipated Transients Without Scram, Rev. 2, See Notes d and e.
03/2007 15.9 Boiling Water Reactor Stability, Initial Issuance, N/A 03/2007 16 Technical Specifications Acceptable See Notes d, e, and f.
16.1 Risk-informed Decision Making: Technical N/A This SRP applies to the Specifications, Rev. 1, 03/2007 Technical Specifications change process.
1.9-5 17.1 Quality Assurance During the Design and Acceptable See Notes d, e, and f.
Construction Phases, Rev. 2, 07/1981 This section covers the requirements of SRP Section 17.1 through reference to quality assurance plan which is maintained separately as described in FSAR Sections 17.1 and 17.5 17.2 Quality Assurance During the Operations Phase, See Notes d and e.
Rev. 2, 07/1981 1.9-49 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 26 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 17.3 Quality Assurance Program Description, Rev. 0, See Notes d and e.
08/1990 17.4 Reliability Assurance Program (RAP), Initial See Notes d and e.
Issuance, 03/2007 17.5 Quality Assurance Program Description - Design Acceptable See Notes d, e, and f. This Certification, Early Site Permit and New License section covers the Applicants, Initial Issuance, 03/2007 requirements of SRP Section 17.5 through reference to Quality Assurance Program Description which is maintained separately and developed in accordance with NEI 06-14A.
17.6 Maintenance Rule, Initial Issuance, 03/2007 Acceptable Content developed in accordance with NEI-07-02A 18.0 Human Factors Engineering, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
19.0 Probabilistic Risk Assessment and Severe Acceptable See Notes d, e, and f.
Accident Evaluation for New Reactors, Rev. 2, 06/2007 19.1 Determining the Technical Adequacy of Acceptable See Notes d, e, and f.
Probabilistic Risk Assessment Results for Risk-Informed Activities, Rev. 2, 06/2007 1.9-50 Revision 3
Part 2, FSAR TABLE 1.9-202 (Sheet 27 of 27)(a) 1.9-1 CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Reference FSAR Comments/Summary of (b)
Criteria Section Criteria Position (c) Exceptions 19.2 Review of Risk Information Used to Support See Note g.
Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, Initial Issuance, 06/2007 a) This table is provided as a one-time aid to facilitate NRC review. This table becomes historical information and need not be updated b) If no revision or date is specified, it is Rev. 3, 03/2007.
c) Consult the AP1000 Design Control Document (DCD) Appendix 1A and Appendix 1AA to determine extent of conformance with Regulatory Guides (except Regulatory Guide 1.206).
d) Conformance with a previous revision of this SRP is documented in AP1000 Design Control Document (Section 1.9.2 and WCAP-15799) e) Conformance with the design aspects of this SRP is as stated in the AP1000 DCD.
f) Conformance with the plant or site-specific aspects of this SRP is as stated under FSAR Position.
g) This SRP is not applicable to the AP1000 certified design.
1.9-51 Revision 3
TABLE 1.9-203 (Sheet 1 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria TMI Action Plan Items I.A.1.1 Shift Technical Advisor f Resolved per NUREG-0933 I.A.1.2 Shift Supervisor Administrative Duties f Resolved per NUREG-0933 I.A.1.3 Shift Manning f Resolved per NUREG-0933 I.A.1.4 Long-Term Upgrading f Resolved per NUREG-0933 I.A.2.1(1) Qualifications - Experience f Resolved per NUREG-0933 I.A.2.1(2) Immediate Upgrading of RO & SRO Training and f Resolved per Qualifications, Training NUREG-0933 I.A.2.1(3) Facility Certification of Competence and Fitness of f Resolved per Applicants for Operator and Senior Operator NUREG-0933 Licenses I.A.2.3 Administration of Training Programs f Resolved per NUREG-0933 I.A.2.4 NRR Participation in Inspector Training d Not applicable to new plants I.A.2.6(1) Revise Regulatory Guide 1.8 f Resolved per NUREG-0933 I.A.3.1 Revise Scope of Criteria for Licensing Examinations f Resolved per NUREG-0933 I.A.3.5 Establish Statement of Understanding with INPO d Not applicable and DOE to new plants I.A.4.1(2) Interim Changes in Training Simulators f Resolved per NUREG-0933 I.A.4.2(1) Research on Training Simulators f Resolved per NUREG-0933 I.A.4.2(2) Upgrade Training Simulator Standards f Resolved per NUREG-0933 I.A.4.2(3) Regulatory Guide on Training Simulators f Resolved per NUREG-0933 I.A.4.2(4) Review Simulators for Conformance to Criteria f Resolved per NUREG-0933 I.A.4.3 Feasibility Study of Procurement of NRC Training d Not applicable Simulator to new plants I.A.4.4 Feasibility Study of NRC Engineering Computer d Not applicable to new plants 1.9-52 Revision 3
TABLE 1.9-203 (Sheet 2 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria I.B.1.3(1) Require Licensees to Place Plant in Safest d Not applicable Shutdown Cooling Following a Loss of Safety to new plants Function Due to Personnel Error I.B.1.3(2) Use Existing Enforcement Options to Accomplish d Not applicable Safest Shutdown Cooling to new plants I.B.1.3(3) Use Non-Fiscal Approaches to Accomplish Safest d Not applicable Shutdown Cooling to new plants I.B.2.1(1) Verify the Adequacy of Management and d Not applicable Procedural Controls and Staff Discipline to new plants I.B.2.1(2) Verify that Systems Required to Be Operable Are d Not applicable Properly Aligned to new plants I.B.2.1(3) Follow-up on Completed Maintenance Work Orders d Not applicable to Ensure Proper Testing and Return to Service to new plants I.B.2.1(4) Observe Surveillance Tests to Determine Whether d Not applicable Test Instruments Are Properly Calibrated to new plants I.B.2.1(5) Verify that Licensees Are Complying with Technical d Not applicable Specifications to new plants I.B.2.1(6) Observe Routine Maintenance d Not applicable to new plants I.B.2.1(7) Inspect Terminal Boards, Panels, and Instrument d Not applicable Racks for Unauthorized Jumpers and Bypasses to new plants I.B.2.2 Resident Inspector at Operating Reactors d Not applicable to new plants I.B.2.3 Regional Evaluations d Not applicable to new plants I.B.2.4 Overview of Licensee Performance d Not applicable to new plants I.C.1(1) Small Break LOCAs f Resolved per NUREG-0933 I.C.1(2) Inadequate Core Cooling f Resolved per NUREG-0933 I.C.1(3) Transients and Accidents f Resolved per NUREG-0933 I.C.2 Shift and Relief Turnover Procedures f Resolved per NUREG-0933 I.C.3 Shift Supervisor Responsibilities f Resolved per NUREG-0933 I.C.4 Control Room Access f Resolved per NUREG-0933 I.C.6 Procedures for Verification of Correct Performance f Resolved per of Operating Activities NUREG-0933 1.9-53 Revision 3
TABLE 1.9-203 (Sheet 3 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria I.C.7 NSSS Vendor Review of Procedures f Resolved per NUREG-0933 I.C.8 Pilot Monitoring of Selected Emergency Procedures f Resolved per for Near-Term Operating License Applicants NUREG-0933 I.D.5(5) Disturbance Analysis Systems d Not applicable to new plants I.D.6 Technology Transfer Conference d Not applicable to new plants I.E.1 Office for Analysis and Evaluation of Operational d Not applicable Data to new plants I.E.2 Program Office Operational Data Evaluation d Not applicable to new plants I.E.3 Operational Safety Data Analysis d Not applicable to new plants I.E.4 Coordination of Licensee, Industry, and Regulatory d Not applicable Programs to new plants I.E.5 Nuclear Plant Reliability Data Systems d Not applicable to new plants I.E.6 Reporting Requirements d Not applicable to new plants I.E.7 Foreign Sources d Not applicable to new plants I.E.8 Human Error Rate Analysis d Not applicable to new plants I.F.2(6) Increase the Size of Licensees' QA Staff f Resolved per NUREG-0933 I.F.2(9) Clarify Organizational Reporting Levels for the QA f Resolved per Organization NUREG-0933 I.G.1 Training Requirements f Resolved per NUREG-0933 I.G.2 Scope of Test Program f Resolved per NUREG-0933 II.B.4 Training for Mitigating Core Damage f Resolved per NUREG-0933 II.B.5(1) Behavior of Severely Damaged Fuel d Not applicable to new plants II.B.5(2) Behavior of Core Melt d Not applicable to new plants II.B.5(3) Effect of Hydrogen Burning and Explosions on d Not applicable Containment Structures to new plants 1.9-54 Revision 3
TABLE 1.9-203 (Sheet 4 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria II.B.6 Risk Reduction for Operating Reactors at Sites with f Resolved per High Population Densities NUREG-0933 II.E.1.3 Update Standard Review Plan and Develop d Resolved per Regulatory Guide NUREG-0933 II.E.6.1 Test Adequacy Study d Resolved per NUREG-0933 II.F.5 Classification of Instrumentation, Control, and d Not applicable Electrical Equipment to new plants II.H.4 Determine Impact of TMI on Socioeconomic and d Not applicable Real Property Values to new plants II.J.1.1 Establish a Priority System for Conducting Vendor d Not applicable Inspections to new plants II.J.1.2 Modify Existing Vendor Inspection Program d Not applicable to new plants II.J.1.3 Increase Regulatory Control Over Present Non- d Not applicable Licensees to new plants II.J.1.4 Assign Resident Inspectors to Reactor Vendors and d Not applicable Architect-Engineers to new plants II.J.2.1 Reorient Construction Inspection Program d Not applicable to new plants II.J.2.2 Increase Emphasis on Independent Measurement d Not applicable in Construction Inspection Program to new plants II.J.2.3 Assign Resident Inspectors to All Construction Sites d Not applicable to new plants II.J.3.1 Organization and Staffing to Oversee Design and f Not applicable Construction to new plants II.J.4.1 Revise Deficiency Reporting Requirements f Resolved per NUREG-0933 II.K.1(1) Review TMI-2 PNs and Detailed Chronology of the f Resolved per TMI-2 Accident NUREG-0933 II.K.1(3) Review Operating Procedures for Recognizing, f Resolved per Preventing, and Mitigating Void Formation in NUREG-0933 Transients and Accidents II.K.1(4) Review Operating Procedures and Training f Resolved per Instructions NUREG-0933 II.K.1(5) Safety-Related Valve Position Description f Resolved per NUREG-0933 II.K.1(6) Review Containment Isolation Initiation Design and f Resolved per Procedures NUREG-0933 1.9-55 Revision 3
TABLE 1.9-203 (Sheet 5 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria II.K.1(9) Review Procedures to Assure That Radioactive f Resolved per Liquids and Gases Are Not Transferred out of NUREG-0933 Containment Inadvertently II.K.1(10) Review and Modify Procedures for Removing f Resolved per Safety-Related Systems from Service NUREG-0933 II.K.1(11) Make All Operating and Maintenance Personnel f Resolved per Aware of the Seriousness and Consequences of the NUREG-0933 Erroneous Actions Leading up to, and in Early Phases of, the TMI-2 Accident II.K.1(12) One Hour Notification Requirement and Continuous f Resolved per Communications Channels NUREG-0933 II.K.1(13) Propose Technical Specification Changes Reflecting f Resolved per Implementation of All Bulletin Items NUREG-0933 II.K.1(14) Review Operating Modes and Procedures to Deal f Resolved per with Significant Amounts of Hydrogen NUREG-0933 II.K.1(15) For Facilities with Non-Automatic AFW Initiation, f Resolved per Provide Dedicated Operator in Continuous NUREG-0933 Communication with CR to Operate AFW II.K.1(16) Implement Procedures That Identify PZR PORV f Resolved per "Open" Indications and That Direct Operator to NUREG-0933 Close Manually at "Reset" Setpoint II.K.1(17) Trip PZR Level Bistable so That PZR Low Pressure f Resolved per Will Initiate Safety Injection NUREG-0933 II.K.1(26) Revise Emergency Procedures and Train ROs and f Resolved per SROs NUREG-0933 II.K.3(3) Report Safety and Relief Valve Failures Promptly f Resolved per and Challenges Annually NUREG-0933 II.K.3(5) Automatic Trip of Reactor Coolant Pumps f Resolved per NUREG-0933 II.K.3(10) Anticipatory Trip Modification Proposed by Some f Resolved per Licensees to Confine Range of Use to High Power NUREG-0933 Levels II.K.3(11) Control Use of PORV Supplied by Control f Resolved per Components, Inc. Until Further Review Complete NUREG-0933 II.K.3(12) Confirm Existence of Anticipatory Trip Upon Turbine f Resolved per Trip NUREG-0933 II.K.3(30) Revised Small-Break LOCA Methods to Show f Resolved per Compliance with 10 CFR 50, Appendix K NUREG-0933 II.K.3(31) Plant-Specific Calculations to Show Compliance f Resolved per with 10 CFR 50.46 NUREG-0933 III.A.1.1(1) Implement Action Plan Requirements for Promptly f Resolved per Improving Licensee Emergency Preparedness NUREG-0933 1.9-56 Revision 3
TABLE 1.9-203 (Sheet 6 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria III.A.1.1(2) Perform an Integrated Assessment of the f Not applicable Implementation to new plants III.A.2.1(1) Publish Proposed Amendments to the Rules d Resolved per NUREG-0933 III.A.2.1(2) Conduct Public Regional Meetings d Not applicable to new plants III.A.2.1(3) Prepare Final Commission Paper Recommending d Not applicable Adoption of Rules to new plants III.A.2.1(4) Revise Inspection Program to Cover Upgraded d Resolved per Requirements NUREG-0933 III.A.2.2 Development of Guidance and Criteria d Resolved per NUREG-0933 III.A.3.3 Communications d Resolved per NUREG-0933 III.C.1(1) Review Publicly Available Documents d Not applicable to new plants III.C.1(2) Recommend Publication of Additional Information d Not applicable to new plants III.C.1(3) Program of Seminars for News Media Personnel d Not applicable to new plants III.C.2(1) Develop Policy and Procedures for Dealing With d Not applicable Briefing Requests to new plants III.C.2(2) Provide Training for Members of the Technical Staff d Not applicable to new plants III.D.2.4(2) Place 50 TLDs Around Each Site d Not applicable to new plants III.D.2.6 Independent Radiological Measurements d Not applicable to new plants III.D.3.2(1) Amend 10 CFR 20 d Not applicable to new plants III.D.3.2(2) Issue a Regulatory Guide d Not applicable to new plants III.D.3.2(3) Develop Standard Performance Criteria d Not applicable to new plants III.D.3.2(4) Develop Method for Testing and Certifying Air- d Not applicable Purifying Respirators to new plants III.D.3.3 In-Plant Radiation Monitoring COL 12.3.4, Item 12.3-2 Appendix 12AA III.D.3.5(1) Develop Format for Data To Be Collected by Utilities d Not applicable Regarding Total Radiation Exposure to Workers to new plants 1.9-57 Revision 3
TABLE 1.9-203 (Sheet 7 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria III.D.3.5(2) Investigate Methods of Obtaining Employee Health d Not applicable Data by Nonlegislative Means to new plants III.D.3.5(3) Revise 10 CFR 20 d Not applicable to new plants IV.A.1 Seek Legislative Authority d Not applicable to new plants IV.A.2 Revise Enforcement Policy d Not applicable to new plants IV.B.1 Revise Practices for Issuance of Instructions and d Not applicable Information to Licensees to new plants IV.D.1 NRC Staff Training d Not applicable to new plants IV.E.1 Expand Research on Quantification of Safety d Not applicable Decision-Making to new plants IV.E.2 Plan for Early Resolution of Safety Issues d Not applicable to new plants IV.E.3 Plan for Resolving Issues at the CP Stage d Not applicable to new plants IV. E.4 Resolve Generic Issues by Rulemaking d Not applicable to new plants IV.G.1 Develop a Public Agenda for Rulemaking d Not applicable to new plants IV.G.2 Periodic and Systematic Reevaluation of Existing d Not applicable Rules to new plants IV.G.3 Improve Rulemaking Procedures d Not applicable to new plants IV.G.4 Study Alternatives for Improved Rulemaking d Not applicable Process to new plants IV.H.1 NRC Participation in the Radiation Policy Council d Not applicable to new plants V.A.1 Develop NRC Policy Statement on Safety d Not applicable to new plants V.B.1 Study and Recommend, as Appropriate, Elimination d Not applicable of Nonsafety Responsibilities to new plants V.C.1 Strengthen the Role of Advisory Committee on d Not applicable Reactor Safeguards to new plants V.C.2 Study Need for Additional Advisory Committees d Not applicable to new plants V.C.3 Study the Need to Establish an Independent d Not applicable Nuclear Safety Board to new plants 1.9-58 Revision 3
TABLE 1.9-203 (Sheet 8 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria V.D.1 Improve Public and Intervenor Participation in the d Not applicable Hearing Process to new plants V.D.2 Study Construction-During-Adjudication Rules d Not applicable to new plants V.D.3 Reexamine Commission Role in Adjudication d Not applicable to new plants V.D.4 Study the Reform of the Licensing Process d Not applicable to new plants V.E.1 Study the Need for TMI-Related Legislation d Not applicable to new plants V.F.1 Study NRC Top Management Structure and Process d Not applicable to new plants V.F.2 Reexamine Organization and Functions of the NRC d Not applicable Offices to new plants V.F.3 Revise Delegations of Authority to Staff d Not applicable to new plants V.F.4 Clarify and Strengthen the Respective Roles of d Not applicable Chairman, Commission, and Executive Director for to new plants Operations V.F.5 Authority to Delegate Emergency Response d Not applicable Functions to a Single Commissioner to new plants V.G.1 Achieve Single Location, Long-Term d Not applicable to new plants V.G.2 Achieve Single Location, Interim d Not applicable to new plants Task Action Plan Items A-3 Westinghouse Steam Generator Tube Integrity COL 5.4.2.5 (former USI) Item 5.4-1 A-19 Digital Computer Protection System d Not applicable to new plants A-20 Impacts of the Coal Fuel Cycle d Not applicable to new plants A-23 Containment Leak Testing COL 6.2.5.1 Item 6.2-1 A-27 Reload Applications d Not applicable to new plants B-1 Environmental Technical Specifications d Not applicable to new plants B-2 Forecasting Electricity Demand d Not applicable to new plants 1.9-59 Revision 3
TABLE 1.9-203 (Sheet 9 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria B-11 Subcompartment Standard Problems d Not applicable to new plants B-13 Marviken Test Data Evaluation d Not applicable to new plants B-20 Standard Problem Analysis d Not applicable to new plants B-25 Piping Benchmark Problems d Not applicable to new plants B-27 Implementation and Use of Subsection NF d Not applicable to new plants B-28 Radionuclide/Sediment Transport Program d Not applicable to new plants B-29 Effectiveness of Ultimate Heat Sinks d Not applicable to new plants B-30 Design Basis Floods and Probability d Not applicable to new plants B-33 Dose Assessment Methodology d Not applicable to new plants B-35 Confirmation of Appendix I Models for Calculations d Not applicable of Releases of Radioactive Materials in Gaseous to new plants and Liquid Effluents from Light Water Cooled Power Reactors B-37 Chemical Discharges to Receiving Waters d Not applicable to new plants B-42 Socioeconomic Environmental Impacts d Not applicable to new plants B-43 Value of Aerial Photographs for Site Evaluation d Not applicable to new plants B-44 Forecasts of Generating Costs of Coal and Nuclear d Not applicable Plants to new plants B-49 Inservice Inspection Criteria and Corrosion d Not applicable Prevention Criteria for Containments to new plants B-59 (N-1) Loop Operation in BWRs and PWRs d Not applicable to new plants B-64 Decommissioning of Reactors f Resolved per NUREG-0933.
B-72 Health Effects and Life Shortening from Uranium d Not applicable and Coal Fuel Cycles to new plants C-4 Statistical Methods for ECCS Analysis d Not applicable to new plants 1.9-60 Revision 3
TABLE 1.9-203 (Sheet 10 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria C-5 Decay Heat Update d Not applicable to new plants C-6 LOCA Heat Sources d Not applicable to new plants New Generic Issues
- 43. Reliability of Air Systems f, j Resolved per NUREG-0933.
- 59. Technical Specification Requirements for Plant d Not applicable Shutdown when Equipment for Safe Shutdown is to new plants Degraded or Inoperable 67.2.1 Integrity of Steam Generator Tube Sleeves d Not applicable to new plants 67.5.1 Reassessment of Radiological Consequences d Not applicable to new plants 67.5.2 Reevaluation of SGTR Design Basis d Not applicable to new plants 67.10.0 Supplement Tube Inspections d Not applicable to new plants
- 99. RCS/RHR Suction Line Valve Interlock on PWRs f Resolved per NUREG-0933.
111. Stress Corrosion Cracking of Pressure Boundary d Not applicable Ferritic Steels in Selected Environments to new plants 112. Westinghouse RPS Surveillance Frequencies and d Not applicable Out-of-Service Times to new plants 118. Tendon Anchorage Failure f Resolved per NUREG-0933.
119.1 Piping Rupture Requirements and Decoupling of d Not applicable Seismic and LOCA Loads to new plants 119.3 Decoupling the OBE from the SSE d Not applicable to new plants 119.4 BWR Piping Materials d Not applicable to new plants 119.5 Leak Detection Requirements d Not applicable to new plants 128. Electrical Power Reliability h (High) Resolved per NUREG-0933.
130. Essential Service Water Pump Failures at Multiplant f See DCD Sites Subsection 1.9.4, item 130 133. Update Policy Statement on Nuclear Plant Staff d Not applicable Working Hours to new plants 1.9-61 Revision 3
TABLE 1.9-203 (Sheet 11 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria 136. Storage and Use of Large Quantities of Cryogenic d Not applicable Combustibles On Site to new plants 139. Thinning of Carbon Steel Piping in LWRs d Not applicable to new plants 146. Support Flexibility of Equipment and Components d Not applicable to new plants 147. Fire-Induced Alternate Shutdown Control Room d Not applicable Panel Interactions to new plants 148. Smoke Control and Manual Fire-Fighting d Not applicable Effectiveness to new plants 155.2 Establish Licensing Requirements For Non- d Not applicable Operating Facilities to new plants 156 Systematic Evaluation Program f Not applicable to new plants 156.6.1 Pipe Break Effects on Systems and Components High The AP1000 is a new plant that takes the effects of a pipe break into account and therefore issue 156.6.1 is not applicable.
163 Multiple Steam Generator Tube Leakage h (High) See DCD Subsection 1.9.4.2.3, item 163 168 Environmental Qualification Of Electrical Equipment f Not applicable to new plants 178 Effect Of Hurricane Andrew On Turkey Point d Not applicable to new plants 180 Notice Of Enforcement Discretion d Not applicable to new plants 181 Fire Protection d Not applicable to new plants 183 Cycle-Specific Parameter Limits In Technical d Not applicable Specifications to new plants 184 Endangered Species d Not applicable to new plants 185 Control of Recriticality following Small-Break LOCA h Not applicable in PWRs to new plants 186 Potential Risk and Consequences of Heavy Load Continue 1.9.4.2.3 Drops in Nuclear Power Plants 9.1.5.3 1.9-62 Revision 3
TABLE 1.9-203 (Sheet 12 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria 189 Susceptibility of Ice Condenser and Mark III Continue Not applicable to Containments to Early Failure from Hydrogen the AP1000.
Combustion During a Severe Accident Description 191 Assessment Of Debris Accumulation On PWR Sump h (High) See DCD Performance Subsections 6.3.2.2.7 and 1.9.4.2.3, item 191 199 Implications of Updated Probabilistic Seismic Issue to be 2.5 Hazard Estimates in Central and Eastern United Prioritized States by NRC in the Future Human Factors Issues HF1.1 Shift Staffing f 13.1.2.1.4 18.6 HF2.1 Evaluate Industry Training d Not applicable to new plants HF2.2 Evaluate INPO Accreditation d Not applicable to new plants HF2.3 Revise SRP Section 13.2 d Not applicable to new plants HF3.1 Develop Job Knowledge Catalog d Not applicable to new plants HF3.2 Develop License Examination Handbook d Not applicable to new plants HF3.5 Develop Computerized Exam System d Not applicable to new plants HF4.2 Procedures Generation Package Effectiveness d Not applicable Evaluation to new plants HF7.1 Human Error Data Acquisition d Not applicable to new plants HF7.2 Human Error Data Storage and Retrieval d Not applicable to new plants HF7.3 Reliability Evaluation Specialist Aids d Not applicable to new plants HF7.4 Safety Event Analysis Results Applications d Not applicable to new plants Chernobyl Issues CH1.1A Symptom-Based EOPs d Not applicable to new plants 1.9-63 Revision 3
TABLE 1.9-203 (Sheet 13 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria CH1.1B Procedure Violations d Not applicable to new plants CH1.2A Test, Change, and Experiment Review Guidelines d Not applicable to new plants CH1.2B NRC Testing Requirements d Not applicable to new plants CH1.3A Revise Regulatory Guide 1.47 d Not applicable to new plants CH1.4A Engineered Safety Feature Availability d Not applicable to new plants CH1.4B Technical Specification Bases d Not applicable to new plants CH1.4C Low Power and Shutdown d Not applicable to new plants CH1.5 Operating Staff Attitudes Toward Safety d Not applicable to new plants CH1.6A Assessment of NRC Requirements on Management d Not applicable to new plants CH1.7A Accident Management d Not applicable to new plants CH2.1A Reactivity Transients d Not applicable to new plants CH2.3B Contamination Outside Control Room d Not applicable to new plants CH2.3C Smoke Control d Not applicable to new plants CH2.3D Shared Shutdown Systems d Not applicable to new plants CH2.4A Firefighting With Radiation Present d Not applicable to new plants CH3.1A Containment Performance d Not applicable to new plants CH3.2A Filtered Venting d Not applicable to new plants CH4.3A Ingestion Pathway Protective Measures d Not applicable to new plants CH4.4A Decontamination d Not applicable to new plants CH4.4B Relocation d Not applicable to new plants 1.9-64 Revision 3
TABLE 1.9-203 (Sheet 14 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC COL 1.9-3 SAFETY ISSUES Action Plan Title Applicable Notes Item/Issue Screening No. Criteria CH5.1A Mechanical Dispersal in Fission Product Release d Not applicable to new plants CH5.1B Stripping in Fission Product Release d Not applicable to new plants CH5.2A Steam Explosions d Not applicable to new plants CH6.1B Structural Graphite Experiments d Not applicable to new plants CH6.2 Assessment d Not applicable to new plants Notes (from DCD Table 1.9-2):
(d) Issue is not a design issue (Environmental, Licensing, or Regulatory Impact Issue; or covered in an existing NRC program).
(f) Issue is not an AP1000 design certification issue. Issue is applicable to current operating plants or is programmatic in nature.
(h) Issue is unresolved pending generic resolution (for example, prioritized as High, Medium, or possible resolution identified).
(j) The AP600 DSER (Draft NUREG-01512) identified this item as required to be discussed.
1.9-65 Revision 3
TABLE 1.9-204 (Sheet 1 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment BULLETIN 80-06 Engineered Safety Feature (ESF) Reset See Note a.
Controls (3/80) 80-10 Contamination of Nonradioactive Appendix 12AA System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment (5/80) 80-15 Possible Loss of Emergency 9.5.2.2.3.1 Notification System (ENS) with Loss of 9.5.2.5.1 Offsite Power (6/80) 02-01 Reactor Pressure Vessel Head 5.2.4 Degradation and Reactor Coolant See Note a.
Pressure Boundary Integrity 02-02 Reactor Pressure Vessel Head and 5.2.4 Vessel Head Penetration Nozzle See Note a.
Inspection Programs 03-01 Potential Impact of Debris Blockage on 6.3 Emergency Sump Recirculation at See Note a.
Pressurized-Water Reactors 03-02 Leakage from Reactor Pressure Vessel 5.2.4.3 Lower Head Penetrations and Reactor See Note a.
Coolant Pressure Boundary Integrity 03-03 Potentially Defective 1-inch Valves for N/A Uranium Hexafluoride Cylinders 03-04 Rebaselining of Data in the Nuclear N/A Materials Management and Safeguards One time report.
System 04-01 Inspection of Alloy 82/182/600 Materials See Note a.
Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors 1.9-66 Revision 3
TABLE 1.9-204 (Sheet 2 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment 05-01 Material Control and Accounting at 13.6 Reactors and Wet Spent Fuel Storage Facilities 05-02 Emergency Preparedness and 13.3 Response Actions for Security-Based Events 88-11 Pressurizer Surge Line Thermal 3.9.3.1.2 Stratification GENERIC LETTERS 80-22 Transmittal of NUREG-0654 Criteria for 13.3 Preparation and Evaluation of Radiological Emergency Response Plans (3/80) 80-26 Qualifications of Reactor Operators 13.2 (3/80) 18.10 80-51 On-Site Storage Of Low-Level Waste 11.4.6 (6/90) 80-55 Possible Loss of Hotline With Loss Of See Bulletin 80-15 Off-Site Power 80-77 Refueling Water Level (8/80) 16.1 See Note a.80-094 Emergency Plan (11/80) 13.3 80-099 Technical Specification Revisions for Snubbers no longer in Snubber Surveillance (11/80) generic Tech Specs See Note a.80-108 Emergency Planning (12/80) 13.3 81-02 Analysis, Conclusions and 13.2 Recommendations Concerning Operator Licensing (1/81) 81-10 Post-TMI Requirements for the 13.3 Emergency Operations Facility (2/81) 1.9-67 Revision 3
TABLE 1.9-204 (Sheet 3 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment 81-38 Storage of Low-Level Radioactive 11.4.6 Waste at Power Reactor Sites (11/81) 81-40 Qualifications of Reactor Operators 13.1 (12/81) 13.2 82-02 Commission Policy on Overtime (2/82) 16.1 82-04 Use of INPO See-in Program (3/82) 13.1 13.5 82-12 Nuclear Power Plant Staff Working 13.1.2.1.2.4 - 13.1.2.1.2.8 Hours (6/82) 13.1.2.1.3 13.1.2.1.4 82-13 Reactor Operator and Senior Reactor For information only.
Operator Examinations (6/82) 82-18 Reactor Operator and Senior Reactor 13.2 Operator Requalification Examinations (10/82) 83-06 Certificates and Revised Format For 13.2 Reactor Operator and Senior Reactor Operator Licenses (1/83) 83-11 Licensee Qualification for Performing 13.1 Safety Analyses in Support of Licensing See Note a.
Actions (2/83) 83-12 Issuance of NRC FORM 398 - Personal 13.2 Qualifications Statement - Licensee (2/83) 83-17 Integrity of the Requalification 13.1 Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses (4/83) 83-22 Safety Evaluation of "Emergency 18.9 Response Guidelines" (6/83) 83-40 Operator Licensing Examination (12/83) 13.2 1.9-68 Revision 3
TABLE 1.9-204 (Sheet 4 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment 84-10 Administration of Operating Tests Prior 13.2 to Initial Criticality (10 CFR 55.25) (4/84) 84-14 Replacement and Requalification 13.2 Training Program (5/84) 84-17 Annual Meeting to Discuss Recent Administrative Developments Regarding Operator Training, Qualifications, and Examinations (7/84) 84-20 Scheduling Guidance for Licensee 13.5 Submittals of Reloads That Involve Unreviewed Safety Questions (8/84) 85-04 Operating Licensing Examinations Administrative (1/85) 85-05 Inadvertent Boron Dilution Events (1/85) 13.5 85-14 Commercial Storage At Power Reactor Administrative Sites Of Low Level Radioactive Waste Not Generated By The Utility (8/85) 85-18 Operator Licensing Examinations (9/85) Administrative 85-19 Reporting Requirements On Primary 16.1 Coolant Iodine Spikes (9/85) 86-14 Operator Licensing Examinations (8/86) Administrative 87-14 Operator Licensing Examinations (8/87) Administrative 88-05 Boric Acid Corrosion of Carbon Steel 5.2.4 Reactor Pressure Boundary See Note a.
Components in PWR Plants (3/88) 88-14 Instrument Air Supply System Problems 9.3.7 Affecting Safety-Related Equipment (8/88) 88-18 Plant Record Storage on Optical Disk 17 (10/88) 1.9-69 Revision 3
TABLE 1.9-204 (Sheet 5 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment 89-07 Power Reactors Safeguards 13.6 Contingency Planning for Surface Vehicle Bombs (4/89) 89-07 S1 Power Reactor Safeguards 13.6 Contingency Planning for Surface Vehicle Bombs 89-08 Erosion/Corrosion-Induced Pipe Wall 10.1.3.1 Thinning (5/89) 89-12 Operator Licensing Examination (7/89) 13.2 89-15 Emergency Response Data System 9.5.2 (8/89) 13.3 89-17 Planned Administrative Changes to the N/A NRC Operator Licensing Written Examination Process (9/89) 91-14 Emergency Telecommunications (9/91) 9.5.2 13.3 91-16 Licensed Operators and Other Nuclear 13.7 Facility Personnel Fitness for Duty (10/91) 92-01 Reactor Vessel Structural Integrity 5.3.2.6.3 (1/92) 93-01 Emergency Response Data System 13.3 Test Program 93-03 Verification of Plant Records 17 96-02 Reconsideration of Nuclear Power Plant 13.6 Security Requirements Associated with an Internal Threat (2/96) 03-01 Control Room Habitability 6.4 See Note a.
1.9-70 Revision 3
TABLE 1.9-204 (Sheet 6 of 6)
COL 1.9-2 GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment 04-01 Requirements for Steam Generator 5.4.2.5 Tube Inspections 16.1 See Note a.
04-02 Potential Impact of Debris Blockage on 6.3.8.1 Emergency Recirculation during Design See Note a.
Basis Accidents at Pressurized-Water Reactors 06-01 Steam Generator Tube Integrity and 5.4.2.5 Associated Technical Specifications 16.1 See Note a.
06-02 Grid Reliability and the Impact on Plant 8.2.1.1 Risk and the Operability of Offsite 8.2.2 Power See Note a.
06-03 Potentially Nonconforming Hemyc and 9.5.1.8 MT Fire Barrier Configurations See Note a.
07-01 Inaccessible or Underground Power 17.6 Cable Failures that Disable Accident See Note a.
Mitigation Systems or Cause Plant Transients.
(a) The design aspects of this topic are as stated in the AP1000 DCD.
1.9-71 Revision 3
Add the following section after DCD Section 1.9.
1.10 NUCLEAR POWER PLANTS TO BE OPERATED ON MULTI-UNIT SITES SUP 1.10-1 The certification for the AP1000 is for a single unit. Dual siting of AP1000 is achievable, provided that the centerlines of the units are sufficiently separated.
The primary consideration in setting this separation distance is the space needed to support plant construction via the use of a heavy-lift crane.
Security controls during construction and operation are addressed in the Physical Security Plan.
Management and administrative controls are established to identify potential hazards to structures, systems, and components (SSCs) of an operating unit as a result of construction activities at a unit under construction. Controls within this section are not required unless there is an operating unit on the site, i.e., a unit with fuel loaded into the reactor vessel. Advance notification, scheduling and planning allow site management to implement interim controls to reduce the potential for impact to SSCs.
This section presents an assessment of the potential impacts of construction of one unit on SSCs important to safety for an operating unit, in accordance with 10 CFR 52.79(a)(31). This assessment includes:
- Identification of potential construction activity hazards
- Identification of SSCs important to safety and limiting conditions for operation (LCOs) for the operating unit
- Identification of potentially impacted SSCs and LCOs
- Identification of applicable managerial and administrative controls 1.10.1 POTENTIAL CONSTRUCTION ACTIVITY HAZARDS SUP 1.10-1 The power blocks for Units 3 and 4 have a minimum separation of at least 800 feet between plant centerlines.
SUP 1.10-1 Construction activities may include site exploration, grading, clearing, and installation of drainage and erosion-control measures; boring, drilling, dredging, pile driving and excavating; transportation, storage and warehousing of equipment; and construction, erection, and fabrication of new facilities.
1.10-1 Revision 3
Construction activities and their representative hazards to an operating unit are shown in Table 1.10-201.
1.10.2 POTENTIALLY IMPACTED SSCS AND LIMITING CONDITIONS FOR OPERATION The construction activities described above were reviewed for possible impact to operating unit SSCs important to safety.
SUP 1.10-1
- As indicated in Chapter 16, the LCOs for Units 3 and 4 are located in Part 4 of the COL Application.
SUP 1.10-1 This assessment identified administrative and managerial controls to avoid impacts to SSCs from construction. The results of the assessment are presented in Table 1.10-202.
1.10.3 MANAGERIAL AND ADMINISTRATIVE CONTROLS To eliminate or mitigate construction hazards that could potentially impact operating unit SSCs important to safety, specific managerial and administrative controls have been identified as shown in Table 1.10-203.
Although not all of the managerial and administrative construction controls are necessary to protect the operating unit, the identified controls are applied to any operating unit as a conservative measure. This conservative approach provides reasonable assurance of protecting the identified SSCs from potential construction hazards and preventing the associated LCOs specified in the operating unit Technical Specifications from being exceeded as a result of construction activities, as discussed below.
The majority of the operating unit SSCs important to safety are contained and protected within safety-related structures. The managerial controls protect these internal SSCs from postulated construction hazards by maintaining the integrity and design basis of the safety-related structures and foundations. Heavy load drop controls, crane boom failure standoff requirements, ground vibration controls and construction generated missile(s) control are examples of managerial controls that provide this protection.
Other managerial controls support maintaining offsite power, control of hazardous materials and gases, and protection of cooling water supplies and safety system instrumentation. These managerial controls prevent or mitigate external construction impacts that could affect SSCs important to safety. These controls 1.10-2 Revision 3
also prevent or mitigate unnecessary challenges to safety systems caused by plant construction hazards, such as disruption of offsite transmission lines or impact to plant cooling water supplies.
The above discussed controls to eliminate or mitigate construction hazards that could potentially impact operating unit SSCs important to safety are in place when there is an operating nuclear unit on the site.
1.10-3 Revision 3
SUP 1.10-1 TABLE 1.10-201 (Sheet 1 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT Site Exploration, Grading,
- Overhead Power Lines Clearing, Installation of Drainage and Erosion Control
- Transmission Towers Measures
- Underground Conduits, Piping, Tunnels, Etc.
- Site Access and Egress
- Drainage Facilities and Structures
- Onsite Transportation Routes
- Slope Stability
- Soil Erosion and Local Flooding
- Construction-Generated Dust and Equipment Exhausts
- Encroachment on Plant Control Boundaries
- Encroachment on Structures and Facilities 1.10-4 Revision 3
SUP 1.10-1 TABLE 1.10-201 (Sheet 2 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT Boring, Drilling, Pile Driving,
- Underground Conduits, Piping, Dredging, Demolition, Tunnels, Etc Excavation
- Foundation Integrity
- Structural Integrity
- Slope Stability
- Erosion and Turbidity Control
- Groundwater and Groundwater Monitoring Facilities
- Dewatering Structures, Systems and Components
- Nearby Structures, Systems and Components
- Vibratory Ground Motion Equipment Movement, Material
- Overhead Power Lines Delivery, Vehicle Traffic
- Transmission Towers
- Underground Conduits, Piping, Tunnels
- Crane Load Drops
- Crane or Crane Boom Failures
- Vehicle Accidents
- Rail Car Derailments Equipment and Material
- Releases of Stored Flammable, Laydown, Storage, Hazardous or Toxic Materials Warehousing
- Wind-Generated, Construction-Related Debris and Missiles 1.10-5 Revision 3
SUP 1.10-1 TABLE 1.10-201 (Sheet 3 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT General Construction, Erection,
- Physical Integrity of Structures, Fabrication Systems and Components
- Adjacent or Nearby Structures, Systems and Components
- Instrumentation and Control Systems and Components
- Electrical Systems and Components*
Cooling Water Systems and Components
- Waste Heat Environmental Controls and Parameters
- Radioactive Waste Release Points and Parameters
- Abandonment of Structures, Systems or Components
- Relocation of Structures, Systems or Components
- Removal of Structures, Systems or Components Connection, Integration, Testing
- Instrumentation and Control Systems and Components
- Electrical and Power Systems and Components
- Cooling Water Systems and Components 1.10-6 Revision 3
SUP 1.10-1 TABLE 1.10-202 (Sheet 1 of 2)
HAZARDS DURING CONSTRUCTION ACTIVITIES CONSTRUCTION HAZARD IMPACTED SSCs Impact on Overhead Power
- Offsite Power System Lines Impact on Transmission Towers
- Offsite Power Systems Impact on Utilities,
- Fire Protection System Underground Conduits, Piping, Tunnels, Tanks
- Service Water System1 Impact of Construction-
- Control Room Emergency HVAC Generated Dust and Equipment Systems1 Exhausts
- Diesel Generators Impact of Vibratory Ground
- Offsite Power System Motion
- Onsite Power Systems
- Instrumentation and Seismic Monitors Impact of Crane or Crane
- Safety-Related Structures Boom Failures Impact of Releases of
- Control Room Emergency HVAC Flammable, Hazardous or Toxic Systems1 Materials Impact of Wind-Generated,
- Safety-Related Structures Construction-Related Debris and Missiles
- Control Room Emergency HVAC Systems1 Impact on Electrical Systems
- Offsite Power System and Components
- Onsite Power Systems Impact on Cooling Water
- Service Water System1 Systems and Components
- Ultimate Heat Sink1 1.10-7 Revision 3
SUP 1.10-1 TABLE 1.10-202 (Sheet 2 of 2)
HAZARDS DURING CONSTRUCTION ACTIVITIES CONSTRUCTION HAZARD IMPACTED SSCs Impact on Radioactive Waste
- Gaseous and Liquid Radioactive Release Points and Waste Management Systems Parameters Impact of Relocation of
- Fire Protection System Structures, Systems or Components
- Service Water System1 Impact of Site Groundwater
- Safety-Related Structures and Depression and Dewatering Foundations Impact of Equipment Delivery
- Safety-Related Structures and and Heavy Equipment Delivery Foundations 1
Not applicable to AP1000 operating units 1.10-8 Revision 3
SUP 1.10-1 TABLE 1.10-203 (Sheet 1 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL Impact on Transmission Power
- Safe standoff clearance distances are Lines and Offsite Power Lines established for transmission power lines, including verification of standoff distance for modules, the reactor vessel and other equipment to be transported beneath energized electric lines to meet minimum standoff clearance requirements.
- Physical warning or caution barriers and signage are erected along transport routes.
Impact on Transmission Towers
- Establish controls or physical barriers to avoid equipment collisions with electric transmission support towers Impact on Utilities,
- Grading, excavation, and pile driving Underground Conduits, Piping, require location and identification of Tunnels, Tanks equipment or underground structures that must be relocated, removed, or left in place and protected prior to the work activity.
Impact of Construction-
- Fugitive dust and dust generation is Generated Dust and Equipment controlled. Potentially affected Exhausts system air intakes and filters are periodically monitored.
Impact of Vibratory Ground
- Construction administrative Motion procedures, methods, and controls are implemented to prevent exceeding ground vibration and instrumentation limit settings.
Impact of Crane or Crane
- Construction standoff distance Boom Failures controls prevent heavy load impacts from crane boom failures and crane load drops. Drop analyses may be substituted if minimum standoff distances are not practical.
1.10-9 Revision 3
SUP 1.10-1 TABLE 1.10-203 (Sheet 2 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL Impact of Releases of
- Environmental, safety and health Flammable, Hazardous or Toxic controls limit transport, storage, Materials and Missile quantities, type and use of Generation flammable, hazardous, toxic materials and compressed gasses.
Construction safety and storage controls maintain potential missile generation events from compressed gasses within the operating unit design basis.
Impact of Wind-Generated,
- Administrative controls address Construction-Related Debris equipment, material storage and and Missiles transport during high winds or high wind warnings.
- Plant procedures are followed during severe weather conditions which may call for power reduction or shut down.
Impact on Electrical Systems
- Affected operating unit electrical and Components systems and components within the construction area are identified and isolated or relocated or otherwise protected.
Impact on Cooling Water
- Transport of heavy load equipment Systems and Components over buried cooling water piping is prohibited without evaluation.
Impact on Radioactive Waste
- Engineering evaluation and Release Points and managerial controls are Parameters implemented, as necessary, to prevent radioactive releases beyond the established limits due to construction activity.
Impact of Relocation of
- Administrative controls identify SSCs Structures, Systems or that require relocation. Temporary or Components permanent design changes are implemented if necessary.
1.10-10 Revision 3
SUP 1.10-1 TABLE 1.10-203 (Sheet 3 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL Impact of Equipment Delivery
- Rail transport speed limits and and Heavy Equipment Delivery maximum rail loading weights onsite are established.
- General equipment and heavy equipment movement controls and limitations are established.
1.10-11 Revision 3
APPENDIX 1A CONFORMANCE WITH REGULATORY GUIDES This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
COL 1.9-1 Appendix 1AA is provided to supplement the information in DCD Appendix 1A.
1A-1 Revision 3
APPENDIX 1B SUP 1B-1 SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES DCD Appendix 1B is not incorporated into this FSAR. Rather, the severe accident mitigation design alternatives are addressed in the Environmental Report. As indicated in 10 CFR Part 52, Appendix D, Section III.B, "...the evaluation of severe accident mitigation design alternatives in appendix 1B of the generic DCD are not part of this appendix."
1B-1 Revision 3
APPENDIX 1AA CONFORMANCE WITH REGULATORY GUIDES COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions DIVISION 1 - Power Reactors Regulatory Guide 1.7, Rev. 3, 03/07 - Control of Combustible Gas Concentrations in Containment Conformance of the design aspects with Revision 2 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 3 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.2 Conforms C.4 Conforms Regulatory Guide 1.8, Rev. 3, 5/00 - Qualification and Training of Personnel for Nuclear Power Plants C.1 Conforms C.2 Section 4 of Exception Not able to meet Regulatory Guide 1.8, ANSI/ANS- Rev. 3 qualification requirements for 3.1-1993 licensed personnel prior to operations.
Regulatory Guide 1.12, Rev. 2, 3/97 - Nuclear Power Plant Instrumentation for Earthquakes Conformance of the design aspects is as stated in the DCD. Conformance for programmatic and/or operational aspects is documented below.
C.3 Conforms C.8 Conforms Regulatory Guide 1.13, Rev. 2, 03/07 - Spent Fuel Storage Facility Design Basis Conformance of the design aspects with Revision 1 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 2 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.7 Conforms Regulatory Guide 1.20, Rev. 3, 3/07 - Comprehensive Vibration Assessment Program For Reactor Internals During Preoperational and Initial Startup Testing Conformance with Revision 2 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
1AA-1 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.21, Rev. 1, 6/74 - Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.1 Conforms C.3-C.5 Conforms C.6 Conforms C.7-C.14 Conforms Regulatory Guide 1.23, Rev. 1, 3/07 - Meteorological Monitoring Programs for Nuclear Power Plants General Exception Sampling interval for temperature and dew point during siting activities based on guidance in effect at the beginning of the program General Conforms Plant operations phase program will conform.
Regulatory Guide 1.26, Rev. 4, 3/07 - Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants Conformance with Revision 3 of the Regulatory Guide for DCD scope of work is as stated in the DCD. Conformance with Revision 4 of this Regulatory Guide for remaining scope is documented below.
General Conforms Regulatory Guide 1.28, Rev. 3, 8/85 - Quality Assurance Program Requirements (Design and Construction)
Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
1AA-2 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.29, Rev. 4, 3/07 - Seismic Design Classification Conformance with Revision 3 of the Regulatory Guide for DCD scope of work is as stated in the DCD. Conformance with Revision 4 of this Regulatory Guide for remaining scope is documented below.
C.4 Conforms Regulatory Guide 1.30, Rev. 0, 8/72 - Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
Regulatory Guide 1.32, Rev. 3, 03/04 - Criteria for Power Systems for Nuclear Power Plants Conformance of the design aspects with Revision 2 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 3 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.33, Rev. 2, 2/78 - Quality Assurance Program Requirements (Operation)
C.1 & C.3 Conforms C.2 Clarification See separate conformance statement for each identified Regulatory Guide.
C.3 - C.5 Conforms Regulatory Guide 1.37, Rev. 1, 3/07 - Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants Conformance of the design aspects with Revision 0 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms 1AA-3 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.38, Rev. 2, 5/77 - Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
Regulatory Guide 1.39, Rev. 2, 9/77 - Housekeeping Requirements for Water-Cooled Nuclear Power Plants Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
Regulatory Guide 1.45, Rev. 0, 5/73 - Reactor Coolant Pressure Boundary Leakage Detection Systems Conformance of the design aspects is as stated in the DCD. Conformance with programmatic and/or operational aspects is documented below.
C.7 Conforms Regulatory Guide 1.53, Rev. 2, 11/03 - Application of the Single-Failure Criterion to Safety Systems Conformance of the design aspects with Revision 0 of the Regulatory Guide is as stated in the DCD. This guidance is completely within the scope of the DCD.
Regulatory Guide 1.54, Rev. 1, 7/00 - Service Level I, II, And III Protective Coatings Applied To Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. Conformance with programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.57, Rev. 1, 3/07 - Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components Conformance with Revision 0 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
1AA-4 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.59, Rev. 2, 8/77 - Design Basis Floods for Nuclear Power Plants General Exception Regulatory Guide 1.59, Appendix A indicates use of ANSI N170-1976 Standards for Determining Design Basis Flooding at Power Reactor Sites. In place of this standard, ANSI/
ANS 2.8-1992 Determining Design Basis Flooding at Power Reactor Sites was used.
ANSI/ANS 2.8-1992 was withdrawn on July 26, 2002. However, a replacement standard has not been issued.
NUREG-0800 2.4.3 Revision 4, March 2007 and 2.4.4 Revision 3, March 2007 include ANSI/ANS 2.8-1992 as a reference. ANSI/ANS 2.8-1992 is also specifically identified in the review procedures subsection of NUREG-0800 2.4.4.
Regulatory Guide 1.61, Rev. 1, 3/07 - Damping Values for Seismic Design of Nuclear Power Plants Conformance with Revision 0 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.65, Rev. 0, 10/73 - Materials and Inspections for Reactor Vessel Closure Studs Conformance of the design aspects is as stated in the DCD. Conformance with programmatic and/or operational aspects is documented below.
C.3 Conforms C.4 Exception ASME XI ISI criteria for reactor vessel closure stud examinations are applied in lieu of the ASME III NB 2545 and NB 2546 surface examinations. The volumetric examinations currently required by ASME XI provide improved (since 1973) detection of bolting degradation.
1AA-5 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.68, Rev. 3, 3/07 - Initial Test Program for Water-Cooled Nuclear Power Plants Conformance with Revision 2 of the Regulatory Guide is documented in the DCD.
Conformance of the design aspects is as stated in the DCD. Conformance with Revision 3 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C2-C.9 Conforms Appendix B Appendix C Regulatory Guide 1.70, Rev. 3, 11/78, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)
General Exception The format and content of the FSAR follow Regulatory Guide 1.206 and the AP1000 Design Control Document as required by Appendix D of 10 CFR Part 52.
Regulatory Guide 1.71, Rev. 1, 3/07 - Welder Qualification for Areas of Limited Accessibility Conformance of the design aspects with Revision 0 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 1 of the Regulatory Guide during the operational phase (i.e., after the construction phase is completed per the DCD) is documented below.
General Conforms Regulatory Guide 1.75, Rev. 3, 2/05 - Criteria for Independence of Electrical Safety Systems Conformance with Revision 2 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.76, Rev. 1, 3/07 - Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants Conformance with Revision 0 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.78, Rev. 1, 12/01 - Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release Conformance with the design aspects is as stated in the DCD. Conformance with programmatic and/or operational aspects is documented below.
General Conforms 1AA-6 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.82, Rev. 3, 11/03 - Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident Conformance of the design aspects with Revision 2 of this Regulatory Guide is as stated in the DCD. Conformance with Revision 3 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.1.1.2 Conforms C.1.1.5 Conforms Regulatory Guide 1.83, Rev. 1, 7/75 - Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes Conformance of the design aspects is as stated in the DCD. Conformance of the programmatic and/or operational aspects is documented below.
General Exception Steam generator tube surveillance is in accordance with Nuclear Energy Institute (NEI) 97-06. This guidance has been endorsed by NRC as an acceptable program basis.
Regulatory Guide 1.84, Rev. 33, 8/05 - Design, Fabrication, and Materials Code Case Acceptability, ASME Section III Conformance with Revision 31 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.86, Rev. 0, 6/74 - Termination of Operating Licenses for Nuclear Reactors This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.91, Rev. 1, 2/78 - Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.92, Rev. 2, 07/06 - Combining Modal Responses and Spatial Components in Seismic Response Analysis Conformance with Revision 1 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
1AA-7 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.94, Rev. 1, 4/76 - Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
Regulatory Guide 1.97, Rev. 4, 6/06 - Criteria For Accident Monitoring Instrumentation For Nuclear Power Plants Conformance with this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Exception Portable equipment outside the DCD scope conforms to Revision 3 of this Regulatory Guide for consistency with DCD scope since Revision 4 indicates that partial implementation is not advised.
Regulatory Guide 1.101, Rev. 5, 6/05 - Emergency Response Planning and Preparedness for Nuclear Power Reactors General Exception Rev. 5 is not applicable for this site.
Rev. 3 and 4 are essentially the same except for endorsement of NEI 99-01 which is not directly applicable to the AP1000 passive design. The EP conforms to Rev. 3 and 4 with the exception that the EALs are written with necessary modifications to address the passive plant design.
Regulatory Guide 1.109, Rev. 1, 10/77 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms 1AA-8 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.110, Rev. 0, 3/76 - Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors Conformance of the design aspects is as stated in the DCD. Conformance with Revision 0 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.111, Rev. 1, 7/77 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors General Conforms Regulatory Guide 1.112, Rev. 1, 3/07 - Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Nuclear Power Reactors Conformance of the design aspects with Revision 0-R of the Regulatory Guide is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General ANSI 18.1- Conforms 1999 Regulatory Guide 1.113, Rev. 1, 4/77 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I General Conforms Regulatory Guide 1.114, Rev. 2, 5/89 - Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit General Conforms Regulatory Guide 1.115, Rev. 1, 7/77 - Protection Against Low-Trajectory Turbine Missiles Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms 1AA-9 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.116, Rev. 0-R, 5/77 - Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems Conformance for DCD scope of work is as stated in the DCD. Conformance for remaining scope is documented below.
General Exception Quality assurance requirements utilize the more recently NRC endorsed NQA-1 in lieu of the identified outdated standards.
Regulatory Guide 1.124, Rev. 2, 02/07 - Service Limits and Loading Combinations for Class 1 Linear-Type Supports Conformance with Revision 1 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.128, Rev. 2, 2/07 - Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants Conformance with Revision 1 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.129, Rev. 2, 2/07 - Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants General IEEE Std. Exception Approved Generic Technical 450-2002 Specifications are based on IEEE Std 450-1995.
Regulatory Guide 1.130, Rev. 2, 3/07 - Service Limits and Loading Combinations for Class 1 Plate-And-Shell-Type Supports Conformance with Revision 1 of the Regulatory Guide is as stated in the DCD.
This guidance is completely within the scope of the DCD.
Regulatory Guide 1.132, Rev. 2, 10/03 - Site Investigations for Foundations of Nuclear Power Plants General Conforms Regulatory Guide 1.133, Rev. 1, 5/81 - Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.2b Conforms Procedures are addressed in Section 13.5 1AA-10 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions C.3a Conforms Procedures are addressed in Section 13.5 C.4g Conforms Procedures are addressed in Section 13.5 C.4h Conforms Procedures are addressed in Section 13.5 C.4i Conforms ALARA is addressed in Chapter 12 and Section 13.5 C.4j Conforms Training is addressed in Section 13.2 C.6 Exception Regulatory Guide 1.16 has been withdrawn. Event reporting is performed in accordance with 10 CFR 50.72 and 50.73 utilizing the guidance of NUREG-1022.
Regulatory Guide 1.134, Rev. 3, 3/98 - Medical Evaluation of Licensed Personnel at Nuclear Power Plants General Conforms Regulatory Guide 1.135, Rev. 0, 9/77 - Normal Water Level and Discharge at Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. The programmatic and/or operational aspects are not applicable since this guidance was withdrawn by NRC (74 FR 39349, 08/06/2009).
Regulatory Guide 1.138, Rev. 2, 12/03 - Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants General Conforms Regulatory Guide 1.139, Rev. 0, 5/78 - Guidance for Residual Heat Removal Conformance with the design aspects is as stated in the DCD. The programmatic and/or operational aspects are not applicable since this guidance was withdrawn by NRC (73 FR 32750, 06/10/2008).
Regulatory Guide 1.143, Rev. 2, 11/01 - Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. Conformance with Revision 2 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms 1AA-11 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.145, Rev. 1, 11/82 (Revised 2/83 to correct page 1.145-7) - Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants General Conforms Regulatory Guide 1.147, Rev. 14, 8/05 - Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 Conformance with Revision 12 of the Regulatory Guide is documented in the DCD. Conformance of the design aspects is as stated in the DCD. Conformance with Revision 14 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.149, Rev. 3, 10/01 - Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations C.1 Conforms During cold licensing, training is conducted using a simulator with limited scope in accordance with Appendix D of ANSI/ANS-3.5-1998. Operator Licensing examinations are conducted on a simulator meeting the applicable requirements of ANSI/ANS-3.5-1998.
Regulatory Guide 1.150, Rev. 1, 2/83 - Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations Conformance with the design aspects is as stated in the DCD. The programmatic and/or operational aspects are not applicable since this guidance was withdrawn by NRC (73 FR 7766, 02/11/2008).
Regulatory Guide 1.152, Rev. 2, 1/06 - Criteria for Use of Computers in Safety Systems of Nuclear Power Plants Conformance of the design aspects with Revision 1 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 2 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Exception The Cyber Security Program is based on March 2009 revisions of the 10 CFR 73.54 regulations in lieu of Revision 2 of this Regulatory Guide.
Regulatory Guide 1.154, Rev. 0, 1/87 - Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors General Conforms 1AA-12 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.159, Rev. 1, 10/03 - Assuring the Availability of Funds for Decommissioning Nuclear Reactors General N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.160, Rev. 2, 3/97 - Monitoring the Effectiveness of Maintenance at Nuclear Power Plants General Conforms Regulatory Guide 1.162, Rev. 0, 2/96 - Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.163, Rev. 0, 9/95 - Performance-Based Containment Leak-Test Program Conformance of the design aspects is as stated in the DCD. Conformance with Revision 0 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.165, Rev. 0, 3/97 - Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion General N/A Seismic analysis performed in accordance with Regulatory Guide 1.208.
Regulatory Guide 1.166, Rev. 0, 3/97 - Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions General Conforms Regulatory Guide 1.167, Rev. 0, 3/97 - Restart of a Nuclear Power Plant Shut Down by a Seismic Event General Conforms Regulatory Guide 1.168, Rev. 1, 2/04 - Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants Conformance of the design aspects with Revision 0 of the Regulatory Guide is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms 1AA-13 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.174, Rev. 1, 11/02 - An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.175, Rev. 0, 8/98 - An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing Risk-informed inservice testing is not being utilized for this plant.
Regulatory Guide 1.177, Rev. 0, 8/98 - An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications General Conforms Regulatory Guide 1.178, Rev. 1, 9/03 - An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping Risk-informed inservice inspection is not being utilized for this plant.
Regulatory Guide 1.179, Rev. 0, 1/99 - Standard Format and Content of License Termination Plans for Nuclear Power Reactors N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.180, Rev. 1, 10/03 - Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Exclusion zones are established through administrative controls to prohibit the activation of portable EMI/RFI emitters (e.g., welders and transceivers) in areas where safety-related I&C systems are installed.
Regulatory Guide 1.181, Rev. 0, 9/99 - Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)
General Conforms Regulatory Guide 1.182, Rev. 0, 5/00 - Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants General Conforms 1AA-14 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.184, Rev. 0, 7/00 - Decommissioning of Nuclear Power Reactors N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.185, Rev. 0, 7/00 - Standard Format and Content for Post-shutdown Decommissioning Activities Report N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.186, Rev. 0, 12/00 - Guidance and Examples for Identifying 10 CFR 50.2 Design Bases N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.187, Rev. 0, 11/00 - Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments General Conforms Regulatory Guide 1.188, Rev. 1, 9/05 - Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.189, Rev. 1, 3/07 - Fire Protection for Nuclear Power Plants Conformance with Revision 0 of the Regulatory Guide is documented in the DCD.
Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.191, Rev. 0, 5/01 - Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.192, Rev. 0, 6/03 - Operation and Maintenance Code Case Acceptability, ASME OM Code General Conforms 1AA-15 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.193, Rev. 1, 8/05 - ASME Code Cases Not Approved for Use General Conforms Regulatory Guide 1.194, Rev. 0, 6/03 - Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants General Conforms Regulatory Guide 1.195, Rev. 0, 5/03 - Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.196, Rev. 1, 1/07 - Control Room Habitability at Light-Water Nuclear Power Reactors Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below. This Regulatory Guide is not applicable to the AP1000 certified design.
General Conforms Regulatory Guide 1.197, Rev. 0, 5/03 - Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors Conformance with the design aspects is as stated in the DCD. Conformance with programmatic and/or operational aspects is documented below.
General Conforms Regulatory Guide 1.198, Rev. 0, 11/03 - Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites General Conforms Regulatory Guide 1.199, Rev. 0, 11/03 - Anchoring Components and Structural Supports in Concrete N/A This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.200, Rev. 1, 1/07 - An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities General Conforms 1AA-16 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.201, Rev. 1, 5/06 - Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.202, Rev. 0, 2/05 - Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 1.203, Rev. 0, 12/05 - Transient and Accident Analysis Methods This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.204, Rev. 0, 11/05 - Guidelines for Lightning Protection of Nuclear Power Plants General Conforms Regulatory Guide 1.205, Rev. 0, 5/06 - Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.206, Rev. 0, 6/07 - Combined License Applications for Nuclear Power Plants (LWR Edition)
General Format Conforms General Content Exception Exceptions to content are identified in Table 1.9-202.
Regulatory Guide 1.207, Rev. 0, 3/07 - Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors This Regulatory Guide is not applicable to the AP1000 certified design.
Regulatory Guide 1.208, Rev. 0, 3/07 - A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion General Conforms Appendix C, Exception Exception is taken to requirement that Section C.3 3.4 0.05 and 0.95 fractile hazard curves be provided. These were not run. Hazard curves were run at 0.15 and 0.85th percentile instead of 0.16 and 84th as they are very close approximations (+/- 1 sigma).
1AA-17 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 1.209, Rev. 0, 3/07 - Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants This Regulatory Guide is not applicable to the AP1000 certified design.
DIVISION 4 - Environmental and Siting Regulatory Guide 4.7 Rev. 2, 4/98 - General Site Suitability Criteria for Nuclear Power Stations General Conforms Regulatory Guide 4.15 Rev. 2, 7/07 - Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent Streams and the Environment Exception The Guidance of Rev. 1, February 1979 will be followed as per the justification provided in FSAR Subsection 11.5.3.
DIVISION 5 - Materials and Plant Protection Regulatory Guide 5.9 Rev. 2, 12/83 - Guidelines for Germanium Spectroscopy Systems for Measurement of Special Nuclear Material N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 5.12, Rev. 0, 11/73 - General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials Conformance of the design aspects is as stated in the DCD.
N/A This Regulatory Guide is outside the scope of the FSAR.
Regulatory Guide 5.65, Rev. 0, 9/86 - Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls Conformance of the design aspects is as stated in the DCD.
N/A This Regulatory Guide is outside the scope of the FSAR.
1AA-18 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions DIVISION 8 - Occupational Health Regulatory Guide 8.2, Rev. 0, 2/73 - Guide for Administrative Practices in Radiation Monitoring General 10 CFR Exception The reference to 10 CFR 20.401 is no Part 20; longer valid in the current version of ANSI 13.2- 10 CFR Part 20.
1969 ANSI N13.2-1969 was reaffirmed in 1988.
Regulatory Guide 8.4, Rev. 0, 2/73 - Direct-Reading and Indirect-Reading Pocket Dosimeters General 10 CFR Exception The reference to 10 CFR 20.202 (a) and Part 20 20.401 is no longer valid in the current version of 10 CFR Part 20.
ANSI N13.5-1972 ANSI N13.5-1972 was reaffirmed in 1989.
The two performance criteria specified in Regulatory Guide 8.4 (accuracy and leakage) for these devices are met using acceptance standards in ANSI N322-1997 "American National Standard Inspection, Test, Construction, and Performance Requirements for Direct Reading Electrostatic/
Electroscope Type Dosimeters".
Regulatory Guide 8.5, Rev. 1, 3/81 - Criticality and Other Interior Evacuation Signals General Conforms Regulatory Guide 8.6, Rev. 0, 5/73 - Standard Test Procedure for Geiger-Muller Counters General Exception Instrument calibration program is based upon criteria in ANSI N323A-1997 (with 2004 Correction Sheet) Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments. The ANSI 42.3-1969 Standard is no longer recognized as sufficient for calibration of modern instruments.
1AA-19 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 8.7, Rev. 2, 11/05 - Instructions for Recording and Reporting Occupational Radiation Dose Data General Conforms Regulatory Guide 8.8, Rev. 3, 6/78 - Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable Conformance of the design aspects is as stated in the DCD. Conformance with Revision 3 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
C.1 Conforms C.3.a Conforms C.3.b Exception Regulatory Guide 1.16 C.1.b.(3) data is no longer reported. Reporting per C.1.b(2) is also no longer required.
C.3.c Conforms C.4.b-C.4.d ANSI Z- Conforms Conformance is with the latest revision of 88.2, NUREG-0041.
Regulatory Guide 8.15, NUREG-0041 Regulatory Guide 8.9, Rev. 1, 7/93 - Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program General Conforms Regulatory Guide 8.10, Rev. 1-R, 5/77 - Operating Philosophy For Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable General Conforms Regulatory Guide 8.13, Rev. 3, 6/99 - Instruction Concerning Prenatal Radiation Exposure General Conforms Regulatory Guide 8.15, Rev. 1, 10/99 - Acceptable Programs for Respiratory Protection General Conforms 1AA-20 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 8.27, Rev. 0, 3/81 - Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants General Conforms Regulatory Guide 8.28, Rev. 0, 8/81 - Audible-Alarm Dosimeters General ANSI Conforms N13.27-1981 Regulatory Guide 8.29, Rev. 1, 2/96 - Instruction Concerning Risks from Occupational Radiation Exposure General Conforms Regulatory Guide 8.34, Rev. 0, 7/92 - Monitoring Criteria and Methods To Calculate Occupational Radiation Doses General Conforms Regulatory Guide 8.35, Rev. 0, 6/92 - Planned Special Exposures General Conforms Regulatory Guide 8.36, Rev. 0, 7/92 - Radiation Dose to the Embryo/Fetus General Conforms 1AA-21 Revision 3
COL 1.9-1 Criteria Referenced FSAR Clarification/
Section Criteria Position Summary Description of Exceptions Regulatory Guide 8.38, Rev. 1, 5/06 - Control of Access to High and Very High Radiation Areas in Nuclear Power Plants Conformance of the design aspects is as stated in the DCD. Conformance with Revision 1 of this Regulatory Guide for programmatic and/or operational aspects is documented below.
General Conforms Notes:
(1) Above stated general alternatives regarding the use of previous revisions of the Regulatory Guide for design aspects as stated in the DCD is provided to preserve the finality of the certified design. Further, each stated conformance with the programmatic and/or operational aspects is only to the extent that a design change or departure from the approved DCD is not required to implement those programmatic and/or operational aspects. As the operational and programmatic aspects become more fully defined (for example, during the preparation, approval, or initial implementation of plant procedures), there exists a potential that a conflict could be identified between the design as certified in the DCD and the programmatic and/or operational aspects of the guidance. In such cases, the design certification (rule) becomes the controlling factor, and the design conformance to the Regulatory Guide is per the revision stated in the DCD.
(2) A Criteria Section entry of General indicates a scope for the conformance statement of all regulatory guide positions related to programmatic and/or operational aspects. Thus, an associated conformance statement of Conforms indicates that the applicant complies with all regulatory guide positions related to programmatic and/or operational aspects.
1AA-22 Revision 3