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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1-i 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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 1-ii 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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1-iii 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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1-iv 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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-1 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 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.
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 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).
STD SUP 1.1-1 BLN SUP 1.1-2 BLN COL 2.1-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-2 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:
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.
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.
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.
BLN COL 1.1-1 STD SUP 1.1-6 STD SUP 1.1-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-3 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.
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.
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.
STD SUP 1.1-4 BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-4 1.1.7 COMBINED LICENSE INFORMATION Add the following text to the end of DCD Subsection 1.1.7.
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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-5 TABLE 1.1-201 (Sheet 1 of 8)
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 BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-6 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 TABLE 1.1-201 (Sheet 2 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-7 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 TABLE 1.1-201 (Sheet 3 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-8 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 TABLE 1.1-201 (Sheet 4 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-9 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 TABLE 1.1-201 (Sheet 5 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-10 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 TABLE 1.1-201 (Sheet 6 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-11 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 TABLE 1.1-201 (Sheet 7 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-12 ZIT Zone of Intense Thinning ZRA Zone of River Anomalies ZRA-S Zone of River Anomalies in South Carolina TABLE 1.1-201 (Sheet 8 of 8)
ACRONYMS USED IN THE FSAR Acronym Definition BLN SUP 1.1-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-13 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 or STD CDI FSAR information that addresses DCD Conceptual Design Information (CDI). Replacement design 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.
STD SUP 1.1-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-14 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.
TABLE 1.1-202 (Sheet 2 of 2)
LEFT MARGIN ANNOTATIONS STD SUP 1.1-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.1-15 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.
TABLE 1.1-203 ANTICIPATED SCHEDULE FOR CONSTRUCTION AND 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-related activities) 3rd Q 2013 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-related activities) 3rd Q 2014 Fuel Load, Commence Start-Up 3rd Q 2018 6 Months BLN COL1.1-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.2-1 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.
Site Plan 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 BLN COL 3.3-1 BLN COL 2.1-1 BLN COL 3.5-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.2-2 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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.2-3 1.2.3 PLANT ARRANGEMENT DESCRIPTION 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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.3-1 1.3 COMPARISONS WITH SIMILAR FACILITY DESIGNS This section of the referenced DCD is incorporated by reference with no departures or supplements.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.4-1 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:
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:
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:
1.4.2.8 Other Contractors Contractual relationships have been established with specialized consulting firms to assist in preparing the COL Application for BLN.
BLN SUP 1.4-1 BLN SUP 1.4-2 BLN SUP 1.4-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.4-2 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
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.4-3 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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.5-1 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION This section of the referenced DCD is incorporated by reference with no departures or supplements.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.6-1 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.
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.
STD SUP 1.6-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.6-2 (A) Denotes NRC approved document.
TABLE 1.6-201 ADDITIONAL MATERIAL REFERENCED Author /
Report Number(a) 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.
Title Revision FSAR Section Document Transmittal ADAMS Accession Number Westinghouse /
APP-GW-GL-700 AP1000 Design Control Document 17 All September 2008 ML083230868 NEI 07-08A Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA) 0 12.1 October 2009 ML093220164 NEI 07-03A Generic FSAR Template Guidance for Radiation Protection Program Description 0
Appendix 12AA May 2009 ML091490684 NEI 06-13A Template for an Industry Training Program Description 2
13.2 March 2009 ML090910554 NEI 07-02A Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52 0
17.6 March 2008 ML080910149 Emergency Plan Bellefonte Nuclear Station Combined License Application Emergency Plan 2
13.3 December 2009 ML100151002 Cyber Security Plan Bellefonte Nuclear Plant Units 3 & 4 Cyber Security Plan 0
13.6 August 2009 Not Applicable (SUNSI)
QAPD TVA Bellefonte Units 3 and 4 Quality Assurance Program Description 1
17.5 January 2009 ML090290406 STD SUP 1.6-1 BLN SUP 1.6-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.7-1 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.
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.
BLN SUP 1.7-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.7-2 TABLE 1.7-201 AP1000 SYSTEM DESIGNATORS AND SYSTEM DRAWINGS Designator System FSAR 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 Line Diagram 8.2 8.2-201 BLN SUP 1.7-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-1 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.
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.
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.
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.
BLN SUP 1.8-1 BLN SUP 1.8-2 BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-2 TABLE 1.8-201 (Sheet 1 of 3)
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure Number Departure Description Summary FSAR Section or Subsection STD DEP 1.1-1 An administrative departure is established to identify instances where the renumbering of FSAR sections is necessary to effectively include content consistent with Regulatory Guide 1.206, as well as NUREG-0800.(a) 2.1.1 2.1.4 2.2.1 2.2.4 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 BLN SUP 1.8-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-3 BLN DEP 2.3-1 In Revision 17 of the DCD the EAB atmospheric dispersion coefficients were revised to values that did not bound the BLN site-specific values. This departure provides the evaluation associated with the BLN site-specific parameter values.
Table 1.9-202, 6.2.6 Table 2.0-201 Table 2.0-202 6.2.5.1.2 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 was rearranged to simplify the design. The 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.
Figure 1.1-202 Figure 8.2-202 BLN DEP 9.2-1 The Service Water Cooling Tower blowdown flow will only be routed to the Waste Water Retention Basin.
9.2.1.2.1 TABLE 1.8-201 (Sheet 2 of 3)
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure Number Departure Description Summary FSAR Section or Subsection BLN SUP 1.8-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-4 BLN DEP 18.8-1 At Bellefonte, the Technical Support Center (TSC) is not located in the control support area (CSA) as identified in DCD Subsection 18.8.3.5; the TSC location is as described in the Emergency Plan. Additionally, the Operations Support Center (OSC) is also 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.
18.8.3.5 18.8.3.6 12.5.2.2 12.3 9A 1.2 a) The Departure is standard for AP1000 COLAs but the applicable FSAR Sections or Subsections may vary in the AP1000 Subsequent COLAs.
TABLE 1.8-201 (Sheet 3 of 3)
SUMMARY
OF FSAR DEPARTURES FROM THE DCD Departure Number Departure Description Summary FSAR Section or Subsection BLN SUP 1.8-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-5 TABLE 1.8-202 (Sheet 1 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B) 1.1-1 Construction and Startup Schedule 1.1.7 1.1.5 1.1.7 A
1.9-1 Regulatory Guide Conformance 1.9.1.5 1.9.1 1.9.1.1 1.9.1.2 1.9.1.3 1.9.1.4 1.9.1.5 Appendix 1A Appendix 1AA A
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 Issues Table 1.9-2 1.9.4.1 1.9.4.1 1.9.4.2.3 A
2.1-1 Geography and Demography 2.1.1 1.1.1 1.2.2 2.1 A
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 2.3.6.1 A
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-6 2.3-2 Local Meteorology 2.3.6.2 2.3.2 2.3.6.2 A
2.3-3 Onsite Meteorological Measurements Program 2.3.6.3 2.3.3 2.3.6.3 A
2.3-4 Short-Term Diffusion Estimates 2.3.6.4 2.3.4 2.3.6.4 15.6.5.3.7.3 15A.3.3 A
2.3-5 Long-Term Diffusion Estimates 2.3.6.5 2.3.5 2.3.6.5 A
2.4-1 Hydrological Description 2.4.1.1 2.4.1 2.4.8 2.4.15.1 A
2.4-2 Floods 2.4.1.2 2.4.2 2.4.3 2.4.4 2.4.5 2.4.6 2.4.7 2.4.10 2.4.15.2 A
TABLE 1.8-202 (Sheet 2 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-7 2.4-3 Cooling Water Supply 2.4.1.3 2.4.9 2.4.11 2.4.15.3 A
2.4-4 Groundwater 2.4.1.4 2.4.12.1 2.4.12.2 2.4.12.4 2.4.12.5 2.4.15.4 A
2.4-5 Accidental Release of Liquid Effluents into Ground and Surface Water 2.4.1.5 2.4.12.3 2.4.13 2.4.15.5 A
2.4-6 Flood Protection Emergency Operation Procedures 2.4.1.6 2.4.14 2.4.15.6 A
2.5-1 Basic Geologic and Seismic Information 2.5.1 2.5 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 A
TABLE 1.8-202 (Sheet 3 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-8 2.5-2 Site Seismic and Tectonic Characteristics Information 2.5.2.1 2.5.2 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 A
2.5-3 Geoscience Parameters 2.5.2.3 2.5.2.6 2.5.4.11 2.5.6.3 A
2.5-4 Surface Faulting 2.5.3 2.5.3 2.5.6.4 A
TABLE 1.8-202 (Sheet 4 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-9 2.5-5 Site and Structures 2.5.4.6.1 2.5.4 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 A
2.5-6 Properties of Underlying Materials 2.5.4.6.2 2.5.4.2.1 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 A
TABLE 1.8-202 (Sheet 5 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-10 2.5-7 Excavation and Backfill 2.5.4.6.3 2.5.4.5 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 A
2.5-8 Ground Water Conditions 2.5.4.6.4 2.5.4.5.2.2 2.5.4.6 2.5.4.6.3 2.5.4.6.8 A
2.5-9 Liquefaction Potential 2.5.4.6.5 2.5.4.8 2.5.4.6.9 A
2.5-10 Bearing Capacity 2.5.4.6.6 2.5.4.10 2.5.4.11 2.5.6.10 A
2.5-11 Earth Pressures 2.5.4.6.7 2.5.4.10.5 2.5.6.11 A
TABLE 1.8-202 (Sheet 6 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-11 2.5-12 Static and Dynamic Stability of Facilities 2.5.4.6.9 2.5.4.5.5 2.5.4.10.3 2.5.4.10.4 2.5.6.12 A
2.5-13 Subsurface Instrumentation 2.5.4.6.10 2.5.4.5.5 2.5.6.13 A
2.5-14 Stability of Slopes 2.5.5 2.5.5 2.5.6.14 A
2.5-15 Embankments and Dams 2.5.6 2.5.5 2.5.6.15 A
2.5-16 Settlement of Nuclear Island 2.5.4.6.11 2.5.4.10.4 2.5.6.16 A
3.3-1 Wind and Tornado Site Interface Criteria 3.3.3 1.2.2 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 A
TABLE 1.8-202 (Sheet 7 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-12 3.4-1 Site-Specific Flooding Hazards Protective Measures 3.4.3 3.4.1.3 3.4.3 A
3.5-1 External Missile Protection Requirements 3.5.4 1.2.2 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 A
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-Before-Break Piping 3.6.4.4 3.6.4.4 A
3.7-1 Seismic Analysis of Dams 3.7.5.1 3.7.2.12 3.7.5.1 A
3.7-2 Post-Earthquake Procedures 3.7.5.2 3.7.4.4 3.7.5.2 A
3.7-3 Seismic Interaction Review 3.7.5.3 3.7.5.3 H
TABLE 1.8-202 (Sheet 8 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-13 3.7-4 Reconciliation of Seismic Analyses of Nuclear Island Structures 3.7.5.4 3.7.5.4 H
3.7-5 Location of Free-Field Acceleration Sensor 3.7.5.5 3.7.4.2.1 3.7.5.5 A
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 3.9.8.3 A
3.9-4 Valve Inservice Testing 3.9.8.4 3.9.6 3.9.6.2.2 3.9.6.2.4 3.9.6.2.5 3.9.6.3 3.9.8.4 A
3.9-5 Surge Line Thermal Monitoring 3.9.8.5 3.9.3.1.2 3.9.8.5 A
3.11-1 Equipment Qualification File 3.11.5 3.11.5 H
4.4-2 Confirm Assumptions for Safety Analyses DNBR Limits 4.4.7.2 4.4.7 H
5.2-1 ASME Code and Addenda 5.2.6.1 5.2.1.1 5.2.6.1 A
TABLE 1.8-202 (Sheet 9 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-14 5.2-2 Plant Specific Inspection Program 5.2.6.2 5.2.4 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 A
5.3-1 Reactor Vessel Pressure - Temperature Limit Curves 5.3.6.1 5.3.6.1 H
5.3-2 Reactor Vessel Materials Surveillance Program 5.3.6.2 5.3.2.6 5.3.2.6.3 5.3.6.2 A
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 5.4.15 A
6.1-1 Procedure Review for Austenitic Stainless Steels 6.1.3.1 6.1.1.2 6.1.3.1 A
TABLE 1.8-202 (Sheet 10 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-15 6.1-2 Coating Program 6.1.3.2 6.1.2.1.6 6.1.3.2 A
6.2-1 Containment Leak Rate Testing 6.2.6 6.2.5.1 6.2.5.2.2 6.2.6 A
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 6.4.7 A
6.4-2 Procedures for Training for Control Room Habitability 6.4.7 6.4.3 6.4.7 A
6.6-1 Inspection Programs 6.6.9.1 6.6 6.6.1 6.6.3 6.6.4 6.6.6 6.6.9.1 A
6.6-2 Construction Activities 6.6.9.2 6.6.2 6.6.9.2 A
TABLE 1.8-202 (Sheet 11 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-16 8.2-1 Offsite Electrical Power 8.2.5 8.2.1 8.2.1.1 8.2.1.2 8.2.1.3 8.2.1.4 8.2.5 A
8.2-2 Technical Interfaces 8.2.5 8.2.1.2.2 8.2.2 8.2.5 A
8.3-1 Grounding and Lightning Protection 8.3.3 8.3.1.1.7 8.3.1.1.8 8.3.3 A
8.3-2 Onsite Electrical Power Plant Procedures 8.3.3 8.3.1.1.2.4 8.3.1.1.6 8.3.2.1.4 8.3.3 A
9.1-5 Inservice Inspection Program of Cranes 9.1.6.5 9.1.4.4 9.1.5.4 9.1.6 A
TABLE 1.8-202 (Sheet 12 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-17 9.1-6 Radiation Monitor 9.1.6.6 9.1.4.3.8 9.1.5.3 9.1.6 A
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 9.2.5.3 9.2.12.1 A
9.2-2 Waste Water Retention Basins 9.2.11.2 9.2.9.2.2 9.2.12.2 A
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 9.4.7.4 9.4.12 A
TABLE 1.8-202 (Sheet 13 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-18 9.5-1 Qualification Requirements for Fire Protection Program 9.5.1.8.1 9.5.1.6 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 A
9.5-2 Fire Protection Analysis Information 9.5.1.8.2 9.5.1.9.2 9A.3.3 A
9.5-3 Regulatory Conformance 9.5.1.8.3 9.5.1.8.8 9.5.1.8.9 9.5.1.9.3 9A.3.3 A
9.5-4 NFPA Exceptions 9.5.1.8.4 9.5.1.8.1.1 9.5.1.9.4 A
TABLE 1.8-202 (Sheet 14 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-19 9.5-6 Verification of Field Installed Fire Barriers 9.5.1.8.6 9.5.1.8.6 9.5.1.9.6 H
9.5-8 Establishment of Procedures to Minimize Risk for Fire Areas Breached During Maintenance 9.5.1.8.7 9.5.1.8.1.2.a.3.vi 9.5.1.9.7 A
9.5-9 Offsite Interfaces 9.5.2.5.1 9.5.2.2.3.1 9.5.2.5.1 A
9.5-10 Emergency Offsite Communications 9.5.2.5.2 9.5.2.2.3.2 9.5.2.5.2 A
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 9.5.4.7.2 A
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 10.4.5.2.2 10.4.5.5 10.4.12.1 A
10.4-2 Condensate, Feedwater and Auxiliary Steam System Chemistry Control 10.4.12.2 10.4.7.2.1 10.4.12.2 A
TABLE 1.8-202 (Sheet 15 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-20 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 11.2.5.1 A
11.2-2 Cost Benefit Analysis of Population Doses 11.2.5.2 11.2.3.3 11.2.3.5 11.2.5.2 A
11.3-1 Cost Benefit Analysis of Population Doses 11.3.5.1 11.3.3.4 11.3.5.1 A
11.4-1 Solid Waste Management System Process Control Program 11.4.6 11.4.6 A
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 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 A
TABLE 1.8-202 (Sheet 16 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-21 11.5-3 10 CFR 50, Appendix I 11.5.7 11.2.3.5 11.3.3.4 11.5.7 A
12.1-1 ALARA and Operational Policies 12.1.3 12.1 12.1.3 Appendix 12AA A
12.2-1 Additional Contained Radiation Sources 12.2.3 12.2.1.1.10 12.2.3 A
12.3-1 Administrative Controls for Radiological Protection 12.3.5.1 12.3.5.1 Appendix 12AA A
12.3-2 Criteria and Methods for Radiological Protection 12.3.5.2 12.3.4 12.3.5.2 A
12.3-3 Groundwater Monitoring Program 12.3.5.3 12.3.5.3 Appendix 12AA A
12.3-4 Record of Operational Events of Interest for Decommissioning 12.3.5.4 12.3.5.4 Appendix 12AA A
12.5-1 Radiological Protection Organization and Procedures 12.5.5 12.5.5 Appendix 12AA A
TABLE 1.8-202 (Sheet 17 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-22 13.1-1 Organizational Structure of Combined License Applicant 13.1.1 13.1 13.1.4 Appendix 13AA A
13.2-1 Training Program for Plant Personnel 13.2.1 13.2 13.2.1 A
13.3-1 Emergency Planning and Communications 13.3.1 13.3 13.3.1 A
13.3-2 Activation of Emergency Operations Facility 13.3.1 13.3 13.3.1 A
13.4-1 Operational Review 13.4.1 13.4 13.4.1 A
13.5-1 Plant Procedures 13.5.1 13.5 13.5.3 A
13.6-1 Security 13.6 13.6 13.6.1 A
13.6-5 Cyber Security Program 13.6.1 13.6 13.6.1 H
14.4-1 Organization and Staffing 14.4.1 14.2.2 14.4.1 A
TABLE 1.8-202 (Sheet 18 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-23 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 14.4.4 H
14.4-5 Testing Interface Requirements 14.4.5 14.2.9.4.15 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 A
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 15.7.6 A
16.1-1 Technical Specification Preliminary Information 16.1 16.1.1 A
16.3-1 Procedure to Control Operability of Investment Protection Systems, Structures and Components 16.3.2 16.3.1 16.3.2 A
TABLE 1.8-202 (Sheet 19 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-24 17.5-1 Quality Assurance Design Phase 17.5.1 17.1 17.5 17.7 A
17.5-2 Quality Assurance for Procurement, Fabrication, Installation, Construction and Testing 17.5.2 17.5 17.7 A
17.5-4 Quality Assurance Program for Operations 17.5.4 17.5 17.7 A
17.5-8 Operational Reliability Assurance Program Integration with Quality Assurance Program 17.5.8 17.5 17.7 A
18.2-2 Design of the Emergency Operations Facility 18.2.6.2 18.2.1.3 18.2.6.2 A
18.6-1 Plant Staffing 18.6.1 13.1.1.4 13.1.3.1 13.1.3.2 18.6 18.6.1 A
18.10-1 Training Program Development 18.10.1 13.1.1.3.1.9 13.1.1.3.2.4 13.2 18.10 18.10.1 A
TABLE 1.8-202 (Sheet 20 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-25 18.14-1 Human Performance Monitoring 18.14 18.14 A
19.59.10-1 As-Built SSC HCLPF Comparison to Seismic Margin Evaluation 19.59.10.5 19.59.10.5 H
19.59.10-2 Evaluation of As-Built Plant Versus Design in AP1000 PRA and Site-Specific PRA External Events 19.59.10.5 19.59.10.5 B
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.
TABLE 1.8-202 (Sheet 21 of 21)
COL ITEM TABULATION COL ITEM SUBJECT DCD SUBSECTION FSAR SECTION(S)
COL APPLICANT (A),
HOLDER (H)
OR BOTH (B)
BLN SUP 1.8-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-26 TABLE 1.8-203 (Sheet 1 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection 2.1 Envelope of AP1000 plant site related parameters Site Interface Site specific parameters Table 2.0-201 2.2 External missiles from man-made hazards and accidents Site Interface Site specific parameters 2.2.2.2, 2.2.3.1, 3.5 2.3 Maximum loads from man-made hazards and accidents Site Interface Site specific parameters Table 2.0-201 2.4 Limiting meteorological parameters (/Q) for design basis accidents and for routine releases and other extreme meteorological conditions for the design of systems and components exposed to the environment.
Site Interface Site specific parameters Table 2.0-201 2.5 Tornado and operating basis wind loadings Site Interface Site specific parameters Table 2.0-201 2.6 External missiles generated by natural phenomena Site Interface Site specific parameters Table 2.0-201 2.7 Snow, ice and rain loads Site Interface Site specific parameters 2.3.1.2 2.8 Ambient air temperatures Site Interface Site specific parameters Table 2.0-201 BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-27 2.9 Onsite meteorological measurement program Requirement of AP1000 Combined License applicant program 2.3.3 2.10 Flood and ground water elevations Site Interface Site specific parameters Table 2.0-201 2.11 Hydrostatic loads on systems, components and structures Site Interface Site specific parameters Table 2.0-201 2.12 Seismic parameters peak ground acceleration response spectra shear wave velocity Site Interface Site specific parameters Table 2.0-201 2.13 Required bearing capacity of foundation materials Site Interface Site specific parameters Table 2.0-201 3.1 Deleted N/A N/A N/A 3.2 Operating procedures to minimize water hammer Requirement of AP1000 Combined License applicant procedure 10.3.2.2.1, 10.4.7.2.1 3.3 Site seismic sensor location and "trigger" value Requirement of AP1000 Onsite implementation 3.7.4.2.1 3.4 Depth of overburden Requirement of AP1000 Onsite implementation 3.8.5.1, 2.5.4 3.5 Depth of embedment Requirement of AP1000 Onsite implementation 3.8.5.1, 2.5.4 TABLE 1.8-203 (Sheet 2 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-28 3.6 Specific depth of waterproofing Requirement of AP1000 Onsite implementation 2.5.4.1 3.7 Foundation Settlement Monitoring Requirement of AP1000 Combined License applicant coordination 2.5.4.10.4 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 3.10 Inservice Inspection requirements and locations Requirement of AP1000 Combined License applicant program 3.9.6, 5.2.4, 6.6 3.11 Maintenance of preservice and reference test data for inservice testing of pumps and valves Requirement of AP1000 Combined License applicant program 3.9.6 3.12 Earthquake response procedures Requirement of AP1000 Combined License applicant program 3.7.4.4 5.1 Steam Generator Tube Surveillance Requirements Requirement of AP1000 Combined License applicant program 5.4.2.5 6.1 Inservice Inspection requirements for the containment Requirement of AP1000 Combined License applicant program 6.6 TABLE 1.8-203 (Sheet 3 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-29 6.2 Off site environmental conditions assumed for Main Control Room and control support area habitability design AP1000 Interface Site specific parameter 2.2.3, 6.4 7.1 Listing of all design criteria applied to the design of the I&C systems Not an Interface N/A N/A 7.2 Power required for site service water instrumentation NNS and Not an Interface N/A N/A 7.3 Other provisions for site service water instrumentation NNS and Not an Interface N/A N/A 8.1 Listing of design criteria applied to the design of the offsite power system NNS Combined License applicant coordination 8.1.4.3 8.2 Offsite ac requirements:
- Steady-state load;
- Inrush kVA for motors;
- Nominal voltage;
- Allowable voltage regulation;
- Nominal frequency;
- Allowable frequency fluctuation;
- Maximum frequency decay rate;
- Limiting under frequency value for RCP NNS Combined License applicant coordination 8.2.2 TABLE 1.8-203 (Sheet 4 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-30 8.3 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 in Chapter 15 analyses for a minimum of three (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.
NNS Combined License applicant analysis 8.2.2, 8.2.1.2.2 8.4 Listing of design criteria applied to the design of onsite ac power systems NNS and Not an Interface N/A N/A 8.5 Onsite ac requirements NNS and Not an Interface N/A N/A 8.6 Diesel generator room coordination NNS and Not an Interface N/A N/A 8.7 Listing of design criteria applied to the design of onsite dc power systems Not an Interface N/A N/A 8.8 Provisions of dc power systems to accommodate the site service water system NNS and Not an Interface N/A N/A TABLE 1.8-203 (Sheet 5 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-31 9.1 Listing of design criteria applied to the design of portions of the site service water within AP1000 NNS and Not an Interface N/A N/A 9.2 Integrated heat load to site service water system NNS and Not an Interface N/A N/A 9.3 Plant cooling water systems parameters NNS and Not an Interface N/A N/A 9.4 Plant makeup water quality limits NNS Site specific parameter 9.2.11 9.5 Requirements for location and arrangement of raw and sanitary water systems NNS Site implementation 9.2.5, 9.2.11 9.6 Ventilation requirements for diesel-generator room NNS and Not an Interface N/A N/A 9.7 Requirements to satisfy fire protection program AP1000 Interface Combined License applicant program 9.5.1 11.1 Expected release rates of radioactive material from the Liquid Waste System including:
- Location of release points
- Effluent temperature
- Effluent flow rate
- Size and shape of flow orifices Site Interface Site specific parameters 11.2 TABLE 1.8-203 (Sheet 6 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-32 11.2 Expected release rates of radioactive materials from the Gaseous Waste System including:
- Location of release points
- Height above grade
- Height relative to adjacent buildings
- Effluent temperature
- Effluent flow rate
- Effluent velocity
- Size and shape of flow orifices Site Interface Site specific parameters 11.3 11.3 Expected release rates of radioactive material from the Solid Waste System including:
- Location of release points
- Material types
- Material qualities
- Size and shape of material containers Site Interface Site specific parameters 11.4.6 11.4 Requirements for offsite sampling and monitoring of effluent concentrations AP1000 Interface Combined License applicant program 11.5.3, 11.5.7 12.1 Identification of miscellaneous radioactive sources AP1000 Interface Combined License applicant program 12.2.1 13.1 Features that may affect plans for coping with emergencies as specified in 10 CFR 50, Appendix O AP1000 Interface Combined License applicant program 13.3 TABLE 1.8-203 (Sheet 7 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-33 13.2 Physical Security Plan consistent with AP1000 plant AP1000 Interface Combined License applicant program 13.6 14.1 Identification of special features to be considered in development of the initial test program Requirement of AP1000 Combined License applicant program 14 14.2 Maintenance of preoperational test data and inservice inspection baseline data AP1000 Interface Combined License applicant program 14 16.1 Administrative requirements associated with reliability information maintenance AP1000 Interface Combined License applicant program 16 16.2 Administrative requirements associated with the Technical Specifications Requirement of AP1000 Combined License applicant implementation 16 16.3 Site and operator related information associated with the Reliability Assurance Program (D-RAP)
Requirement of AP1000 Combined License applicant program 16.2 18.1 Operating staff consistent with Human Factors evaluations AP1000 Interface Combined License applicant program 18.6 18.2 Operator training consistent with Human Factors evaluations AP1000 Interface Combined License applicant program 18.8, 18.10 TABLE 1.8-203 (Sheet 8 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.8-34 Note 1 - This table supplements DCD Table 1.8-1 by providing additional information in the Section or Subsection column.
18.3 Operating Procedures consistent with Human Factors evaluations AP1000 Interface Combined License applicant program 18.8, 18.10 TABLE 1.8-203 (Sheet 9 of 9)
SUMMARY
OF FSAR DISCUSSIONS OF AP1000 PLANT INTERFACES Item No.
Interface Interface Type Matching Interface Item Section(1) or Subsection BLN SUP 1.8-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-1 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:
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:
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 STD COL 1.9-1 STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-2 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:
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:
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 STD COL 1.9-1 STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-3 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:
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:
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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-4 1.9.2 COMPLIANCE WITH STANDARD REVIEW PLAN (NUREG-0800)
Add the following paragraph to the end of DCD Subsection 1.9.2:
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:
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 Add the following text in DCD Subsection 1.9.4.2.3., following the AP1000 Position for Issue 185.
STD SUP 1.9-1 STD COL 1.9-3 STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-5 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.
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 STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-6 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 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 STD SUP 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-7 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:
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.
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 STD SUP 1.9-2 STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-8 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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-9 TABLE 1.9-201 (Sheet 1 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona Division 1 Regulatory Guides 1.6 Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Rev. 0, March 1971) 16 (TS Bases 3.8.1) 1.7 Control of Combustible Gas Concentrations in Containment (Rev. 3, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.8 Qualification and Training of Personnel for Nuclear Power Plants (Rev. 3, May 2000) 12.1 (NEI 07-08A)
Appendix 12AA 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 for Earthquakes (Rev. 2, March 1997) 3.7.4.1 1.13 Spent Fuel Storage Facility Design Basis (Rev. 2, March 2007) 16 (TS Bases 3.7.11) 16 (TS Bases 3.7.12) 1.20 Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing (Rev. 3, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.21 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 (Rev.1, June 1974) 2.3.3.2.3 11.5.1.2 11.5.4.1 12.3.4 1.23 Meteorological Monitoring Program for Nuclear Power Plants (Rev. 1, March 2007) 2.3.3.2 2.3.4.2 2.3.4.3 STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-10 1.26 Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants (Rev. 4, March 2007) 5.2.4.1 17.5 (QAPD IV) 1.27 Ultimate Heat Sink for Nuclear Power Plants (Rev. 2, January 1976) 2.4.11.6 1.28 Quality Assurance Program Requirements (Design and Construction) (Rev. 3, August 1985) 17.5 (QAPD, II, 17.1) 17.5 (QAPD, IV) 1.29 Seismic Design Classification (Rev. 4, March 2007) 17.5 (QAPD IV) 1.30 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Rev. 0, August 1972)
Not referenced; see Appendix 1AA 1.31 Control of Ferrite Content in Stainless Steel Weld Metal (Rev. 3, April 1978) 6.1.1.2 1.32 Criteria for Power Systems for Nuclear Power Plants (Rev. 3, March 2004) 16 (TS Bases 3.8.1) 1.33 Quality Assurance Program Requirements (Operation) (Rev. 2, February 1978) 16 (TS 5.4.1) 17.5 (QAPD, IV) 1.37 Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants (Rev. 1, March 2007) 17.5 (QAPD IV) 17.5 (QAPD, II, 13.2) 1.38 Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants (Rev. 2, May 1977)
DCD discussion only; see DCD Table 1.9-1 TABLE 1.9-201 (Sheet 2 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-11 1.39 Housekeeping Requirements for Water-Cooled Nuclear Power Plants (Rev. 2, September 1977)
DCD discussion only; see DCD Table 1.9-1 1.44 Control of the Use of Sensitized Stainless Steel (Rev. 0, May 1973) 6.1.1.2 1.45 Reactor Coolant Pressure Boundary Leakage Detection Systems (Rev. 0, May 1973) 16 (TS Bases 3.4.7) 16 (TS Bases 3.4.9) 1.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems (Rev. 2, November 2003)
DCD discussion only; see DCD Table 1.9-1 1.54 Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants (Rev. 1, July 2000) 1.9.4.2.3 6.1.2.1.6 1.57 Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components (Rev. 1, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.59 Design Basis Floods for Nuclear Power Plants (Rev. 2, August 1977) 2.4.2.2 2.4.3 2.4.4 2.4.4.1 2.4.5 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants (Rev. 1, December 1973)
Table 2.0-201 1.61 Damping Values for Seismic Design of Nuclear Power Plants (Rev. 1, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.68 Initial Test Program for Water-Cooled Nuclear Power Plants (Rev. 3, March 2007) 14.2.1 14.2.3 14.2.5.2 14.2.8 16 (TS Bases 3.1.8)
TABLE 1.9-201 (Sheet 3 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-12 1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) (Rev. 3, November 1978) 1.1.6.1 1.71 Welder Qualification for Areas of Limited Accessibility (Rev 1, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.75 Criteria for Independence of Electrical Safety Systems (Rev 3, February 2005)
DCD discussion only; see DCD Table 1.9-1 1.76 Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants (Rev. 1, March 2007)
Table 2.0-201 2.3.1.4 1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors (Rev 0, May 1974) 16 (TS Bases 3.2.1) 16 (TS Bases 3.2.2) 16 (TS Bases 3.2.4) 16 (TS Bases 3.2.5) 1.78 Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release (Rev. 1, December 2001) 2.2.3.1.3 6.4.3 6.4.4.2 16 (TS Bases 3.7.6) 1.82 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident (Rev. 3, November 2003)
DCD discussion only; see DCD Table 1.9-1 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes (Rev. 1, July 1975)
DCD discussion only; see DCD Table 1.9-1 1.84 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (Rev. 33, August 2005)
DCD discussion only; see DCD Table 1.9-1 1.86 Termination of Operating Licenses for Nuclear Reactors (Rev. 0, June 1974)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 4 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-13 1.91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants (Rev. 1, February 1978) 2.2.3.1.1 2.2.3.2 3.5.1.5 Table 19.58-201 1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis (Rev. 2, July 2006)
DCD discussion only; see DCD Table 1.9-1 1.93 Availability of Electric Power Sources (Rev. 0, December 1974) 16 (TS Bases 3.8.1) 16 (TS Bases 3.8.5) 1.94 Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Rev. 1, April 1976)
Not referenced; see Appendix 1AA 1.97 Criteria For Accident Monitoring Instrumentation For Nuclear Power Plants (Rev. 4, June 2006)
Not refererenced; see Appendix 1AA 1.97 Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Environs Conditions During and Following an Accident (Rev. 3, May 1983)
Table 7.5-201 Appendix 12AA 16 (TS Bases 3.3.3) 1.99 Radiation Embrittlement of Reactor Vessel Materials (Rev. 2, May 1988) 16 (TS Bases 3.4.3) 1.101 Emergency Response Planning and Preparedness for Nuclear Power Reactors (Rev. 5, June 2005)
Not referenced; see Appendix 1AA 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors (Rev. 4, July 2003)
Not referenced; see Appendix 1AA 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors (Rev. 3, August 1992) 9.5.1.8.2.2 Table 9.5-201 13.3 (Emergency Plan I.C.1)
TABLE 1.9-201 (Sheet 5 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-14 1.109 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 (Rev. 1, October 1977) 11.2.3.5 11.3.3.4 12.4.1.9.3 Table 12.4-201 1.110 Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (Draft Rev. 0, March 1976) 11.2.3.5.3 11.3.3.4.3 1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors (Rev. 1, July 1977) 2.3.5.1 12.4.1.9.3 1.112 Calculation of Releases of Radioactive Materials in Gaseous or Liquid Effluents from Light-Water-Cooled Nuclear Power Reactors (Rev. 1, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.113 Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I (Rev. 1, April 1977) 11.2.3.3 1.114 Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit (Rev. 2, May 1989) 13.1.2.1.2.6 13.1.2.1.3 1.115 Protection Against Low-Trajectory Turbine Missiles (Rev. 1, July 1977) 3.5.1.3 1.116 Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems (Rev. 0-R, May 1977)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 6 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-15 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (Rev. 0, August 1976) 16 (TS Bases 3.4.18) 1.124 Service Limits and Loading Combinations for Class 1 Linear-Type Supports (Rev. 2, February 2007)
DCD discussion only; see DCD Table 1.9-1 1.128 Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Rev. 2, February 2007)
DCD discussion only; see DCD Table 1.9-1 1.129 Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Rev. 2, February 2007)
Table 8.1-201 8.3.2.1.4 16 (TS Bases 3.8.1) 1.130 Service Limits and Loading Combinations for Class 1 Plate-And-Shell-Type Supports (Rev. 2, March 2007)
DCD discussion only; see DCD Table 1.9-1 1.132 Site Investigations for Foundations of Nuclear Power Plants (Rev. 2, October 2003) 2.5.4.2.1 2.5.4.4 1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Rev. 1, May 1981)
Not referenced; see Appendix 1AA 1.134 Medical Evaluation of Licensed Personnel at Nuclear Power Plants (Rev. 3, March 1998)
Not referenced; see Appendix 1AA 1.135 Normal Water Level and Discharge at Nuclear Power Plants (Rev. 0, September 1977)
Not referenced; see Appendix 1AA 1.138 Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants (Rev. 2, December 2003) 2.5.4.2.1 TABLE 1.9-201 (Sheet 7 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-16 1.139 Guidance for Residual Heat Removal (Rev. 0, May 1978)
DCD discussion only; see DCD Table 1.9-1 1.140 Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants (Rev. 2, June 2001) 9.4.1.4 9.4.7.4 16 (TS Bases 3.9.6) 1.143 Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Rev. 2, November 2001) 11.2.1.2.5.2 11.2.3.6 11.3.3.6 11.4.5 11.4.6.2 1.145 Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (Rev. 1, November 1982) 2.3.4.1 2.3.4.2 1.147 Inservice Inspection Code Case Acceptability, ASME section XI, Division 1 (Rev. 15, October 2007) 5.2.4 6.6 1.149 Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations (Rev. 3, October 2001) 13.2 (NEI 06-13A) 1.150 Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations (Rev. 1, February 1983)
DCD discussion only; see DCD Table 1.9-1 1.152 Criteria for Use of Computers in Safety Systems of Nuclear Power Plants (Rev. 2, January 2006)
Not referenced; see Appendix 1AA 1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors (Rev. 0, January 1987)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 8 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-17 1.155 Station Blackout (Rev. 0, August 1998) Table 8.1-201 1.159 Assuring the Availability of Funds for Decommissioning Nuclear Reactors (Rev. 1, October 2003)
Not referenced; see Appendix 1AA 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Rev. 2, March 1997) 17.6 (NEI 07-02A) 1.162 Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels (Rev. 0, February 1996)
Not referenced; see Appendix 1AA 1.163 Performance-Based Containment Leak-Test Program (Rev. 0, September 1995) 6.2.5.1 6.2.5.2.2 16 (TS 5.5.8) 1.165 Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion (Rev. 0, March 1997)
Not referenced; see Appendix 1AA 1.166 Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post Earthquake Actions (Rev. 0, March 1997) 3.7.4.4 1.167 Restart of a Nuclear Power Plant Shut Down by a Seismic Event (Rev. 0, March 1997) 3.7.4.4 1.168 Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Rev. 1, February 2004)
DCD discussion only; see DCD Table 1.9-1 1.174 An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis (Rev. 1, November 2002)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 9 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-18 1.175 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (Rev. 0, August 1998)
Not referenced; see Appendix 1AA 1.177 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications (Rev. 0, August 1998) 16 (TS Bases 3.5.1) 16 (TS Bases 3.7.10) 1.178 An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping (Rev. 1, September 2003)
Not referenced; see Appendix 1AA 1.179 Standard Format and Content of License Termination Plans for Nuclear Power Reactors (Rev. 0, January 1999)
Not referenced; see Appendix 1AA 1.180 Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems (Rev. 1, October 2003)
DCD discussion only; see DCD Table 1.9-1 1.181 Content of Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) (Rev. 0, September 1999)
Not referenced; see Appendix 1AA 1.182 Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants (Rev. 0, May 2000) 16 (TS Bases SR 3.0.3) 17.6 (NEI 07-02A) 1.183 Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 0, July 2000) 16 (TS Bases 3.7.5) 16 (TS Bases 3.9.4) 16 (TS Bases 3.9.7) 1.184 Decommissioning of Nuclear Power Reactors (Rev. 0, July 2000)
Not referenced; see Appendix 1AA 1.185 Standard Format and Content for Post-shutdown Decommissioning Activities Report (Rev. 0, July 2000)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 10 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-19 1.186 Guidance and Examples for Identifying 10 CFR 50.2 Design Bases (Rev. 0, December 2000)
Not referenced; see Appendix 1AA 1.187 Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiment (Rev. 0, November 2000)
Not referenced; see Appendix 1AA 1.188 Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses (Rev. 1, September 2005)
Not referenced; see Appendix 1AA 1.189 Fire Protection for Nuclear Power Plants (Rev. 1, March 2007) 9.5.1.8.1.1 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 Power Plants During Decommissioning and Permanent Shutdown (Rev. 0, May 2001)
Not referenced; see Appendix 1AA 1.192 Operation and Maintenance Code Case Acceptability, ASME OM Code (Rev. 0, June 2003) 3.9.6.3 1.193 ASME Code Cases Not Approved for Use (Rev 1, August 2005)
Not referenced; see Appendix 1AA 1.194 Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants (Rev. 0, June 2003) 2.3.4.3 1.195 Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors (Rev. 0, May 2003)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 11 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-20 1.196 Control Room Habitability at Light-Water Nuclear Power Reactors (Rev. 1, January 2007) 6.4.3 1.197 Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors (Rev. 0, February 2003)
DCD discussion only; see DCD Table 1.9-1 1.198 Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites (Rev. 0, November 2003) 2.5.4.8 1.199 Anchoring Components and Structural Supports in Concrete (Rev. 0, November 2003)
Not referenced; see Appendix 1AA 1.200 An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (Rev. 1, January 2007) 19.59.10.6 1.201 Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance (Rev. 1, May 2006)
Not referenced; see Appendix 1AA 1.202 Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors (Rev. 0, February 2005)
Not referenced; see Appendix 1AA 1.203 Transient and Accident Analysis Methods (Rev. 0, December 2005)
Not referenced; see Appendix 1AA 1.204 Guidelines for Lightning Protection of Nuclear Power Plants (Rev. 0, November 2005)
Table 8.1-201 1.205 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants (Rev. 0, May 2006)
Not referenced; see Appendix 1AA TABLE 1.9-201 (Sheet 12 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-21 1.206 Combined License Applications for Nuclear Power Plants (LWR Edition)
(Rev. 0, June 2007)
See Appendix 1AA.
1.1.6.1 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 Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Rev. 0, March 2007)
Not referenced; see Appendix 1AA 1.208 A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion (Rev. 0, March 2007) 2.5.1 2.5.2 2.5.3 2.5.4 1.209 Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants (Rev. 0, March 2007)
Not referenced; see Appendix 1AA Division 4 Regulatory Guides 4.7 General Site Suitability Criteria for Nuclear Power Stations (Rev. 2, April 1998)
Not referenced; see Appendix 1AA 4.15 Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent Streams and the Environment (Rev. 2, July 2007) 11.5.3 TABLE 1.9-201 (Sheet 13 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-22 4.15 Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) Effluent Streams and the Environment (Rev. 1, February 1979) 11.5.1.2 11.5.3 11.5.4 11.5.6.5 Division 5 Regulatory Guides 5.9 Guidelines for Germanium Spectroscopy Systems for Measurements of Special Nuclear Material (Rev. 2, December 1983)
Not referenced; see Appendix 1AA 5.12 General Use of Locks in the Protection and Controls of Facilities and Special Nuclear Materials (Rev. 0, November 1973)
Not referenced; see Appendix 1AA 5.65 Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls (Rev. 0, September 1986)
Not referenced; see Appendix 1AA Division 8 Regulatory Guides 8.2 Guide for Administrative Practices in Radiation Monitoring (Rev. 0, February 1973) 12.1 (NEI 07-08A) 12.3.4 Appendix 12AA (NEI 07-03A) 8.4 Direct-Reading and Indirect-Reading Pocket Dosimeters (Rev. 0, February 1973)
Appendix 12AA (NEI 07-03A) 8.5 Criticality and Other Interior Evacuation Signals (Rev. 1, March 1981)
Appendix 12AA (NEI 07-03A) 8.6 Standard Test Procedure for Geiger-Muller Counters (Rev. 0, May 1973)
Appendix 12AA (NEI 07-03A) 8.7 Instructions for Recording and Reporting Occupational Radiation Exposure Data (Rev. 2, November 2005) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A)
TABLE 1.9-201 (Sheet 14 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-23 8.8 Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable (Rev. 3, June 1978) 12.1 (NEI 07-08A) 12.3.4 Appendix 12AA Appendix 12AA (NEI 07-03A) 13.1.2.1.1 13.1.2.1.1.5 8.9 Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program (Rev. 1, July 1993) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable (Rev. 1-R, May 1977) 12.1 (NEI 07-08A) 12.3.4 Appendix 12AA Appendix 12AA (NEI 07-03A) 13.1.2.1.1 13.1.2.1.1.5 8.13 Instruction Concerning Prenatal Radiation Exposure (Rev. 3, June 1999) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.15 Acceptable Programs for Respiratory Protection (Rev. 1, October 1999) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.27 Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants (Rev. 0, March 1981) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.28 Audible-Alarm Dosimeters (Rev. 0, August 1981) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.29 Instruction Concerning Risks from Occupational Radiation Exposure (Rev. 1, February 1996) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.34 Monitoring Criteria and Methods To Calculate Occupational Radiation Doses (Rev. 0, July 1992) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.35 Planned Special Exposures (Rev. 0, June 1992) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A)
TABLE 1.9-201 (Sheet 15 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-24 8.36 Radiation Dose to the Embryo/Fetus (Rev. 0, July 1992) 12.1 (NEI 07-08A)
Appendix 12AA (NEI 07-03A) 8.38 Control of Access to High and Very High Radiation Areas of Nuclear Plants (Rev. 1, May 2006) 12.1 (NEI 07-08A)
Appendix 12AA Table 12AA-201 Appendix 12AA (NEI 07-03A) a.
NEI templates are incorporated by reference. See Table 1.6-201.
TABLE 1.9-201 (Sheet 16 of 16)
REGULATORY GUIDE/FSAR SECTION CROSS-REFERENCES Regulatory Guides FSAR Chapter, Section, or Subsectiona STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-25 TABLE 1.9-202 (Sheet 1 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions 1
Introduction and Interfaces, Initial Issuance, 03/2007 N/A No specific acceptance criteria associated with these general requirements.
2.0 Site Characteristics and Site Parameters, Initial Issuance, 03/2007 N/A No specific acceptance 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 for Accident Releases Acceptable 2.3.5 Long-Term Atmospheric Dispersion Estimates for Routine Releases Acceptable 2.4.1 Hydrologic Description Acceptable 2.4.2 Floods, Rev. 4, 03/2007 Acceptable STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-26 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers, Rev. 4, 03/2007 Acceptable 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 Effluents in Ground and Surface Waters Acceptable 2.4.14 Technical Specifications and Emergency Operation Requirements Acceptable 2.5.1 Basic Geologic and Seismic Information, Rev.4, 03/2007 Acceptable TABLE 1.9-202 (Sheet 2 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-27 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 Foundations Acceptable TABLE 1.9-202 (Sheet 3 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-28 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, 03/2007 See Notes d and e.
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 Failures Acceptable See Notes d, e, and f.
3.4.2 Analysis Procedures See Notes d and e.
3.5.1.1 Internally Generated Missiles (Outside Containment)
See Notes d and e.
3.5.1.2 Internally Generated Missiles (Inside Containment)
See Notes d and e.
3.5.1.3 Turbine Missiles Acceptable See Notes d, e, and f.
3.5.1.4 Missiles Generated by Tornadoes and Extreme Winds See Notes d and e.
3.5.1.5 Site Proximity Missiles (Except Aircraft), Rev.4, 03/2007 Acceptable See Notes d, e, and f.
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.
TABLE 1.9-202 (Sheet 4 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-29 3.5.2 Structures, Systems, and Components to be Protected from Externally-Generated Missiles See Notes d and e.
3.5.3 Barrier Design Procedures See Notes d and e.
3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment See Notes d and e.
3.6.2 Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
3.6.3 Leak-Before-Break Evaluation Procedures, Rev. 1, 03/2007 Acceptable See Notes d, e, and f.
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 Concrete Containments, Rev. 2, 03/2007 See Notes d and e.
3.8.4 Other Seismic Category I Structures, Rev. 2, 03/2007 See Notes d and e.
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.
TABLE 1.9-202 (Sheet 5 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-30 3.9.2 Dynamic Testing and Analysis of Systems, Structures, and Components See Notes d and e.
3.9.3 ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
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 Testing Programs for Pumps, Valves, and Dynamic Restraints Acceptable See Notes d, e, and f.
3.9.7 Risk-Informed Inservice Testing, Rev. 0, 08/1998 N/A 3.9.8 Risk-Informed Inservice Inspection of Piping, Rev.0, 09/2003 N/A 3.10 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment See Notes d and e.
3.11 Environmental Qualification of Mechanical and Electrical Equipment Acceptable See Notes d, e, and f.
3.12 ASME Code Class 1, 2, and 3 Piping Systems, Piping Components and their Associated Supports, Initial Issuance, 03/2007 See Note g.
3.13 Threaded Fasteners - ASME Code Class 1, 2, and 3, Initial Issuance, 03/2007 See Note g.
4.2 Fuel System Design See Notes d and e.
4.3 Nuclear Design See Notes d and e.
TABLE 1.9-202 (Sheet 6 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-31 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 Materials See Notes d and e.
4.6 Functional Design of Control Rod Drive System, Rev. 2, 03/2007 See Notes d and e.
5.2.1.1 Compliance with the Codes and Standards Rule, 10 CFR 50.55a Acceptable See Notes d, e, and f.
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 Inspection and Testing, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
5.2.5 Reactor Coolant Pressure Boundary Leakage Detection, Rev. 2, 03/2007 See Notes d and e.
5.3.1 Reactor Vessel Materials, Rev. 2, 03/2007 See Notes d and e.
5.3.2 Pressure-Temperature Limits, Upper-Shelf Energy, and Pressurized Thermal Shock, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
5.3.3 Reactor Vessel Integrity, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
5.4 Reactor Coolant System Component and Subsystem Design, Rev. 2, 03/2007 N/A No specific acceptance criteria associated with these general requirements.
5.4.1.1 Pump Flywheel Integrity (PWR), Rev. 2, 03/2007 See Notes d and e.
TABLE 1.9-202 (Sheet 7 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-32 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),
Rev. 4, 03/2007 N/A 5.4.7 Residual Heat Removal (RHR) System, Rev. 4, 03/2007 See Notes d and e.
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, Rev. 1, 03/2007 See Notes d and e.
5.4.13 Isolation Condenser System (BWR), Initial Issuance, 03/2007 N/A 6.1.1 Engineered Safety Features Materials, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
6.1.2 Protective Coating Systems (Paints) - Organic Materials Acceptable See Notes d, e, and f.
6.2.1 Containment Functional Design See Notes d and e.
6.2.1.1.A PWR Dry Containments, Including Subatmospheric Containments See Notes d and e.
6.2.1.1.B Ice Condenser Containments, Rev. 2, 07/1981 N/A 6.2.1.1.C Pressure-Suppression Type BWR Containments, Rev. 7, 03/2007 N/A 6.2.1.2 Subcompartment Analysis See Notes d and e.
TABLE 1.9-202 (Sheet 8 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-33 6.2.1.3 Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accidents (LOCAs)
See Notes d and e.
6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures, Rev. 2, 03/2007 See Notes d and e.
6.2.1.5 Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance Capability Studies See Notes d and e.
6.2.2 Containment Heat Removal Systems, Rev. 5, 03/2007 See Notes d and e.
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.
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 Boundary, Rev. 1, 03/2007 See Notes d and e.
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.
TABLE 1.9-202 (Sheet 9 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1 BLN SUP 1.9-4
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-34 6.5.1 ESF Atmosphere Cleanup Systems See Notes d and e.
6.5.2 Containment Spray as a Fission Product Cleanup System, Rev. 4, 03/2007 See Notes d and e.
6.5.3 Fission Product Control Systems and Structures See Notes d and e.
6.5.4 Ice Condenser as a Fission Product Cleanup System, Rev. 3, 12/1988 N/A 6.5.5 Pressure Suppression Pool as a Fission Product Cleanup System, Rev. 1, 03/2007 N/A 6.6 Inservice Inspection and Testing of Class 2 and 3 Components, Rev. 2, 03/2007 Acceptable See Notes d, e, and f.
6.7 Main Steam Isolation Valve Leakage Control System (BWR), Rev. 2, 07/1981 N/A 7
Instrumentation and Controls -Overview of Review Process, Rev. 5, 03/2007 See Notes d and e.
Appendix 7.0-A Review Process for Digital Instrumentation and Control Systems, Rev. 5, 03/2007 See Notes d and e.
7.1 Instrumentation and Controls -Introduction, Rev. 5, 03/2007 See Notes d and e.
7.1-T Table 7-1 Regulatory Requirements, Acceptance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety, Rev. 5, 03/2007 See Notes d and e.
Appendix 7.1-A Acceptance Criteria and Guidelines for Instrumentation and Controls Systems Important to Safety, Rev. 5, 03/2007 See Notes d and e.
TABLE 1.9-202 (Sheet 10 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-35 Appendix 7.1-B Guidance for Evaluation of Conformance to IEEE Std 279, Rev. 5, 03/2007 See Notes d and e.
Appendix 7.1-C Guidance for Evaluation of Conformance to IEEE Std 603, Rev. 5, 03/2007 See Notes d and e.
Appendix 7.1-D Guidance for Evaluation of the Application of IEEE Std 7-4.3.2 Initial Issuance 03/2007 See Notes d and e.
7.2 Reactor Trip System, Rev. 5, 03/2007 See Notes d and e.
7.3 Engineered Safety Features Systems, Rev. 5, 03/2007 See Notes d and e.
7.4 Safe Shutdown Systems, Rev. 5, 03/2007 See Notes d and e.
7.5 Information Systems Important to Safety, Rev. 5, 03/2007 See Notes d and e.
7.6 Interlock Systems Important to Safety, Rev. 5, 03/2007 See Notes d and e.
7.7 Control Systems, Rev. 5, 03/2007 See Notes d and e.
7.8 Diverse Instrumentation and Control Systems, Rev. 5, 03/2007 See Notes d and e.
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.
TABLE 1.9-202 (Sheet 11 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-36 8.4 Station Blackout, Initial Issuance, 03/2007 See Note g.
9.1.1 Criticality Safety of Fresh and Spent Fuel Storage and Handling See Notes d and e.
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, Rev. 2, 03/2007 See Notes d and e.
9.1.4 Light Load Handling System (Related to Refueling)
Acceptable See Notes d, e, and f.
9.1.5 Overhead Heavy Load Handling Systems, Rev. 1, 03/2007 Acceptable See Notes d, e, and f.
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, Rev. 4, 03/2007 See Notes d and e.
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)
(Including Boron Recovery System)
See Notes d and e.
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.
TABLE 1.9-202 (Sheet 12 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-37 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 Transfer System Acceptable See Notes d, e, and f.
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 and Exhaust System See Notes d and e.
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.
TABLE 1.9-202 (Sheet 13 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-38 10.4.6 Condensate Cleanup System See Notes d and e.
10.4.7 Condensate and Feedwater System, Rev. 4, 03/2007 Acceptable See Notes d, e, and f.
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 Instrumentation and Sampling Systems, Rev. 4, 03/2007 Acceptable See Notes d, e, and f.
TABLE 1.9-202 (Sheet 14 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-39 12.1 Assuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable Exception See Notes d, e, and f.
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.
TABLE 1.9-202 (Sheet 15 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-40 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.
TABLE 1.9-202 (Sheet 16 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-41 13.1.1 Management and Technical Support Organization, Rev. 5, 03/2007 Exception See Notes d, e, and f.
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.
TABLE 1.9-202 (Sheet 17 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-42 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.
TABLE 1.9-202 (Sheet 18 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-43 13.2.1 Reactor Operator Requalification Program; Reactor Operator Training Exception See Notes d, e, and f. SRP 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.
TABLE 1.9-202 (Sheet 19 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-44 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 Issuance, 03/2007 Exception The procedure development schedule is addressed in the COL application (not in the SAR as requested by this SRP).
13.5.2.1 Operating and Emergency Operating Procedures, Rev. 2, 03/2007 Exception See Notes d, e, and f.
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 Responsibilities, Initial Issuance, 03/2007 Acceptable See Security Plan developed in accordance with NEI 03-12 13.6.2 Physical Security - Design Certification, Initial Issuance, 03/2007 See notes d and e.
TABLE 1.9-202 (Sheet 20 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-45 13.6.3 Physical Security - Early Site Permit, Initial Issuance, 03/2007 N/A 14.2 Initial Plant Test Program - Design Certification and New License Applicants Exception See Notes d, e, and f. The level of detail is consistent with DCD section content addressing nonsafety-related systems.
14.2.1 Generic Guidelines for Extended Power Uprate Testing Programs, Initial Issuance, 08/2006 N/A No power uprate is sought.
14.3 Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 Acceptable 14.3.1
[Reserved]
14.3.2 Structural and Systems Engineering -
Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.3 Piping Systems and Components - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.4 Reactor Systems - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.5 Instrumentation and Controls - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
TABLE 1.9-202 (Sheet 21 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-46 14.3.6 Electrical Systems - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.7 Plant Systems - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 Acceptable See Notes d, e, and f.
14.3.8 Radiation Protection - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.9 Human Factors Engineering - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.10 Emergency Planning - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 Acceptable See Notes d, e, and f.
14.3.11 Containment Systems - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 See Notes d and e.
14.3.12 Physical Security Hardware - Inspections, Tests, Analyses, and Acceptance Criteria, Initial Issuance, 03/2007 Acceptable See Notes d, e, and f.
15 Introduction - Transient and Accident Analysis See Notes d and e.
15.0.1 Radiological Consequence Analyses Using Alternative Source Terms, Rev. 0, 07/2000 See Notes d and e.
TABLE 1.9-202 (Sheet 22 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-47 15.0.2 Review of Transient and Accident Analysis Method, Rev. 0, 12/2005 See Notes d and e.
15.0.3 Design Basis Accident Radiological Consequences of Analyses for Advanced Light Water Reactors, Initial Issuance, 03/2007 See Notes d and e.
15.1.1 - 15.1.4 Decrease in Feedwater Temperature, Increase in Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve, Rev. 2, 03/2007 See Notes d and e.
15.1.5 Steam System Piping Failures Inside and Outside of Containment (PWR)
See Notes d and e.
15.2.1 - 15.2.5 Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed), Rev. 2, 03/2007 See Notes d and e.
15.2.6 Loss of Nonemergency AC Power to the Station Auxiliaries, Rev. 2, 03/2007 See Notes d and e.
15.2.7 Loss of Normal Feedwater Flow See Notes d and e.
15.2.8 Feedwater System Pipe Breaks Inside and Outside Containment (PWR), Rev. 2, 03/2007 See Notes d and e.
15.3.1 - 15.3.2 Loss of Forced Reactor Coolant Flow Including Trip of Pump Motor and Flow Controller Malfunctions, Rev. 2, 03/2007 See Notes d and e.
15.3.3 - 15.3.4 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break See Notes d and e.
TABLE 1.9-202 (Sheet 23 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-48 15.4.1 Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition See Notes d and e.
15.4.2 Uncontrolled Control Rod Assembly Withdrawal at Power See Notes d and e.
15.4.3 Control Rod Misoperation (System Malfunction or Operator Error)
See Notes d and e.
15.4.4 - 15.4.5 Startup of an Inactive Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate, Rev. 2, 03/2007 See Notes d and e.
15.4.6 Inadvertent Decrease in Boron Concentration in the Reactor Coolant System (PWR), Rev. 2, 03/2007 See Notes d and e.
15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position, Rev. 2, 03/2007 See Notes d and e.
15.4.8 Spectrum of Rod Ejection Accidents (PWR)
See Notes d and e.
15.4.8.A Radiological Consequences of a Control Rod Ejection Accident (PWR), Rev. 1, 07/1981 See Notes d and e.
15.4.9 Spectrum of Rod Drop Accidents (BWR)
N/A 15.5.1 - 15.5.2 Inadvertent Operation of ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory, Rev. 2, 03/2007 See Notes d and e.
TABLE 1.9-202 (Sheet 24 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-49 15.6.1 Inadvertent Opening of a PWR Pressurizer Pressure Relief Valve or a BWR Pressure Relief Valve, Rev. 2, 03/2007 See Notes d and e.
15.6.5 Loss-of-Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary See Notes d and e.
15.8 Anticipated Transients Without Scram, Rev. 2, 03/2007 See Notes d and e.
15.9 Boiling Water Reactor Stability, Initial Issuance, 03/2007 N/A 16 Technical Specifications Acceptable See Notes d, e, and f.
16.1 Risk-informed Decision Making: Technical Specifications, Rev. 1, 03/2007 N/A This SRP applies to the Technical Specifications change process.
17.1 Quality Assurance During the Design and Construction Phases, Rev. 2, 07/1981 Acceptable See Notes d, e, and f.
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, Rev. 2, 07/1981 See Notes d and e.
TABLE 1.9-202 (Sheet 25 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1 BLN SUP 1.9-5
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-50 17.3 Quality Assurance Program Description, Rev. 0, 08/1990 See Notes d and e.
17.4 Reliability Assurance Program (RAP), Initial Issuance, 03/2007 See Notes d and e.
17.5 Quality Assurance Program Description - Design Certification, Early Site Permit and New License Applicants, Initial Issuance, 03/2007 Acceptable See Notes d, e, and f. This section covers the 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 Accident Evaluation for New Reactors, Rev. 2, 06/2007 Acceptable See Notes d, e, and f.
19.1 Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities, Rev. 2, 06/2007 Acceptable See Notes d, e, and f.
TABLE 1.9-202 (Sheet 26 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-51 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.
19.2 Review of Risk Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, Initial Issuance, 06/2007 See Note g.
TABLE 1.9-202 (Sheet 27 of 27)(a)
CONFORMANCE WITH SRP ACCEPTANCE CRITERIA Criteria Section (b)
Reference Criteria FSAR Position (c)
Comments/Summary of Exceptions STD SUP 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-52 TABLE 1.9-203 (Sheet 1 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes 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 Qualifications, Training f
Resolved per NUREG-0933 I.A.2.1(3)
Facility Certification of Competence and Fitness of Applicants for Operator and Senior Operator Licenses f
Resolved per NUREG-0933 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 and DOE d
Not applicable 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 Simulator d
Not applicable to new plants I.A.4.4 Feasibility Study of NRC Engineering Computer d
Not applicable to new plants STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-53 I.B.1.3(1)
Require Licensees to Place Plant in Safest Shutdown Cooling Following a Loss of Safety Function Due to Personnel Error d
Not applicable to new plants I.B.1.3(2)
Use Existing Enforcement Options to Accomplish Safest Shutdown Cooling d
Not applicable to new plants I.B.1.3(3)
Use Non-Fiscal Approaches to Accomplish Safest Shutdown Cooling d
Not applicable to new plants I.B.2.1(1)
Verify the Adequacy of Management and Procedural Controls and Staff Discipline d
Not applicable to new plants I.B.2.1(2)
Verify that Systems Required to Be Operable Are Properly Aligned d
Not applicable to new plants I.B.2.1(3)
Follow-up on Completed Maintenance Work Orders to Ensure Proper Testing and Return to Service d
Not applicable to new plants I.B.2.1(4)
Observe Surveillance Tests to Determine Whether Test Instruments Are Properly Calibrated d
Not applicable to new plants I.B.2.1(5)
Verify that Licensees Are Complying with Technical Specifications d
Not applicable 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 Racks for Unauthorized Jumpers and Bypasses d
Not applicable 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 of Operating Activities f
Resolved per NUREG-0933 TABLE 1.9-203 (Sheet 2 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-54 I.C.7 NSSS Vendor Review of Procedures f
Resolved per NUREG-0933 I.C.8 Pilot Monitoring of Selected Emergency Procedures for Near-Term Operating License Applicants f
Resolved per 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 Data d
Not applicable 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 Programs d
Not applicable 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 Organization f
Resolved per 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 Containment Structures d
Not applicable to new plants TABLE 1.9-203 (Sheet 3 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-55 II.B.6 Risk Reduction for Operating Reactors at Sites with High Population Densities f
Resolved per NUREG-0933 II.E.1.3 Update Standard Review Plan and Develop Regulatory Guide d
Resolved per NUREG-0933 II.E.6.1 Test Adequacy Study d
Resolved per NUREG-0933 II.F.5 Classification of Instrumentation, Control, and Electrical Equipment d
Not applicable to new plants II.H.4 Determine Impact of TMI on Socioeconomic and Real Property Values d
Not applicable to new plants II.J.1.1 Establish a Priority System for Conducting Vendor Inspections d
Not applicable 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-Licensees d
Not applicable to new plants II.J.1.4 Assign Resident Inspectors to Reactor Vendors and Architect-Engineers d
Not applicable 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 in Construction Inspection Program d
Not applicable 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 Construction f
Not applicable 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 TMI-2 Accident f
Resolved per NUREG-0933 II.K.1(3)
Review Operating Procedures for Recognizing, Preventing, and Mitigating Void Formation in Transients and Accidents f
Resolved per NUREG-0933 II.K.1(4)
Review Operating Procedures and Training Instructions f
Resolved per 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 Procedures f
Resolved per NUREG-0933 TABLE 1.9-203 (Sheet 4 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-56 II.K.1(9)
Review Procedures to Assure That Radioactive Liquids and Gases Are Not Transferred out of Containment Inadvertently f
Resolved per NUREG-0933 II.K.1(10)
Review and Modify Procedures for Removing Safety-Related Systems from Service f
Resolved per NUREG-0933 II.K.1(11)
Make All Operating and Maintenance Personnel Aware of the Seriousness and Consequences of the Erroneous Actions Leading up to, and in Early Phases of, the TMI-2 Accident f
Resolved per NUREG-0933 II.K.1(12)
One Hour Notification Requirement and Continuous Communications Channels f
Resolved per NUREG-0933 II.K.1(13)
Propose Technical Specification Changes Reflecting Implementation of All Bulletin Items f
Resolved per NUREG-0933 II.K.1(14)
Review Operating Modes and Procedures to Deal with Significant Amounts of Hydrogen f
Resolved per NUREG-0933 II.K.1(15)
For Facilities with Non-Automatic AFW Initiation, Provide Dedicated Operator in Continuous Communication with CR to Operate AFW f
Resolved per NUREG-0933 II.K.1(16)
Implement Procedures That Identify PZR PORV "Open" Indications and That Direct Operator to Close Manually at "Reset" Setpoint f
Resolved per NUREG-0933 II.K.1(17)
Trip PZR Level Bistable so That PZR Low Pressure Will Initiate Safety Injection f
Resolved per NUREG-0933 II.K.1(26)
Revise Emergency Procedures and Train ROs and SROs f
Resolved per NUREG-0933 II.K.3(3)
Report Safety and Relief Valve Failures Promptly and Challenges Annually f
Resolved per 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 Licensees to Confine Range of Use to High Power Levels f
Resolved per NUREG-0933 II.K.3(11)
Control Use of PORV Supplied by Control Components, Inc. Until Further Review Complete f
Resolved per NUREG-0933 II.K.3(12)
Confirm Existence of Anticipatory Trip Upon Turbine Trip f
Resolved per NUREG-0933 II.K.3(30)
Revised Small-Break LOCA Methods to Show Compliance with 10 CFR 50, Appendix K f
Resolved per NUREG-0933 II.K.3(31)
Plant-Specific Calculations to Show Compliance with 10 CFR 50.46 f
Resolved per NUREG-0933 III.A.1.1(1) Implement Action Plan Requirements for Promptly Improving Licensee Emergency Preparedness f
Resolved per NUREG-0933 TABLE 1.9-203 (Sheet 5 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-57 III.A.1.1(2) Perform an Integrated Assessment of the Implementation f
Not applicable 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 Adoption of Rules d
Not applicable to new plants III.A.2.1(4) Revise Inspection Program to Cover Upgraded Requirements d
Resolved per 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 Briefing Requests d
Not applicable 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-Purifying Respirators d
Not applicable to new plants III.D.3.3 In-Plant Radiation Monitoring COL Item 12.3-2 12.3.4, Appendix 12AA III.D.3.5(1) Develop Format for Data To Be Collected by Utilities Regarding Total Radiation Exposure to Workers d
Not applicable to new plants TABLE 1.9-203 (Sheet 6 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-58 III.D.3.5(2) Investigate Methods of Obtaining Employee Health Data by Nonlegislative Means d
Not applicable 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 Information to Licensees d
Not applicable to new plants IV.D.1 NRC Staff Training d
Not applicable to new plants IV.E.1 Expand Research on Quantification of Safety Decision-Making d
Not applicable 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 Rules d
Not applicable to new plants IV.G.3 Improve Rulemaking Procedures d
Not applicable to new plants IV.G.4 Study Alternatives for Improved Rulemaking Process d
Not applicable 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 of Nonsafety Responsibilities d
Not applicable to new plants V.C.1 Strengthen the Role of Advisory Committee on Reactor Safeguards d
Not applicable 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 Nuclear Safety Board d
Not applicable to new plants TABLE 1.9-203 (Sheet 7 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-59 V.D.1 Improve Public and Intervenor Participation in the Hearing Process d
Not applicable 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 Offices d
Not applicable 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 Chairman, Commission, and Executive Director for Operations d
Not applicable to new plants V.F.5 Authority to Delegate Emergency Response Functions to a Single Commissioner d
Not applicable 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 (former USI)
COL Item 5.4-1 5.4.2.5 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 Item 6.2-1 6.2.5.1 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 TABLE 1.9-203 (Sheet 8 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-60 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 of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light Water Cooled Power Reactors d
Not applicable to new plants 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 Plants d
Not applicable to new plants B-49 Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments d
Not applicable 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 and Coal Fuel Cycles d
Not applicable to new plants C-4 Statistical Methods for ECCS Analysis d
Not applicable to new plants TABLE 1.9-203 (Sheet 9 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-61 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 Shutdown when Equipment for Safe Shutdown is Degraded or Inoperable d
Not applicable to new plants 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 Ferritic Steels in Selected Environments d
Not applicable to new plants 112.
Westinghouse RPS Surveillance Frequencies and Out-of-Service Times d
Not applicable to new plants 118.
Tendon Anchorage Failure f
Resolved per NUREG-0933.
119.1 Piping Rupture Requirements and Decoupling of Seismic and LOCA Loads d
Not applicable 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 Sites f
See DCD Subsection 1.9.4, item 130 133.
Update Policy Statement on Nuclear Plant Staff Working Hours d
Not applicable to new plants TABLE 1.9-203 (Sheet 10 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-62 136.
Storage and Use of Large Quantities of Cryogenic Combustibles On Site d
Not applicable 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 Panel Interactions d
Not applicable to new plants 148.
Smoke Control and Manual Fire-Fighting Effectiveness d
Not applicable to new plants 155.2 Establish Licensing Requirements For Non-Operating Facilities d
Not applicable 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 Specifications d
Not applicable to new plants 184 Endangered Species d
Not applicable to new plants 185 Control of Recriticality following Small-Break LOCA in PWRs h
Not applicable to new plants 186 Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants Continue 1.9.4.2.3 9.1.5.3 TABLE 1.9-203 (Sheet 11 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-63 189 Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident Description Continue Not applicable to the AP1000.
191 Assessment Of Debris Accumulation On PWR Sump Performance h (High)
See DCD Subsections 6.3.2.2.7 and 1.9.4.2.3, item 191 199 Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States Issue to be Prioritized by NRC in the Future 2.5 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 Evaluation d
Not applicable 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 TABLE 1.9-203 (Sheet 12 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-64 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 TABLE 1.9-203 (Sheet 13 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-65 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.
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 TABLE 1.9-203 (Sheet 14 of 14)
LISTING OF UNRESOLVED SAFETY ISSUES AND GENERIC SAFETY ISSUES Action Plan Item/Issue No.
Title Applicable Screening Criteria Notes STD COL 1.9-3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-66 TABLE 1.9-204 (Sheet 1 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment BULLETIN 80-06 Engineered Safety Feature (ESF) Reset Controls (3/80)
See Note a.
80-10 Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment (5/80)
Appendix 12AA 80-15 Possible Loss of Emergency Notification System (ENS) with Loss of Offsite Power (6/80) 9.5.2.2.3.1 9.5.2.5.1 02-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity 5.2.4 See Note a.
02-02 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs 5.2.4 See Note a.
03-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors 6.3 See Note a.
03-02 Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity 5.2.4.3 See Note a.
03-03 Potentially Defective 1-inch Valves for Uranium Hexafluoride Cylinders N/A 03-04 Rebaselining of Data in the Nuclear Materials Management and Safeguards System N/A One time report.
04-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors See Note a.
STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-67 05-01 Material Control and Accounting at Reactors and Wet Spent Fuel Storage Facilities 13.6 05-02 Emergency Preparedness and Response Actions for Security-Based Events 13.3 88-11 Pressurizer Surge Line Thermal Stratification 3.9.3.1.2 GENERIC LETTERS 80-22 Transmittal of NUREG-0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans (3/80) 13.3 80-26 Qualifications of Reactor Operators (3/80) 13.2 18.10 80-51 On-Site Storage Of Low-Level Waste (6/90) 11.4.6 80-55 Possible Loss of Hotline With Loss Of Off-Site Power See Bulletin 80-15 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 Snubber Surveillance (11/80)
Snubbers no longer in generic Tech Specs See Note a.80-108 Emergency Planning (12/80) 13.3 81-02 Analysis, Conclusions and Recommendations Concerning Operator Licensing (1/81) 13.2 81-10 Post-TMI Requirements for the Emergency Operations Facility (2/81) 13.3 TABLE 1.9-204 (Sheet 2 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-68 81-38 Storage of Low-Level Radioactive Waste at Power Reactor Sites (11/81) 11.4.6 81-40 Qualifications of Reactor Operators (12/81) 13.1 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 Hours (6/82) 13.1.2.1.2.4 - 13.1.2.1.2.8 13.1.2.1.3 13.1.2.1.4 82-13 Reactor Operator and Senior Reactor Operator Examinations (6/82)
For information only.
82-18 Reactor Operator and Senior Reactor Operator Requalification Examinations (10/82) 13.2 83-06 Certificates and Revised Format For Reactor Operator and Senior Reactor Operator Licenses (1/83) 13.2 83-11 Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions (2/83) 13.1 See Note a.
83-12 Issuance of NRC FORM 398 - Personal Qualifications Statement - Licensee (2/83) 13.2 83-17 Integrity of the Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses (4/83) 13.1 83-22 Safety Evaluation of "Emergency Response Guidelines" (6/83) 18.9 83-40 Operator Licensing Examination (12/83) 13.2 TABLE 1.9-204 (Sheet 3 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-69 84-10 Administration of Operating Tests Prior to Initial Criticality (10 CFR 55.25) (4/84) 13.2 84-14 Replacement and Requalification Training Program (5/84) 13.2 84-17 Annual Meeting to Discuss Recent Developments Regarding Operator Training, Qualifications, and Examinations (7/84)
Administrative 84-20 Scheduling Guidance for Licensee Submittals of Reloads That Involve Unreviewed Safety Questions (8/84) 13.5 85-04 Operating Licensing Examinations (1/85)
Administrative 85-05 Inadvertent Boron Dilution Events (1/85) 13.5 85-14 Commercial Storage At Power Reactor Sites Of Low Level Radioactive Waste Not Generated By The Utility (8/85)
Administrative 85-18 Operator Licensing Examinations (9/85) Administrative 85-19 Reporting Requirements On Primary Coolant Iodine Spikes (9/85) 16.1 86-14 Operator Licensing Examinations (8/86) Administrative 87-14 Operator Licensing Examinations (8/87) Administrative 88-05 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants (3/88) 5.2.4 See Note a.
88-14 Instrument Air Supply System Problems Affecting Safety-Related Equipment (8/88) 9.3.7 88-18 Plant Record Storage on Optical Disk (10/88) 17 TABLE 1.9-204 (Sheet 4 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-70 89-07 Power Reactors Safeguards Contingency Planning for Surface Vehicle Bombs (4/89) 13.6 89-07 S1 Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs 13.6 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning (5/89) 10.1.3.1 89-12 Operator Licensing Examination (7/89) 13.2 89-15 Emergency Response Data System (8/89) 9.5.2 13.3 89-17 Planned Administrative Changes to the NRC Operator Licensing Written Examination Process (9/89)
N/A 91-14 Emergency Telecommunications (9/91) 9.5.2 13.3 91-16 Licensed Operators and Other Nuclear Facility Personnel Fitness for Duty (10/91) 13.7 92-01 Reactor Vessel Structural Integrity (1/92) 5.3.2.6.3 93-01 Emergency Response Data System Test Program 13.3 93-03 Verification of Plant Records 17 96-02 Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat (2/96) 13.6 03-01 Control Room Habitability 6.4 See Note a.
TABLE 1.9-204 (Sheet 5 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.9-71 (a) The design aspects of this topic are as stated in the AP1000 DCD.
04-01 Requirements for Steam Generator Tube Inspections 5.4.2.5 16.1 See Note a.
04-02 Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors 6.3.8.1 See Note a.
06-01 Steam Generator Tube Integrity and Associated Technical Specifications 5.4.2.5 16.1 See Note a.
06-02 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power 8.2.1.1 8.2.2 See Note a.
06-03 Potentially Nonconforming Hemyc and MT Fire Barrier Configurations 9.5.1.8 See Note a.
07-01 Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients.
17.6 See Note a.
TABLE 1.9-204 (Sheet 6 of 6)
GENERIC COMMUNICATIONS ASSESSMENT Number Title Comment STD COL 1.9-2
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-1 Add the following section after DCD Section 1.9.
1.10 NUCLEAR POWER PLANTS TO BE OPERATED ON MULTI-UNIT SITES 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 The power blocks for Units 3 and 4 have a minimum separation of at least 800 feet between plant centerlines.
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.
STD SUP 1.10-1 BLN SUP 1.10-1 STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-2 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.
New unit SSCs important to safety are described in FSAR Chapter 3.
As indicated in Chapter 16, the LCOs for Units 3 and 4 are located in Part 4 of the COL Application.
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 BLN SUP 1.10-1 STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-3 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.
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-4 TABLE 1.10-201 (Sheet 1 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT Site Exploration, Grading, Clearing, Installation of Drainage and Erosion Control Measures Overhead Power Lines Transmission Towers 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 STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-5 Boring, Drilling, Pile Driving, Dredging, Demolition, Excavation Underground Conduits, Piping, Tunnels, Etc 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 Delivery, Vehicle Traffic Overhead Power Lines Transmission Towers Underground Conduits, Piping, Tunnels Crane Load Drops Crane or Crane Boom Failures Vehicle Accidents Rail Car Derailments Equipment and Material Laydown, Storage, Warehousing Releases of Stored Flammable, Hazardous or Toxic Materials Wind-Generated, Construction-Related Debris and Missiles TABLE 1.10-201 (Sheet 2 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-6 General Construction, Erection, Fabrication Physical Integrity of Structures, 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 TABLE 1.10-201 (Sheet 3 of 3)
POTENTIAL HAZARDS FROM CONSTRUCTION ACTIVITIES CONSTRUCTION ACTIVITY HAZARD POTENTIAL IMPACT STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-7 TABLE 1.10-202 (Sheet 1 of 2)
HAZARDS DURING CONSTRUCTION ACTIVITIES CONSTRUCTION HAZARD IMPACTED SSCs Impact on Overhead Power Lines Offsite Power System Impact on Transmission Towers Offsite Power Systems Impact on Utilities, Underground Conduits, Piping, Tunnels, Tanks Fire Protection System Service Water System1 Impact of Construction-Generated Dust and Equipment Exhausts Control Room Emergency HVAC Systems1 Diesel Generators Impact of Vibratory Ground Motion Offsite Power System Onsite Power Systems Instrumentation and Seismic Monitors Impact of Crane or Crane Boom Failures Safety-Related Structures Impact of Releases of Flammable, Hazardous or Toxic Materials Control Room Emergency HVAC Systems1 Impact of Wind-Generated, Construction-Related Debris and Missiles Safety-Related Structures Control Room Emergency HVAC Systems1 Impact on Electrical Systems and Components Offsite Power System Onsite Power Systems Impact on Cooling Water Systems and Components Service Water System1 Ultimate Heat Sink1 STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-8 1 Not applicable to AP1000 operating units Impact on Radioactive Waste Release Points and Parameters Gaseous and Liquid Radioactive Waste Management Systems Impact of Relocation of Structures, Systems or Components Fire Protection System Service Water System1 Impact of Site Groundwater Depression and Dewatering Safety-Related Structures and Foundations Impact of Equipment Delivery and Heavy Equipment Delivery Safety-Related Structures and Foundations TABLE 1.10-202 (Sheet 2 of 2)
HAZARDS DURING CONSTRUCTION ACTIVITIES CONSTRUCTION HAZARD IMPACTED SSCs STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-9 TABLE 1.10-203 (Sheet 1 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL Impact on Transmission Power Lines and Offsite Power Lines Safe standoff clearance distances are 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, Underground Conduits, Piping, Tunnels, Tanks Grading, excavation, and pile driving require location and identification of equipment or underground structures that must be relocated, removed, or left in place and protected prior to the work activity.
Impact of Construction-Generated Dust and Equipment Exhausts Fugitive dust and dust generation is controlled. Potentially affected system air intakes and filters are periodically monitored.
Impact of Vibratory Ground Motion Construction administrative procedures, methods, and controls are implemented to prevent exceeding ground vibration and instrumentation limit settings.
Impact of Crane or Crane Boom Failures Construction standoff distance 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.
STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-10 Impact of Releases of Flammable, Hazardous or Toxic Materials and Missile Generation Environmental, safety and health controls limit transport, storage, quantities, type and use of 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, Construction-Related Debris and Missiles Administrative controls address equipment, material storage and 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 and Components Affected operating unit electrical systems and components within the construction area are identified and isolated or relocated or otherwise protected.
Impact on Cooling Water Systems and Components Transport of heavy load equipment over buried cooling water piping is prohibited without evaluation.
Impact on Radioactive Waste Release Points and Parameters Engineering evaluation and managerial controls are implemented, as necessary, to prevent radioactive releases beyond the established limits due to construction activity.
Impact of Relocation of Structures, Systems or Components Administrative controls identify SSCs that require relocation. Temporary or permanent design changes are implemented if necessary.
TABLE 1.10-203 (Sheet 2 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1.10-11 Impact of Equipment Delivery and Heavy Equipment Delivery Rail transport speed limits and maximum rail loading weights onsite are established.
General equipment and heavy equipment movement controls and limitations are established.
TABLE 1.10-203 (Sheet 3 of 3)
MANAGERIAL AND ADMINISTRATIVE CONSTRUCTION CONTROLS CONSTRUCTION HAZARDS TO SSCs MANAGERIAL CONTROL STD SUP 1.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1A-1 APPENDIX 1A CONFORMANCE WITH REGULATORY GUIDES This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
Appendix 1AA is provided to supplement the information in DCD Appendix 1A.
STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1B-1 APPENDIX 1B 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."
STD SUP 1B-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-1 APPENDIX 1AA CONFORMANCE WITH REGULATORY GUIDES Criteria Section Referenced Criteria FSAR Position Clarification/
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 ANSI/ANS-3.1-1993 Exception Not able to meet Regulatory Guide 1.8, Rev. 3 qualification requirements for 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.
STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-2 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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-3 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-4 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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-5 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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-6 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 Appendix B Appendix C Conforms 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-7 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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-8 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-9 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 18.1-1999 Conforms 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-10 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.
450-2002 Exception Approved Generic Technical 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-11 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-12 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-13 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-14 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-15 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-16 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-17 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, Section C.3 Exception 3.4 Exception is taken to requirement 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 84th as they are very close approximations (+/- 1 sigma).
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-18 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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-19 DIVISION 8 - Occupational Health Regulatory Guide 8.2, Rev. 0, 2/73 - Guide for Administrative Practices in Radiation Monitoring General 10 CFR Part 20; ANSI 13.2-1969 Exception The reference to 10 CFR 20.401 is no longer valid in the current version of 10 CFR Part 20.
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 Part 20 ANSI N13.5-1972 Exception The reference to 10 CFR 20.202 (a) and 20.401 is no longer valid in the current version of 10 CFR Part 20.
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.
Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-20 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-88.2, Regulatory Guide 8.15, NUREG-0041 Conforms Conformance is with the latest revision of 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-21 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 N13.27-1981 Conforms 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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 1AA-22 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.
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 Criteria Section Referenced Criteria FSAR Position Clarification/
Summary Description of Exceptions STD COL 1.9-1