NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), List of Effective Pages
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List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 1 of 10POINT BEACH NUCLEAR PLANT UNITS 1 & 2FINAL SAFETY ANALYSIS REPORTLIST OF EFFECTIVE PAGESThe following is a List of Effective Pages for the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). This List of Effective Pages should be filed at the front of the FSAR manual. All holders of this FSAR should check their manuals against this List of Effective Pages to ensure that the FSAR is accurate and complete.Some figures are identified as for information only because they are updated on a periodic frequency commensurate with the docketed submittal of this FSAR.The last update submitted to the NRC is identified on the lower-left hand side of each page, followed by the update year, (e.g., UFSAR 2007).
List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 2 of 10 LIST OF EFFECTIVE PAGESList of Effective PagesDescription of ChangesGeneral Table of Contents(Note Repeated in each Chapter)List of TablesList of FiguresChapter 1First PageLast PageUpdateLOEP - 1LOEP - 10201 5First PageLast PageUpdateDOC - 1DOC -
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List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 3 of 10Chapter 2Chapter 31.3-11.3-3020121.4-11.4-120141.5-11.5-22010First PageLast PageUpdateTOC iTOC i201 52.0-12.0-119972.1-12.1-120142.2-12.2-62012 2.3-12.3-320142.4-12.4-420142.5-12.5-15201 52.6-12.6-2520142.7-12.7-620092.8-12.8-62014 2.9-12.9-320142.10-12.10-220132.11-12.11-22014First PageLast PageUpdateTOC iTOC ii201 53.1-13.1-10201 53.2-13.2-102201 53.3-13.3-3201 53.4-13.4-152008First PageLast PageUpdate List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 4 of 10Chapter 4Chapter 5Chapter 6First PageLast PageUpdateTOC iTOC i19994.1-14.1-2420134.2-14.2-3 5 201 54.3-14.3-820104.4-14.4-112007First PageLast PageUpdateTOC iTOC iii201 55.1-15.1-1 09 201 55.2-15.2-104201 55.3-15.3-10201 55.4-15.4-119975.5-15.5-12010 5.6-15.6-2920105.7-15.7-52010First PageLast PageUpdateTOC iTOC i20126.0-16.0-120006.1-16.1-62014 6.2-16.2-49201 56.3-16.3-1820146.4-16.4-25201 56.5-16.5-10201 5
List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 5 of 10Chapter 7Chapter 8Chapter 9First PageLast PageUpdateTOC iTOC iv20107.1-17.1-1020107.2-17.2-442014 7.3-17.3-2220127.4-17.4-820147.5-17.5-152014 7.6-17.6-2520107.7-17.7-182012First PageLast PageUpdateTOC iTOC ii20108.0-18.0-16201 58.1-18.1-5201 58.2-18.2-420148.3-18.3-220148.4-18.4-42014 8.5-18.5-4201 58.6-18.6-620148.7-18.7-52014 8.8-18.8-11201 58.9-18.9-32013First PageLast PageUpdateTOC iTOC ii201 59.0-19.0-32010 List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 6 of 10Chapter 10Chapter 119.1-19.1-1220149.2-19.2-720149.3-19.3-34201 59.4-19.4-14201 59.5-19.5-320109.6-19.6-15201 59.7-19.7-520139.8-19.8-1120149.9-19.9-12201 59.10-19.10-520149.11-19.11-102014First PageLast PageUpdateTOC iTOC i201010.0-110.0-12010 10.1-110.1-50201 510.2-110.2-14201 5First PageLast PageUpdateTOC iTOC ii201311.0-111.0-3201311.1-111.1-20201 511.2-111.2-30201 511.3-111.3-2201311.4-111.4-222014 11.5-111.5-272013First PageLast PageUpdate List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 7 of 10Chapter 12Chapter 13Chapter 1411.6-111.6-20201011.7-111.7-2200811.8-111.8-22013First PageLast PageUpdateTOC iTOC i200512.1-112.1-1200712.2-112.2-3201312.3-112.3-12013 12.4-112.4-5201412.5-112.5-1201412.6-112.6-22000 12.7-112.7-12007First PageLast PageUpdateTOC iTOC i200813.0-113.0-1200813.1-113.1-1200813.2-113.2-192008 13.3-113.3-4200813.4-113.4-32008First PageLast PageUpdateTOC iTOC ii201214.0-114.0-162010First PageLast PageUpdate List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 8 of 1014.1.1-114.1.1-8201014.1.2-114.1.2-15201 514.1.3-114.1.3-42010 14.1.4-114.1.4-5201414.1.5-114.1.5-6201014.1.6-114.1.6-22010 14.1.7-114.1.7-19201 514.1.8-114.1.8-2 4 201 514.1.9-114.1.9-142014 14.1.10-114.1.10-16201014.1.11-114.1.11-16201 514.1.12-114.1.12-42012 14.2.1-114.2.1-8201014.2.2-114.2.2-1200714.2.3-114.2.3-12007 14.2.4-114.2.4-9201 514.2.5-114.2.5-30201414.2.6-114.2.6-162010 14.2.7-114.2.7-1201214.3.1-114.3.1-79201 514.3.2-114.3.2-52201 514.3.3-114.3.3-9201014.3.4-114.3.4-8 7 201 514.3.5-114.3.5-172010 14.3.6-114.3.6-72010First PageLast PageUpdate List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 9 of 10Chapter 15Appendix AAppendix BFirst PageLast PageUpdateTOC iTOC ii201 515.0-115.0-1200815.2-115.2-8201 515.3-115.3-1200615.4-115.4-22201415.5-115.5-12006First PageLast PageUpdateTOC - A-iTOC - A-ii201 5A.1-1A.1-112013 A.2-1A.2-312013A.3-1A.3-112012A.4-1A.4-12006 A.5-1A.5-382014A.6-1A.6-82014A.7-1A.7-1 2 201 5First PageLast PageUpdateTOC - B-iTOC - B-i2006B.2-1B.2-152002 B.3-1B.3-51998 List of Effective PagesFSAR LOEPUFSAR 2015Page LOEP - 10 of 10Appendix CAppendix DAppendix IAppendix TFirst PageLast PageUpdateTOC - C-iTOC - C-i2007C-1C-42010First PageLast PageUpdateTOC - D-iTOC - D-i2008D-1D-52013First PageLast PageUpdateTOC - I-iTOC - I-ii2010I.1-1I.1-32010I.2-1I.2-82009 I.3-1I.3-12010I.4-1I.4-92009I.5-1I.5-32009 I.6-1I.6-21997I.7-1I.7-21997I.8-1I.8-52008 I.9-1I.9-32010 Appendix I Tables and Figures-1 Appendix I Tables and Figures-248 2010First PageLast PageUpdateT.1-1T.1-12008 Description of ChangesFSAR DOCUFSAR 2015Page DOC - 1 of 8 DESCRIPTION OF CHANGESTable of ContentsThroughoutEditorial Changes: Editorial changes were made to correct grammar, punctuation, spelling, and to ensure consistency between text headings, table titles, figure titles, table of contents, etc. These changes may not be identified by a revision bar.Chapter 1FSAR 1.2-2Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 1.2-5Editorial Change: Added new NRC SE regarding the use of optimized ZIRLO TM as reference 5. (LIC 2064578)Chapter 2FSAR 2.5-6Licensing Basis Change: Updated the rip-rap slopes used in Calculation NEE-094-CALC-001. (LIC 2022012)FSAR 2.5-15Licensing Basis Change: Updated Figure 2.5-1 with controlled drawingB-18. (LIC 2021090)Chapter 3FSAR 3.1-1Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.1-3Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-1Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-8Licensing Basis Change: Updated for Unit 1 Cycle 37 reload design implementation of PARAGON Code. (LIC 2092524)FSAR 3.2-9Licensing Basis Change: Updated for Unit 1 Cycle 37 reload design implementation of PARAGON Code. (LIC 2092524)FSAR 3.2-10Licensing Basis Change: Updated for Unit 1 Cycle 37 reload design implementation of PARAGON Code. (LIC 2092524)FSAR 3.2-17Licensing Basis Change: Revised to remove Peripheral Power Suppression Assemblies. (LIC 2064578)FSAR 3.2-17Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-26Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-29Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-36Editorial Change: Corrected date in reference 17. (LIC 2064578)FSAR 3.2-36Editorial Change: Corrected date in reference 21. (LIC 2064578)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 2 of 8 Chapter 3continuedFSAR 3.2-37Editorial Change: Corrected title in reference 45. (LIC 2064578)FSAR 3.2-38Editorial Change: Added reference 55 to Reference Section. (LIC 2092524)FSAR 3.2-39Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-47Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.2-97Licensing Basis Change: Revised figure for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 3.3-1Licensing Basis Change: Revised figure for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO and removed Peripheral Power Suppression Assemblies. (LIC 2064578)FSAR 3.3-2Licensing Basis Change: Revised to remove Peripheral Power Suppression Assemblies. (LIC 2064578)Chapter 4FSAR 4.2-7Licensing Basis Change: Replacement of the #1 seal insert on the RCP with a new Westinghouse shutdown seal via EC 277545. (LIC 1999915)FSAR 4.2-23Updated Figure to reflect approved drawing of record.FSAR 4.2-27Updated Figure to reflect approved drawing of record.Chapter 5FSAR 5.1-60Editorial Change: Revised the origianl blind flange with a Westinghouse quick opening transfer tube closure via EC 282573. (LIC 2046249)FSAR 5.1-109Editorial Change: Incorporated Figure 5.1-20 into the Permanent Drawing System. (LIC 2046249)FSAR 5.2-88Licensing Basis Change: Figure updated for SI-868A to read as closed systems. (LIC 2102267)FSAR 5.2-103Editorial Change: Incorporated Figure 5.2-72 into the Permanent Drawing System. (LIC 2046249)FSAR 5.3-5Licensing Basis Change: Updated Containment Ventilating System Section, Containment Venting During Normal Operation to read 1 psig for applicability when the RE-211/212 radiation monitoring forced ventilation pump is put into service. (LIC 2113706)FSAR 5.3-10Updated Figure to reflect approved drawing of record.Chapter 6FSAR 6.2-12Licensing Basis Change: Added discussion that pumps are analyzed as degraded to the text of the FSAR/evaluation of components and added new reference. (LIC 2039337)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 3 of 8 Chapter 6continuedFSAR 6.2-28Licensing Basis Change: Updated the description of how the safety injection accumulators are opened. (LIC 2108307)FSAR 6.2-29Editorial Change: Added new reference 7. (LIC 2039337)FSAR 6.2-43Updated Figure to reflect approved drawing of record.FSAR 6.2-45Updated Figure to reflect approved drawing of record.FSAR 6.2-48Licensing Basis Change: Revised Figure 6.2-4 to remove degraded pump data. (LIC 2039337)FSAR 6.2-49Licensing Basis Change: Revised Figure 6.2-5 to remove degraded pump data. (LIC 2039337)FSAR 6.4-7Licensing Basis Change: Added discussion that pumps are analyzed as degraded to the text of the FSAR/evaluation of components and added new reference. (LIC 2039337)FSAR 6.4-14Editorial Change: Added new reference 11. (LIC 2039337)
FSAR 6.5-10Updated Figure to reflect approved drawing of record.Chapter 8FSAR 8.0-7Editorial Change: Revised Figure 8-1 that added new F52-7029 breaker with the existing breaker F52-Q303 in the 345kV Line Q303 to Kewaunee. (LIC 2099619)FSAR 8.1-4Editorial Change: Revised Figure 8.1-1 that added 345kV Breaker 7026 upstream of Breaker Q303 on the Kewaunee Line. (LIC 2099619)FSAR 8.5-2Editorial Change: Added new tie breaker 1B52-19B to the cross-tie between safeguard buses 1B03 and 1B04 and clairified the existing tie breaker 1B52-16C (Unit 1) and 2B52-40C (Un it 2) is tripped automatically upon receiving bus undervoltage or safety injection signals. (LIC 2064865)FSAR 8.8-6Editorial Change: Clairified the existing tie breaker 1B52-16C (Unit 1) and 2B52-40C (Unit 2) is tripped automatically upon receiving bus undervoltage or safety injection signals. (LIC 2064865)FSAR 8.8-8Licensing Basis Change: Revised 2nd paragraph to read as "Tests are performed to demonstrate assurance that upon the initiation of a start signal the diesel generator will start and assume the required load in the timing sequence listed above. The frequency for performing surveillances required by Technical Specifications will be in accordance with the Surveillance Frequency Control Program (Reference 10)," for the receipt of NRC Safety Evaluation for License Amendments Nos. 253 and 257. (LIC 2071025)FSAR 8.8-9Editorial Change: Added NRC SE dated 7/28/15 as reference 10 for the receipt of NRC Safety Evaluation for License Amendments Nos. 253 and 257. (LIC 2071025)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 4 of 8 Chapter 9FSAR 9.3-6Licensing Basis Change: Replacement of the #1 seal insert on the RCP with a new Westinghouse shutdown seal via EC 277545. (LIC 1999915)FSAR 9.3-9Licensing Basis Change: Revised discussion of charging pump and controls to describe the new low suction pressure trip function. (LIC 2082658)FSAR 9.3-12Licensing Basis Change: Revised discussion of charging pump and controls to describe the new low suction pressure trip function. (LIC 2082658)FSAR 9.3-21Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 9.3-30Updated Figure to reflect approved drawing of record.FSAR 9.4-5Editorial Change: Revised the origianl blind flange with a Westinghouse quick opening transfer tube closure via EC 282573. (LIC 2046249)FSAR 9.4-9Editorial Change: Revised the origianl blind flange with a Westinghouse quick opening transfer tube closure via EC 282573. (LIC 2046249)FSAR 9.4-14Editorial Change: Incorporated Figure 5.1-20 into the Permanent Drawing System. (LIC 2046249)FSAR 9.6-5Licensing Basis Change: Revised 1st paragraph to read as "The SW system components are tested and inspected in accordance with Technical Specification surveillance criteria and surveillance frequencies by the Surveillance Frequency Control Program (Reference 10). Testing verifies motor-driven pump operability, and operability of all required valves" and added NRC SE dated 7/28/15 as reference 10 for the receipt of NRC Safety Evaluation for License Amendments Nos. 253 and 257. (LIC 2071025)FSAR 9.6-9Updated Figure to reflect approved drawing of record.FSAR 9.6-10Updated Figure to reflect approved drawing of record.FSAR 9.9-1 throughFSAR 9.9-2Editorial Change: Updated the description of the SFP cooling system and its capabilities. (LIC 2044893)FSAR 9.9-7Editorial Change: Added calculatin PGT-2003-1495 to the Reference section. (LIC 2044893)Chapter 10FSAR 10.1-28Updated Figure to reflect approved drawing of record.FSAR 10.2-1Editorial Change: Provided clairification of the safety-related classification of the MDAFW cross-tie piping. (LIC 2088819)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 5 of 8 Chapter 10continuedFSAR 10.2-8Licensing Basis Change: Revised 4th paragraph to read as "The AF system components are tested and inspected in accordance with Technical Specification 3.7.5 surveillance criteria and surveillance frequencies by the Surveillance Frequency Control Program (Reference 22). Testing verifies motor-driven pump operability, turbine-driven pump operability including a cold start, and operability of all required automatic valves. Control circuits, starting logic, and indicators are verified operable by their respective functional test," for the receipt of NRC Safety Evaluation for License Amendments Nos. 253 and 257. (LIC 2071025)FSAR 10.2-10Editorial Change: Added NRC SE dated 7/28/15 as reference 22 for the receipt of NRC Safety Evaluation for License Amendments Nos. 253 and 257. (LIC 2071025)FSAR 10.2-10Editorial Change: Added reference 23 which provided the basis that added the clairification of the safety-related classification of the MDAFW cross-tie piping. (LIC 2088819)FSAR 10.2-13Updated Figure to reflect approved drawing of record.Chapter 11FSAR 11.1-18Updated Figure to reflect approved drawing of record.FSAR 11.2-25Updated Figure to reflect approved drawing of record.FSAR 11.2-30Updated Figure to reflect approved drawing of record.Chapter 14FSAR 14.1.2-2Editorial Change: Corrected reference numbers. (LIC 2064578)FSAR 14.1.7-1Licensing Basis Change: Revised paragraph regarding the function of the turbine governor valve position limiter. (LIC 1990553)FSAR 14.1.8-3Licensing Basis Change: Replacement of the #1 seal insert on the RCP with a new Westinghouse shutdown seal via EC 277545. (LIC 1999915)FSAR 14.1.8-6Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.1.11-3Licensing Basis Change: Replacement of the #1 seal insert on the RCP with a new Westinghouse shutdown seal via EC 277545 and added new reference. (LIC 1999915)FSAR 14.2.4-2Licensing Basis Change: Clairified the SGTR Operator action.(LIC 2109018)FSAR 14.2.4-3Licensing Basis Change: Clairified the SGTR Operator action.(LIC 2109018)FSAR 14.3.1-2Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.3.1-5Editorial Change: Added new reference for Optimized ZIRLO TM.(LIC 2064578)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 6 of 8 Chapter 14continuedFSAR 14.3.1-6Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.3.2-4Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.3.2-9Editorial Change: Added new NRC SE regarding the use of optimized ZIRLO TM as reference 9. (LIC 2064578)FSAR 14.3.2-10Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.3.2-11Licensing Basis Change: Revised for Unit 2 Cycle 35 reload design implementaiton of Optimized ZIRLO. (LIC 2064578)FSAR 14.3.4-22Licensing Basis Change: Updated LOCA M&E evaluation against the NSAL-14-2. (LIC 2092524)Chapter 15FSAR 15.2-1Editorial Change: Deleted the word "all" in front of "Class 1, 2, and 3 pressure-retaining components" to add clairification. (LIC 2105913)FSAR 15.2-6Editorial Change: Added Reference 6 to the end of sub-section 15.2.17. (LIC 2105913)FSAR 15.2-8Editorial Change: Added Reference 6 to the end of the Reference section to provide a historic basis for the details. (LIC 2105913)Appendix A.7FSAR A.7-1Licensing Basis Change: Added a specific statement for providing an internal flood relief path and added new protection methods and associated references. (LIC 2002571)FSAR A.7-2 Licensing Basis Change: Added new section on flood levels and associated references for safe shutdown being the event end point and the basis for the flood levels. (LIC 2002571)FSAR A.7-3Licensing Basis Change: Added new protection method, re-phrased , guideline 1 in NRC letter dated 12-10-1974, added Bullet discussing auxiliary feedwater separation, added Bullet discussing vital switchgear separation, added discussion regarding Category 1 seismic SSCs not being considered flood sources, added discussion regarding the main condensers and associated piping and deleted summary statement regarding non-category 1 (seismic) SSCs. (LIC 2002571)FSAR A.7-3Editorial Change: Re-located LOOP discussion from A.7.1, added detail to the definition of what sources were evaluated, removed previous listing of evaluated systems, and added reference to the evaluation/calculation which provides more detail. (LIC 2002571)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 7 of 8 Appendix A.7continuedFSAR A.7-5Editorial Change: Re-formatted table to match that of recently updated table A.7-2, updated table title, deleted the column listing the flood source, Circulating Water Pump House/Service Water Pump Area: re-statement of information from table A.7-2 for external flooding, and split compound sentence into separate bullets and updated the reference in the second bullet to Reference 28 (Calculation 2014-0007). (LIC 2002571)FSAR A.7-5Licensing Basis Change: Circulating Water Pump House/Service Water Pump Area: reduced the number of louvers from 6 to 2 based on the results of calculation 2009-0008. (LIC 2002571)FSAR A.7-5Licensing Basis Change: Updated Table A.7-1 that the NVSGR wall is a credited desing design feature to mitigate plant internal flooding.(LIC 2019391)FSAR A.7-5Licensing Basis Change: Auxiliary Feedwater Pump Area: Added new discussion bullets. (LIC 2002571)FSAR A.7-5Licensing Basis Change: Vital Switchgear Room: Added new discussion bullets, added new discussion regarding door 18, added new discussion regarding door 14, separated this from the bullet above because of the physical difference implemented by EC 282394, added detail to discussion regarding manhole covers, and added the limiting equipment height.
(LIC 2002571)FSAR A.7-5 through FSAR A.7-6Licensing Basis Change: Changed the design feature for the Emergency Diesel Generator G-01/02 Rooms and and the Vital Switchgear Room. Updated associated references. (LIC 1985139)FSAR A.7-5 throughFSAR A.7-7License Basis Change: Updated Table A.7-1 for Comprehensive Internal Flooding for Turbine Hall via EC 282394 and Flood Mitigation Strategy-DGB, NVSGR, and HVAC Room via EC 283362. (LIC 2135046)FSAR A.7-6Licensing Basis Change: Emergency Diesel Generator G-01/02 Room: Added new discussion bullets and added the limiting equipment height. (LIC 2002571)FSAR A.7-6Editorial Change: Computer Room: Replaced "berm" with 8" high curb to provide a more accurate description and created second bullet to discuss Door-075. (LIC 2002571)FSAR A.7-6Licensing Basis Change: Control Room: Added details that were discussed in the SER but were not in the FSAR. (LIC 2002571)FSAR A.7-6Editorial Change: Auxiliary Building: Deleted existing note 2 as this note added no value to the understanding of plant design. (LIC 2002571)FSAR A.7-6Licensing Basis Change: Auxiliary Building: Added new discussion bullet. (LIC 2002571)FSAR A.7-6Editorial Change: Tendon Gallery: Removed existing note 2 as this note added no value to the understanding of plant design and added strategy as a header. (LIC 2002571)
Description of ChangesFSAR DOCUFSAR 2015Page DOC - 8 of 8 Appendix A.7continuedFSAR A.7-7Licensing Basis Change: Documented the internal flooding from a failure of the fire protection piping in the G03/04 buidling as stated in docketed correspondence. (LIC 2055230)FSAR A.7-7Editorial Change: Residual Heat Removal Pump Cubicles: Added strategy as a header. (LIC 2002571)FSAR A.7-10Editorial: Added new Reference 10. (LIC 1985139)
FSAR A.7-11Editorial: Added new Reference 29. (LIC 2019391)FSAR A.7-12Editorial Change: Added new References 43, 47 through 52.(LIC 2002571)FSAR A.7-12Editorial Change: Added Reference 53 for EC 283362. (LIC 2135046)
Table of ContentsFSAR UFSAR 2015Page TOC - 1 of 17 GENERAL TABLE OF CONTENTS
1.0INTRODUCTION
AND
SUMMARY
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.0-11.1SITE AND ENVIRONMENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.1-11.2
SUMMARY
PLANT DESCRIPTION - - - - - - - - - - - - - - - - - - - - - - - - - 1.2-1 1.2.1STRUCTURES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.2-1 1.2.2NUCLEAR STEAM SUPPLY SYSTEM - - - - - - - - - - - - - - - - - - - - 1.2-1 1.2.3REACTOR AND PLANT CONTROL - - - - - - - - - - - - - - - - - - - - - 1.2-2 1.2.4WASTE DISPOSAL SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - 1.2-2 1.2.5FUEL HANDLING SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - 1.2-3 1.2.6TURBINE AND AUXILIARIES - - - - - - - - - - - - - - - - - - - - - - - - 1.2-3 1.2.7ELECTRICAL SYSTEM- - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.2-3 1.2.8ENGINEERED SAFETY FEATURES SYSTEMS- - - - - - - - - - - - - - - - 1.2-4 1.2.9SHARED FACILITIES AND EQUIPMENT - - - - - - - - - - - - - - - - - - 1.2-4 1.2.10INDEPENDENT SPENT FUEL STORAGE INSTALLATION- - - - - - - - - - 1.2-41.3GENERAL DESIGN CRITERIA - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.3-1 1.3.1OVERALL PLANT REQUIREMENTS (GDC 1- GDC 5) - - - - - - - - - - - - 1.3-1 1.3.2PROTECTION BY MULTIPLE FISSION PRODUCT BARRIERS(GDC 6 - GDC 10)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.3-3 1.3.3NUCLEAR AND RADIATION CONTROLS (GDC 11 - GDC 18)- - - - - - - - 1.3-5 1.3.4RELIABILITY AND TESTABILITY OF PROTECTION SYSTEMS(GDC 19 - GDC 26) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.3-7 1.3.5REACTIVITY CONTROL (GDC 27 - GDC 32)- - - - - - - - - - - - - - - - - 1.3-9 1.3.6REACTOR COOLANT PRESSURE BOUNDARY (GDC 33 - GDC 36) - - - - - 1.3-10 1.3.7ENGINEERED SAFETY FEATURES (GDC 37 - GDC 65) - - - - - - - - - - - 1.3-12 1.3.8FUEL AND WASTE STORAGE SYSTEMS (GDC 66 - GDC 69) - - - - - - - - 1.3-17 1.3.9PLANT EFFLUENTS (GDC 70) - - - - - - - - - - - - - - - - - - - - - - - - 1.3-18
1.3.10RESOLUTION OF SYSTEMATIC EVALUATION PROGRAM ISSUES - - - - 1.3-18 1.3.11RESOLUTION OF OTHER ISSUES ADDRESSED BY THE INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS - - - - - - - - - - - - - - - - - - 1.3-19 1.3.12REFERENCES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.3-191.4QUALITY ASSURANCE PROGRAM - - - - - - - - - - - - - - - - - - - - - - - - 1.4-1 1.
4.1REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.4-11.5FACILITY SAFETY CONCLUSIONS - - - - - - - - - - - - - - - - - - - - - - - - 1.5-1 1.
5.1REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1.5-1 Table of ContentsFSAR UFSAR 2015Page TOC - 2 of 17 2.0SITE AND ENVIRONMENT- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.0-12.1SITE LOCATION AND BOUNDARIES - - - - - - - - - - - - - - - - - - - - - - - 2.1-1 2.2TOPOGRAPHY - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-12.3POPULATION (Historical) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.3-12.4LAND USE (Historical)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.4-12.5HYDROLOGY- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.5-12.5.1GENERAL LAKE HYDROLOGY - - - - - - - - - - - - - - - - - - - - - - - 2.5-12.5.2LAKE LEVELS AND FLOODING- - - - - - - - - - - - - - - - - - - - - - - 2.5-3 2.5.3DILUTION AND DIFFUSION IN LAKE MICHIGAN - - - - - - - - - - - - - 2.5-82.6METEOROLOGY - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-12.7ENVIRONMENTAL RADIOACTIVITY STUDIES - - - - - - - - - - - - - - - - - - 2.7-12.8GEOLOGY- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.8
-12.9SEISMOLOGY- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.9-12.10ENVIRONMENTAL CONCLUSIONS - - - - - - - - - - - - - - - - - - - - - - - - 2.10-12.11REFERENCES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.11
-13.0REACTOR- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.1-13.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.1-1 3.1.1PERFORMANCE OBJECTIVES - - - - - - - - - - - - - - - - - - - - - - - - 3.1-1 3.1.2PRINCIPAL DESIGN CRITERIA - - - - - - - - - - - - - - - - - - - - - - - 3.1-2 3.1.3SAFETY LIMITS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.1-73.2REACTOR DESIGN - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-1 3.2.1NUCLEAR DESIGN AND EVALUATION- - - - - - - - - - - - - - - - - - - 3.2-1 3.2.2THERMAL AND HYDRAULIC DESIGN AND EVALUATION - - - - - - - - 3.2-10 3.2.3MECHANICAL DESIGN AND EVALUATION - - - - - - - - - - - - - - - - 3.2-1 73.3RELOAD CORE DESIGN AND SAFETY ANALYSIS - - - - - - - - - - - - - - - - 3.3-13.4FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS - - - - - - - - - - 3.4-14.0REACTOR COOLANT SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.1-14.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.1-14.2RCS SYSTEM DESIGN AND OPERATION - - - - - - - - - - - - - - - - - - - - - 4.2-14.3SYSTEM DESIGN EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - 4.3-1 4.4TESTS AND INSPECTIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.4-15.0CONTAINMENT SYSTEM STRUCTURE - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-15.1CONTAINMENT SYSTEM STRUCTURE - - - - - - - - - - - - - - - - - - - - - - 5.1-1 Table of ContentsFSAR UFSAR 2015Page TOC - 3 of 17 5.1.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-1 5.1.2CONTAINMENT SYSTEM STRUCTURE DESIGN - - - - - - - - - - - - - - 5.1-8 5.
1.3REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-645.2CONTAINMENT ISOLATION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - 5.2-1 5.2.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.2-1 5.2.2SYSTEM DESIGN- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.2-25.3CONTAINMENT VENTILATING SYSTEM - - - - - - - - - - - - - - - - - - - - - 5.3-1 5.3.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.3-1 5.3.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 5.3-2 5.
3.3REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.3-55.4SYSTEM DESIGN EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - 5.4-1 5.4.1RELIANCE ON INTERCONNECTED SYSTEMS - - - - - - - - - - - - - - - 5.4-1 5.4.2SYSTEM INTEGRITY AND SAFETY FACTORS - - - - - - - - - - - - - - - 5.4-1 5.4.3PERFORMANCE CAPABILITY MARGIN- - - - - - - - - - - - - - - - - - - 5.4-15.5MINIMUMOPERATINGCONDITIONS - - - - - - - - - - - - - - - - - - - - - - - 5.5-1 5.5.1CONTAINMENT INTEGRITY- - - - - - - - - - - - - - - - - - - - - - - - - 5.5-1 5.5.2EXTERNAL PRESSURE AND INTERNAL VACUUM- - - - - - - - - - - - - 5.5-1 5.5.3LEAKAGE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.5-15.6CONSTRUCTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.6-1 5.6.1CONSTRUCTION METHODS- - - - - - - - - - - - - - - - - - - - - - - - - 5.6-1 5.6.2MATERIALS OF CONSTRUCTION IN CONTAINMENT - - - - - - - - - - - 5.6-75.7TESTSANDINSPECTIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.7-1 5.7.1PREOPERATIONAL TESTING - - - - - - - - - - - - - - - - - - - - - - - - 5.7-26.0ENGINEEREDSAFETYFEATURES- - - - - - - - - - - - - - - - - - - - - - - - - 6.0-1 6.1CRITERIA - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.1-1 6.1.1ENGINEERED SAFETY FEATURES CRITERIA - - - - - - - - - - - - - - - 6.1-1 6.1.2RELATED CRITERIA- - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.1-5 6.1.3GENERIC LETTER 2008 - - - - - - - - - - - - - - - - - - - - - - - - - 6.1-6 6.
1.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.1-66.2SAFETY INJECTION SYSTEM (SI) - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-1 6.2.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-1 6.2.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 6.2-4 Table of ContentsFSAR UFSAR 2015Page TOC - 4 of 17 6.2.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-22 6.2.4REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 6.2-27 6.
2.5REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-286.3CONTAINMENTAIRRECIRCULATIONCOOLINGSYSTEM (VNCC) - - - - - - - 6.3-1 6.3.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.3-1 6.3.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 6.3-3 6.3.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.3-8 6.3.4REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 6.3-12 6.
3.5REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.3-136.4CONTAINMENT SPRAY SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-1 6.4.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-1 6.4.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 6.4-4 6.4.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-9 6.4.4REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 6.4-12 6.
4.5REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-136.5LEAKAGE DETECTION SYSTEMS - - - - - - - - - - - - - - - - - - - - - - - - - 6.5-1 6.5.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.5-1 6.5.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 6.5-2 6.5.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.5-8 6.5.4REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 6.5-9 6.
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17.1INTRODUCTION
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.1-1 7.1.1IDENTIFICATION OF SAFETY-RELATED INSTRUMENTATION SYSTEMS 7.1-1 7.1.2GENERAL DESIGN CRITERIA - - - - - - - - - - - - - - - - - - - - - - - - 7.1-1 7.1.3OTHER CRITERIA - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.1-9 7.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.1-107.2REACTOR PROTECTIONSYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-1 7.2.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-1 7.2.2SYSTEM DESIGN- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-5 7.2.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-16 7.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.3-147.4OTHER ACTUATION SYSTEMS - - - - - - - - - - - - - - - - - - - - - - - - - - 7.4-1 7.4.1AMSAC- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.4-1 7.4.2LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) - - - - - - - 7.4-5 7.4.3AFW PUMP SUCTION TRANSFER AND TRIP ON LOWSUCTION PRESSURE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.4-6 7.
4.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.4-77.5OPERATINGCONTROLSTATIONS - - - - - - - - - - - - - - - - - - - - - - - - 7.5-1 7.5.1CONTROL STATIONS LAYOUT, INFORMATION DISPLAY ANDRECORDING - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.5-1 7.5.2COMMUNICATIONSSYSTEMS - - - - - - - - - - - - - - - - - - - - - - - 7.5-7 7.5.3OCCUPANCY- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.5-7 7.5.4EMERGENCY SHUTDOWN CONTROL - - - - - - - - - - - - - - - - - - - 7.5-8 7.
5.5REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.5-127.6INSTRUMENTATION SYSTEMS - - - - - - - - - - - - - - - - - - - - - - - - - - 7.6-1 7.6.1NUCLEAR INSTRUMENTATION SYSTEM- - - - - - - - - - - - - - - - - - 7.6-1 7.6.2POST-ACCIDENT MONITORING INSTRUMENTATION - - - - - - - - - - - 7.6-10 7.6.3INCORE INSTRUMENTATION - - - - - - - - - - - - - - - - - - - - - - - - 7.6-11 7.6.4LOOSE PARTS MONITORING - - - - - - - - - - - - - - - - - - - - - - - - 7.6-147.7CONTROLSYSTEMS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.7-1 7.7.1ROD CONTROL SYSTEM- - - - - - - - - - - - - - - - - - - - - - - - - - - 7.7-1 7.7.2CONDENSER STEAM DUMP CONTROL- - - - - - - - - - - - - - - - - - - 7.7-8 7.7.3PRESSURIZER CONTROL - - - - - - - - - - - - - - - - - - - - - - - - - - 7.7-9 7.7.4STEAM GENERATOR CONTROL - - - - - - - - - - - - - - - - - - - - - - 7.7-11 7.7.5AUTOMATICTURBINELOADRUNBACK- - - - - - - - - - - - - - - - - - 7.7-12 7.7.6SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.7-12 7.
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48.0INTRODUCTION
TO THE ELECTRICAL DISTRIBUTION SYSTEMS - - - - - - - 8.0-1 8.0.1PRINCIPAL DESIGN CRITERIA - - - - - - - - - - - - - - - - - - - - - - - 8.0-1 8.0.2REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 8.0-5 Table of ContentsFSAR UFSAR 2015Page TOC - 6 of 17 8.0.3SINGLE LINE DIAGRAMS - - - - - - - - - - - - - - - - - - - - - - - - - - 8.0-5 8.
0.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.0-68.1345 kV AC ELECTRICAL DISTRIBUTION SYSTEM (345 kV)- - - - - - - - - - - - 8.1-1 8.1.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.1-1 8.1.2SYSTEM DESCRIPTION AND OPERATION - - - - - - - - - - - - - - - - - 8.1-1 8.1.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.1-2 8.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.1-38.213.8K VAC ELECTRICAL DISTRIBUTION SYSTEM (13.8kV)- - - - - - - - - - - - 8.2-1 8.2.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.2-1 8.2.2SYSTEM DESCRIPTION AND OPERATION - - - - - - - - - - - - - - - - - 8.2-1 8.2.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.2-3 8.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.2-38.319K VAC ELECTRICAL DISTRIBUTION SYSTEM (19 KV)- - - - - - - - - - - - - 8.3-1 8.3.1DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.3-1 8.3.2SYSTEM DESCRIPTION AND OPERATION - - - - - - - - - - - - - - - - - 8.3-1 8.3.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.3-2 8.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 9.2-59.3CHEMICAL AND VOLUME CONTROL SYSTEM (CV) - - - - - - - - - - - - - - - 9.3-1 Table of ContentsFSAR UFSAR 2015Page TOC - 8 of 17 9.3.1DESIGN BASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 9.3-1 9.3.2SYSTEM DESIGN AND OPERATION- - - - - - - - - - - - - - - - - - - - - 9.3-3 9.3.3SYSTEM EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - - - 9.3-18 9.3.4REQUIRED PROCEDURES AND TESTS - - - - - - - - - - - - - - - - - - - 9.3-2 2 9.
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.7-113.0SITE SURVEILLANCE AND TESTING PROGRAMS (Historical)- - - - - - - - - - - 13.0-1 13.1OBJECTIVES and SCOPE (Historical) - - - - - - - - - - - - - - - - - - - - - - - - 13.1-113.2GENERAL (Historical) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 13.2-113.3FINAL PLANT PREPARATION (Historical) - - - - - - - - - - - - - - - - - - - - - 13.3-1 13.4INITIAL TESTING IN THE OPERATING REACTOR (Historical)- - - - - - - - - - - 13.4-114.0SAFETY ANALYSIS- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.0-1 14.
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- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.0-814.1CORE AND COOLANT BOUNDARY PROTECTION ANALYSIS - - - - - - - - - - 14.1.1-1 14.1.1UNCONTROLLED ROD WITHDRAWAL FROM SUBCRITICAL - - - - - - - 14.1.1-1 Table of ContentsFSAR UFSAR 2015Page TOC - 12 of 17 14.1.2UNCONTROLLED ROD WITHDRAWAL AT POWER - - - - - - - - - - - - 14.1.2-1 14.1.3ROD CLUSTER CONTROL ASSEMBLY DROP- - - - - - - - - - - - - - - - 14.1.3-1 14.1.4CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION - - - - - 14.1.4-1 14.1.5STARTUP OF AN INACTIVE REACTOR COOLANT LOOP - - - - - - - - - 14.1.5-1 14.1.6REDUCTION IN FEEDWATER ENTHALPY INCIDENT - - - - - - - - - - - 14.1.6-1 14.1.7EXCESSIVE LOAD INCREASE INCIDENT - - - - - - - - - - - - - - - - - - 14.1.7-1 14.1.8LOSS OF REACTOR COOLANT FLOW- - - - - - - - - - - - - - - - - - - - 14.1.8-1 14.1.9LOSS OF EXTERNAL ELECTRICAL LOAD (EPU Conditions) - - - - - - - - 14.1.9-1 14.1.10LOSS OF NORMAL FEEDWATER - - - - - - - - - - - - - - - - - - - - - - 14.1.10-1 14.1.11LOSS OF ALL AC POWER TO STATION AUXILIARIES - - - - - - - - - - - 14.1.11-1 14.1.12LIKELIHOOD OF TURBINE-GENERATOR UNIT OVERSPEED - - - - - - - 14.1.12-114.2STANDBY SAFETY FEATURES ANALYSIS - - - - - - - - - - - - - - - - - - - - 14.2.1-1 14.2.1FUEL HANDLING ACCIDENT - - - - - - - - - - - - - - - - - - - - - - - - 14.2.1-1 14.2.2ACCIDENTAL RELEASE-RECYCLE OR WASTE LIQUID - - - - - - - - - - 14.2.2-1 14.2.3ACCIDENTAL RELEASE-WASTE GAS- - - - - - - - - - - - - - - - - - - - 14.2.3-1 14.2.4STEAM GENERATOR TUBE RUPTURE - - - - - - - - - - - - - - - - - - - 14.2.4-1 14.2.5RUPTURE OF A STEAM PIPE - - - - - - - - - - - - - - - - - - - - - - - - 14.2.5-1 14.2.6RUPTURE OF A CONTROL ROD MECHANISM HOUSING - RCCAEJECTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.2.6-114.2.7INADVERTENT OPENING OF A STEAM GENERATOR (SG) RELIEF ORSAFETY VALVE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.2.7-114.3PRIMARY SYSTEM PIPE RUPTURES- - - - - - - - - - - - - - - - - - - - - - - - 14.3.1-1 14.3.1SMALL BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS- - - - - - - - 14.3.1-114.3.2LARGE BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS- - - - - - - - 14.3.2-1'14.3.3CORE AND INTERNALS INTEGRITY ANALYSIS - - - - - - - - - - - - - - 14.3.3-114.3.4LOCA M&E RELEASE AND CONTAINMENT RESPONSE - - - - - - - - - - 14.3.4-114.3.5RADIOLOGICAL CONSEQUENCES OF LOSS-OF-COOLANT ACCIDENT- - 14.3.5-1 14.3.6REACTOR VESSEL HEAD DROP EVENT - - - - - - - - - - - - - - - - - - 14.3.6-1 15.0AGING MANAGEMENT PROGRAMS and TIME LIMITED AGING ANALYSIS- - - 15.0-115.1PROGRAMS THAT MANAGE THE EFFECTS OF AGING AND GENERIC QUALITY ASSURANCE PROGRAM REQUIREMENTS - - - - - - - - - - - - - - - - - - - - 15.0-115.2AGING MANAGEMENT PROGRAM DESCRIPTIONS- - - - - - - - - - - - - - - - 15.2-1 15.2.1ASME SECTION XI, SUBSECTIONS IWB, IWC, AND IWD ISI PROGRAM- - 15.2-1 15.2.2ASME SECTION XI, SUBSECTIONS IWE and IWL ISI PROGRAM - - - - - - 15.2-1 15.2.3ASME SECTION XI, SUBSECTION IWF ISI PROGRAM - - - - - - - - - - - 15.2-2 15.2.4BOLTING INTEGRITY PROGRAM - - - - - - - - - - - - - - - - - - - - - - 15.2-2 Table of ContentsFSAR UFSAR 2015Page TOC - 13 of 17 15.2.5BORAFLEX MONITORING PROGRAM - - - - - - - - - - - - - - - - - - - 15.2-2 15.2.6BORIC ACID CORROSION PROGRAM- - - - - - - - - - - - - - - - - - - - 15.2-2 15.2.7BURIED SERVICES MONITORING PROGRAM - - - - - - - - - - - - - - - 15.2-3 15.2.8CABLE CONDITION MONITORING PROGRAM - - - - - - - - - - - - - - - 15.2-3 15.2.9CLOSED-CYCLE COOLING WATER SYSTEM SURVEILLANCE PROGRAM 15.2-3 15.2.10FIRE PROTECTION PROGRAM - - - - - - - - - - - - - - - - - - - - - - - 15.2-4 15.2.11FLOW-ACCELERATED CORROSION PROGRAM - - - - - - - - - - - - - - 15.2-4 15.2.12FUEL OIL CHEMISTRY CONTROL PROGRAM - - - - - - - - - - - - - - - 15.2-4 15.2.13ONE-TIME INSPECTION PROGRAM- - - - - - - - - - - - - - - - - - - - - 15.2-4 15.2.14OPEN-CYCLE COOLING (SERVICE) WATER SYSTEM SURVEILLANCEPROGRAM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.2-5 15.2.15 PERIODIC SURVEILLANCE AND PREVENTIVE MAINTENANCEPROGRAM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.2-5 15.2.16REACTOR COOLANT SYSTEM ALLOY 600 INSPECTION PROGRAM - - - 15.2-6 15.2.17REACTOR VESSEL INTERNALS PROGRAM- - - - - - - - - - - - - - - - - 15.2-6 15.2.18REACTOR VESSEL SURVEILLANCE PROGRAM - - - - - - - - - - - - - - 15.2-6 15.2.19STEAM GENERATOR INTEGRITY PROGRAM - - - - - - - - - - - - - - - 15.2-7 15.2.20STRUCTURES MONITORING PROGRAM - - - - - - - - - - - - - - - - - - 15.2-7 15.2.21SYSTEMS MONITORING PROGRAM - - - - - - - - - - - - - - - - - - - - 15.2-7 15.2.22TANK INTERNAL INSPECTION PROGRAM - - - - - - - - - - - - - - - - - 15.2-7 15.2.23THIMBLE TUBE INSPECTION PROGRAM- - - - - - - - - - - - - - - - - - 15.2-8 15.2.24WATER CHEMISTRY CONTROL PROGRAM - - - - - - - - - - - - - - - - 15.2-8 15.2.25REFERENCES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.2-815.3TIME LIMITED AGING ANALYSIS SUPPORTING ACTIVITIES - - - - - - - - - - 15.3-115.4 EVALUATION OF TIME-LIMITED AGING ANALYSES - - - - - - - - - - - - - - 15.4-1 15.4.1REACTOR VESSEL IRRADIATION EMBRITTLEMENT - - - - - - - - - - - 15.4-1 15.4.2 FATIGUE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.4-3 15.4.3FRACTURE MECHANICS ANALYSIS - - - - - - - - - - - - - - - - - - - - 15.4-9 15.4.4LOSS OF PRELOAD - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.4-15 15.4.5NEUTRON ABSORBER- - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.4-15 15.4.6ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT - - - 15.4-15 15.4.7UNIT 1 PRESSURIZER FLAW EVALUATION - - - - - - - - - - - - - - - - 15.4-16 15.4.8UNIT 1 STEAM GENERATOR B FLAW EVALUATION - - - - - - - - - - - 15.4-17 Table of ContentsFSAR UFSAR 2015Page TOC - 14 of 17 15.4.9UNIT 1 STEAM GENERATOR A FLAW EVALUATION - - - - - - - - - - - 15.4-18 15.4.10FLAW TOLERANCE EVALUATION FOR SUSCEPTIBLE CASSREACTOR COOLANT PIPING COMPONENTS IN POINT BEACH UNITS 1 AND 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.4-19 15.4.11UNIT 1 REACTOR VESSEL INLET NOZZLE FLAW EVALUATION - - - - - 15.4-20 15.4.12REFERENCES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.4-2 115.5EXEMPTIONS- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 15.5-1A.1STATION BLACKOUT (SBO)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.1-1A.1.1STATION BLACKOUT OVERVIEW- - - - - - - - - - - - - - - - - - - - - - - - - A.1-1A.1.2STATION BLACKOUT COPING DURATION CATEGORY DETERMINATION - - - A.1-2 A.1.3STATION BLACKOUT COPING ANALYSES - - - - - - - - - - - - - - - - - - - - A.1-5 A.1.4ALTERNATE AC SOURCE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.1-8A.1.5PROCEDURES AND TRAINING- - - - - - - - - - - - - - - - - - - - - - - - - - - A.1-9A.1.6QUALITY ASSURANCE PROGRAM - - - - - - - - - - - - - - - - - - - - - - - - A.1-9 A.
1.7 REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.1
-9A.2HIGH ENERGY PIPE FAILURE OUTSIDE CONTAINMENT - - - - - - - - - - - - - - - - A.2-1A.
2.1INTRODUCTION
AND EVALUATION CRITERIA - - - - - - - - - - - - - - - - - A.2-1 A.
2.2DESCRIPTION
OF HIGH ENERGY SYSTEMS- - - - - - - - - - - - - - - - - - - - A.2-1A.
2.3DESCRIPTION
OF BREAK AND CRACK LOCATIONS - - - - - - - - - - - - - - - A.2-2A.
2.4DESCRIPTION
OF NEEDED EQUIPMENT - - - - - - - - - - - - - - - - - - - - - A.2-3 A.2.5METHODOLOGIES FOR LOCATIONS, SIZE AND ORIENTATION OF BREAKS - - A.2-3A.2.6METHODOLOGY FOR CALCULATING MASS AND ENERGY RELEASE - - - - - A.2-4A.2.7METHODOLOGY FOR COMPARTMENT PRESSURE AND TEMPERATURE- - - - A.2-5 A.2.8METHODOLOGY FOR JET IMPINGEMENT - - - - - - - - - - - - - - - - - - - - A.2-5A.2.9METHODOLOGY FOR PIPE WHIP - - - - - - - - - - - - - - - - - - - - - - - - - A.2-12A.2.10REFERENCES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.2-13A.3CONTROL OF HEAVY LOADS- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.3-1A.3.1OVERVIEW - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.3-1A.3.2NUREG-0612 PHASE I REQUIREMENTS AND COMMITMENTS - - - - - - - - - - A.3-2A.3.3AUXILIARY BUILDING CRANE - - - - - - - - - - - - - - - - - - - - - - - - - - A.3-7A.3.4CONTAINMENT POLAR CRANE - - - - - - - - - - - - - - - - - - - - - - - - - - A.3-7A.
3.5REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.3
-9A.4(DELETED) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.4-1 Table of ContentsFSAR UFSAR 2015Page TOC - 15 of 17 A.5SEISMIC DESIGN ANALYSIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.5-1A.5.1SEISMIC DESIGN CLASSIFICATIONS - - - - - - - - - - - - - - - - - - - - - - - A.5-1 A.5.2SEISMIC CLASSIFICATION OF STRUCTURES AND EQUIPMENT- - - - - - - - - A.5-4A.5.3CLASS I DESIGN CRITERIA FOR VESSELS AND PIPING - - - - - - - - - - - - - A.5-8A.5.4SEISMICDESIGNOFCLASS ISTRUCTURES - - - - - - - - - - - - - - - - - - - A.5-13 A.5.5SEISMIC DESIGN OF SERVICE WATER PIPING - - - - - - - - - - - - - - - - - - A.5-15A.5.6VERIFICATION OF SEISMIC ADEQUACY OF EQUIPMENT PER NRCGENERIC LETTER 87-02 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.5-16A.5.7SEISMIC ANALYSIS OF PIPING SYSTEMS- - - - - - - - - - - - - - - - - - - - - A.5-17 A.5.8MASONRY WALL DESIGN- - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.5-20 A.5.9SEISMIC ANALYSIS OF THE DIESEL GENERATOR BUILDING (DGB) - - - - - - A.5-21 A.5.10REFERENCES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.5-21A.6SHARED SYSTEMS ANALYSIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.6-1 A.7PLANT FLOODING - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.7-1B.2DESIGNPARAMETERSANDPLANTCOMPARISONS- - - - - - - - - - - - - - - - - - - B.2-1B.3INITIAL PLANT DESIGN - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - B
.3-1C.1PURPOSE OF CHEMICAL ADDITION TO CONTAINMENT SPRAY - - - - - - - - - - - - C.1-1DDIESEL GENERATOR PROJECT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-1D.1INTRODUCTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-1D.2DIESEL GENERATOR BUILDING (DGB) - - - - - - - - - - - - - - - - - - - - - - D-1 D.3CABLE AND RACEWAY DESIGN - - - - - - - - - - - - - - - - - - - - - - - - - D-2D.4VENTILATION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-3D.5COMBUSTION AIR INTAKE AND EXHAUST SYSTEM - - - - - - - - - - - - - - D-3 D.6ENGINE COOLING SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-3D.7STARTING AIR SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-4D.8LUBE OIL SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-4 D.9FUEL OIL SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-5D.10REFERENCES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - D-5I.110 CFR 50, APPENDIX I EVALUATION OF RADIOACTIVE RELEASES FROM POINT BEACH NUCLEAR PLANT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.1-1I.1INTRODUCTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.1-1I.1.1LIQUID RADIOACTIVE WASTE SYSTEM (See Note 1)- - - - - - - - - - - - - - - I.1-1I.1.2GASEOUS RADIOACTIVE WASTE SYSTEM (See Note 1) - - - - - - - - - - - - - I.1-1I.1.3SECONDARY SYSTEM WASTES (See Note 1) - - - - - - - - - - - - - - - - - - - I.1-1 Table of ContentsFSAR UFSAR 2015Page TOC - 16 of 17 I.1.4CHEMICAL AND VOLUME CONTROL SYSTEM (See Note 1)- - - - - - - - - - - I.1-2I.1.5PLANT VENTILATION AND FILTRATION SYSTEM (See Note 1) - - - - - - - - - I.1-2I.1.6PREVIOUS RADIOACTIVE WASTE SYSTEM MODIFICATIONS (See Note 1)- - - I.1-2I.1.7SUBSEQUENT CHANGES TO THE WASTEWATER EFFLUENT SYSTEM - - - - - I.1-3I.1.8SUBSEQUENT CHANGES TO THE LIQUID RADIOACTIVE WASTE SYSTEM- - - I.1-3I.2INFORMATION IN RESPONSE TO APPENDIX D OF DRAFT REGULATORY GUIDE 1.BB I.2-1I.2.1GENERAL- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.2-1I.2.2PRIMARY SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.2-2 I.2.3SECONDARY SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.2-2 I.2.4LIQUID WASTE PROCESSING SYSTEMS - - - - - - - - - - - - - - - - - - - - - I.2-3I.2.5GASEOUS WASTE PROCESSING SYSTEM- - - - - - - - - - - - - - - - - - - - - I.2-4I.2.6VENTILATION AND EXHAUST SYSTEMS- - - - - - - - - - - - - - - - - - - - - I.2-6 I.2.7REFERENCE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.2
-8I.3CALCULATED SOURCE TERMS AND RELEASES OF GASEOUS AND LIQUIDEFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.3-1I.3.1ORIGINAL APPENDIX I EVALUATION- - - - - - - - - - - - - - - - - - - - - - - I.3-1 I.3.2IMPACT OF UPRATED POWER OPERATIONS - - - - - - - - - - - - - - - - - - - I.3-1I.3.3REFERENCE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.3
-2I.4.METEOROLOGY - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.4-1I.4.1METEOROLOGICAL PROGRAM AT POINT BEACH NUCLEAR PLANT - - - - - - I.4-1I.
4.2DESCRIPTION
OF X/Q AND D/Q MODELING PROCEDURES - - - - - - - - - - - I.4-4I.4.3CALCULATED /Q AND D/Q VALUE FOR POINT BEACH NUCLEAR PLANT - - I.4-9I.
4.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.4
-9I.5HYDROLOGY- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.5-1I.
5.1DESCRIPTION
OF DISCHARGE- - - - - - - - - - - - - - - - - - - - - - - - - - - I.5-1 I.5.2HYDROLOGY MODEL - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.5-1I.5.3INPUT DATA - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.5-3I.
5.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.5
-3I.6SUPPLEMENTAL INFORMATION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.6-1I.6.1ENCLOSURE 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.6-1I.6.2ENCLOSURE 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.6-1I.7COMPARISONS OF REPORTED AND CALCULATED RELEASES OF RADIOACTIVITY - I.7-1I.7.1GASEOUS RELEASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.7-1 Table of ContentsFSAR UFSAR 2015Page TOC - 17 of 17 I.7.2LIQUID RELEASES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.7-2I.8CALCULATIONS OF DOSES TO MAN - - - - - - - - - - - - - - - - - - - - - - - - - - - I.8-1I.8.1DOSE MODELS - OFFSITE INDIVIDUALS - - - - - - - - - - - - - - - - - - - - - I.8-1I.8.2DOSE MODELS - ONSITE INDIVIDUALS- - - - - - - - - - - - - - - - - - - - - - I.8-4I.8.3CALCULATED DOSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.8-5 I.
8.4REFERENCES
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.8
-5I.9
SUMMARY
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.9-1I.9.1GASEOUS RELEASES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.9-1 I.9.2LIQUID RELEASES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.9-1 I.9.3IMPACT OF UPRATED POWER OPERATIONS - - - - - - - - - - - - - - - - - - - I.9-2I.9.4REFERENCE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I.9
-3T.1TECHNICAL REQUIREMENTS MANUAL - - - - - - - - - - - - - - - - - - - - - - - - - T.1-1 List of TablesFSAR UFSAR 2015Page LOT - 1 of 11 FSAR LIST OF TABLESTableTitle1.3-1POINT BEACH GENERAL DESIGN CRITERIA- - - - - - - - - - - - - - - - - - - - - 1.3-211.3-2 SEP CATEGORY 3 AND 4 ISSUES RESOLVED BY IPEEE - - - - - - - - - - - - - - - 1.3-291.3-3ADDITIONAL GENERIC SAFETY ISSUES RESOLVED BY IPEEE- - - - - - - - - - - 1.3-302.4-1TYPICAL INDUSTRIES IN REGION AT THE TIME OF LICENSE APPLICATION(Historical) Sheets 1-2
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.4-32.5-1FREQUENCY AND WAVE HEIGHT FOR DEEP WATER CONDITIONS - - - - - - - - 2.5-122.5-2AVERAGE AND MAXIMUM PRECIPITATION - - - - - - - - - - - - - - - - - - - - 2.5-132.5-3MUNICIPAL GROUND WATER SUPPLIES AT THE TIME OF LICENSEAPPLICATION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.5-142.6-1CUMULATIVE NUMBER OF TORNADOES WITHIN VARYING RADII OFPOINT BEACH - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-92.6-2WIND DISTRIBUTION (%) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-102.6-3SITE ATMOSPHERIC STABILITY ANALYSIS ANNUAL AVERAGE - POINT BEACH,WISCONSIN THIRTEEN MONTH DATA - 4/67-4/68 (Sheets 1-3) - - - - - - - - - - - - 2.6-112.6-4SITE ATMOSPHERIC STABILITY ANALYSIS ANNUAL AVERAGE - POINT BEACH, WISCONSIN, THIRTEEN MONTH DATA - 4/67-4/68 (Sheets 1-2)- - - - - - - - - - - - 2.6-142.6-5ATMOSPHERIC STABILITY (%) - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-162.6-6HYPOTHETICAL ACCIDENT METEOROLOGICAL MODEL BASIC ON SITE DATA, 1967 - 1968 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-172.7-1PRE-OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEY FOR THE POINT BEACH NUCLEAR POWER PLANT (Sheets 1-2) - - - - - - - - - - - 2.7-42.8-1BEDROCK FORMATIONS IN EASTERN WISCONSIN - - - - - - - - - - - - - - - - 2.8-33.2-1NUCLEAR DESIGN DATA (Sheets 1-4) - - - - - - - - - - - - - - - - - - - - - - - - 3.2-393.2-2REACTIVITY REQUIRMENTS FOR CONTROL RODS K/K (%) - - - - - - - - - - - 3.2-433.2-3CALCULATED (1) ROD WORTHS, K/K(%) - - - - - - - - - - - - - - - - - - - - - 3.2-443.2-4THERMAL AND HYDRAULIC DESIGN PARAMETERS (Sheets 1-2) - - - - - - - - - 3.2-453.2-5CORE MECHANICAL DESIGN PARAMETERS (1) (Sheets 1-2) - - - - - - - - - - - - - 3.2-473.4-1PROTOTYPE FUEL ASSEMBLY AND RCC ASSEMBLY TESTS - - - - - - - - - - - 3.4-114.1-1REACTOR COOLANT SYSTEM DESIGN PARAMETERS AND PRESSURESETTINGS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.1-154.1-2REACTOR VESSEL DESIGN DATA - - - - - - - - - - - - - - - - - - - - - - - - - - 4.1-16 4.1-3PRESSURIZER AND PRESSURIZER RELIEF TANK DESIGN DATA - - - - - - - - - 4.1-174.1-4STEAM GENERATOR DESIGN DATA (Sheets 1-2) - - - - - - - - - - - - - - - - - - 4.1-184.1-5REACTOR COOLANT PUMPS DESIGN DATA - - - - - - - - - - - - - - - - - - - - 4.1-20 4.1-6REACTOR COOLANT PIPING DESIGN DATA - - - - - - - - - - - - - - - - - - - - 4.1-214.1-7REACTOR COOLANT SYSTEM DESIGN PRESSURE DROP(1) - - - - - - - - - - - - 4.1-224.1-8THERMAL AND LOADING CYCLES - - - - - - - - - - - - - - - - - - - - - - - - - 4.1-23 4.1-9REACTOR COOLANT SYSTEM - CODE REQUIREMENTS - - - - - - - - - - - - - - 4.1-24 List of TablesFSAR UFSAR 2015Page LOT - 2 of 11 4.2-1MATERIALS OF CONSTRUCTION OF THE REACTOR COOLANT SYSTEMCOMPONENTS (Sheets 1-2)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-204.3-1
SUMMARY
OF PRIMARY PLUS SECONDARY STRESS INTENSITY FORCOMPONENTS OF THE REACTOR VESSEL - - - - - - - - - - - - - - - - - - - - - 4.3-54.3-2
SUMMARY
OF CUMULATIVE FATIGUE USAGE FACTORS FOR COMPONENTSOF THE REACTOR VESSEL - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.3-64.3-3STRESSES DUE TO MAXIMUM STEAM GENERATOR TUBESHEET PRESSUREDIFFERENTIAL (2485 PSI) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.3-74.3-4RATIO OF ALLOWABLE STRESSES TO COMPUTED STRESSES FOR A STEAMGENERATOR TUBESHEET PRESSURE DIFFERENTIAL OF 2485 PSI - - - - - - - - - 4.3-84.4-1REACTOR COOLANT SYSTEM NONDESTRUCTIVE EXAMINATION (Sheets 1-3) - - 4.4-95.1-1CONTAINMENTSTRUCTURE
SUMMARY
OFCONCRETEANDREINFORCINGSTEEL STRESSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-6 55.1-1(2A)CONTAINMENTSTRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-6 65.1-1(2B)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-6 75.1-1(2C)CONTAINMENTSTRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-6 85.1-1(3)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES D & F INITIAL (STRESSES IN PSI) CASE I MESH #3 AND #4 - - - 5.1-695.1-1(4A)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES MESH #4 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-7 05.1-1(4B)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES MESH #4 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-7 15.1-1(5)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES MESH #3 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-7 25.1-1(5)CONTAINMENT STRUCTURE
SUMMARY
OF CONCRETE AND REINFORCINGSTEEL STRESSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-7 35.1-2TABLEOFLOADINGCONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - 5.1-7 45.2-1INDEXOFCONTAINMENTPENETRATIONFIGURES (Sheets 1-4) - - - - - - - - - - 5.2-75.3-1PRINCIPAL COMPONENT DATA
SUMMARY
(Pages 1-2) - - - - - - - - - - - - - - - 5.3-65.6-1MATERIALS OF CONSTRUCTION IN REACTOR CONTAINMENT - - - - - - - - - - 5.6-175.6-2UNIT1-INVENTORYOFALUMINUMINCONTAINMENT - - - - - - - - - - - - - 5.6-185.6-2UNIT 2 - INVENTORY OF ALUMINUM IN CONTAINMENT - - - - - - - - - - - - - 5.6-195.6-3CORROSION OF ALUMINUM ALLOYS IN ALKALINE SODIUM BORATESOLUTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5.6-205.6-4CONCRETE SPECIMEN TEST DATA - - - - - - - - - - - - - - - - - - - - - - - - - 5.6-215.6-5EVALUATION OF SEALANT MATERIALS FOR USE IN CONTAINMENT - - - - - - 5.6-226.2-1SAFETY INJECTION SYSTEM - CODE REQUIREMENTS - - - - - - - - - - - - - - - 6.2-306.2-2(DELETED) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-316.2-3ACCUMULATOR DESIGN PARAMETERS - - - - - - - - - - - - - - - - - - - - - - 6.2-32 6.2-4REFUELING WATER STORAGE TANK DESIGN PARAMETERS - - - - - - - - - - - 6.2-336.2-5PUMP PARAMETERS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-34 List of TablesFSAR UFSAR 2015Page LOT - 3 of 11 6.2-6RESIDUAL HEAT EXCHANGERS DESIGN PARAMETERS - - - - - - - - - - - - - - 6.2-356.2-7(a)SINGLEFAILUREANALYSIS-SAFETYINJECTIONSYSTEM - - - - - - - - - - - - 6.2-366.2-7(b)LOSS OF RECIRCULATION FLOW PATH - - - - - - - - - - - - - - - - - - - - - - - 6.2-37 6.2-8SHARED FUNCTIONS EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-386.2-9ACCUMULATORINLEAKAGE* - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-396.2-10RESIDUAL HEAT REMOVAL SYSTEM DESIGN, OPERATION AND TESTCONDITIONS- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.2-406.2-11SAFETY RELATED SNUBBERS UNIT1 - - - - - - - - - - - - - - - - - - - - - - - - 6.2-416.2-11SAFETY RELATED SNUBBERS UNIT2 - - - - - - - - - - - - - - - - - - - - - - - - 6.2-42 6.3-1SINGLEFAILUREANALYSIS-CONTAINMENTAIR RECIRCULATIONCOOLINGSYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.3-156.3-2SHARED FUNCTION EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - 6.3-166.4-1CONTAINMENT SPRAY SYSTEM-CODE REQUIREMENTS - - - - - - - - - - - - - 6.4-156.4-2CONTAINMENT SPRAY PUMP DESIGN PARAMETERS - - - - - - - - - - - - - - - 6.4-16 6.4-3SPRAY ADDITIVE TANK DESIGN PARAMETERS - - - - - - - - - - - - - - - - - - 6.4-176.4-4EXPOSURE CONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-186.4-5COMPONENT MATERIALS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-19 6.4-6CORROSION RATES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-2 06.4-7SINGLE FAILURE ANALYSIS - CONTAINMENT SPRAY SYSTEM - - - - - - - - - - 6.4-216.4-8SHARED FUNCTIONS EVALUATION - - - - - - - - - - - - - - - - - - - - - - - - - 6.4-22 7.2-1LIST OF REACTOR TRIPS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-307.2-2INTERLOCKCIRCUITS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.2-317.2-3RPS/ESFAS PRIMARYANDSECONDARYINSTRUMENTATION - - - - - - - - - - 7.2-32 7.3-1LISTOFENGINEEREDSAFETYFEATURESACTUATIONSIGNALS (Sheets 1-3) - - 7.3-157.3-2GENERAL OPERATING TIME REQUIREMENTS FOR ENVIRONMENTALQUALIFICATION OF ELECTRICAL EQUIPMENT (Sheets 1-3)- - - - - - - - - - - - - 7.3-187.5-1UNITS1AND2ASIPINSTRUMENTATION,CONTROLS,ANDINDICATION - - - - 7.5-147.6-1POST-ACCIDENT MONITORING VARIABLES (Sheets 1-5) - - - - - - - - - - - - - - 7.6-167.7-1RODSTOPS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7.7-168.5-1ASSOCIATED 480 VOLT SOURCES - - - - - - - - - - - - - - - - - - - - - - - - - - 8.5-48.8-1EMERGENCY DIESEL GENERATOR LOADING FOLLOWING A LOSS OFCOOLANT ACCIDENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8.8-109.1-1COMPONENT COOLING SYSTEMCOMPONENTDATA - - - - - - - - - - - - - - - 9.1-99.1-2FAILUREANALYSISOFPUMPS,HEATEXCHANGERS,ANDVALVES - - - - - - - 9.1-109.2-1RESIDUAL HEAT REMOVAL LOOP COMPONENT DATA - - - - - - - - - - - - - - - 9.2-69.3-1CHEMICAL AND VOLUME CONTROL SYSTEM CODE REQUIREMENTS - - - - - - 9.3-23 9.3-2CHEMICAL AND VOLUME CONTROL SYSTEM PERFORMANCE REQUIREMENTS* 9.3-249.3-3PRINCIPAL COMPONENT DATA
SUMMARY
- - - - - - - - - - - - - - - - - - - - 9.3-259.3-4PARAMETERS USED IN THE CALCULATION OF REACTOR COOLANT FISSIONPRODUCT ACTIVITIES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 9.3-269.3-5REACTOR COOLANT SYSTEM EQUILIBRIUM ACTIVITIES - - - - - - - - - - - - - 9.3-279.3-6TRITIUM PRODUCTION IN THE REACTOR COOLANT ONE UNIT - - - - - - - - - 9.3-28 List of TablesFSAR UFSAR 2015Page LOT - 4 of 11 9.3-7MALFUNCTION ANALYSIS OF CHEMICAL AND VOLUME CONTROL SYSTEM - - 9.3-299.4-1FUELHANDLINGDATA - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 9.4-139.6-1ESSENTIAL SERVICE WATER LOADS - - - - - - - - - - - - - - - - - - - - - - - - 9.6-6 9.6-2NON-ESSENTIAL LOAD ISOLATION VALVES - - - - - - - - - - - - - - - - - - - - 9.6-79.6-3ESSENTIAL SW AUTOMATIC VALVES - - - - - - - - - - - - - - - - - - - - - - - - 9.6-89.9-1SPENTFUELPOOLCOOLINGSYSTEMCOMPONENTDATA* (Sheets 1 to 4) - - - - 9.9-8 9.11-1SAMPLINGSYSTEMCODEREQUIREMENTS - - - - - - - - - - - - - - - - - - - - 9.11-79.11-2SAMPLINGSYSTEMCOMPONENTS (Sheets 1-2) - - - - - - - - - - - - - - - - - - - 9.11-810.1-1STEAMANDPOWERCONVERSIONSYSTEMCOMPONENTDESIGNPARAMETERS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 10.1-1 710.1-2STEAMANDPOWERCONVERSIONSYSTEMCODEREQUIREMENTS - - - - - - - 10.1-1810.1-3AVTCONTROL,SECONDARYCHEMISTRYCONTROLGUIDELINES(1)(Sheets 1 to 2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 10.1-1910.1-4STEAMANDPOWERCONVERSIONSYSTEM SINGLE FAILURE ANALYSIS - - - - 10.1-2110.2-1AFW SYSTEM LEVEL FAILURE MODES AND EFFECTS ANALYSIS- - - - - - - - - 10.2-1111.0-1WASTE DISPOSAL QUANTITIES - - - - - - - - - - - - - - - - - - - - - - - - - - - 11.0-211.0-2WASTE DISPOSAL SYSTEM COMPONENT
SUMMARY
DATA - - - - - - - - - - - 11.0-311.1-1COMPONENT DESIGN DATA FOR RADIOACTIVE LIQUID TREATMENT(Also See Table 11.0-2) (Sheets 1-6) - - - - - - - - - - - - - - - - - - - - - - - - - - - 11.1-811.1-2ESTIMATED LIQUID DISCHARGE TO WASTE DISPOSAL - - - - - - - - - - - - - - 11.1-1411.1-3ESTIMATED LIQUID RELEASE BY ISOTOPE (TWO UNITS) - - - - - - - - - - - - - 11.1-15 11.1-4ACTIVITYFROMSTEAMGENERATORBLOWDOWN WITHOUT ANDWITH PROCESSING (Historical) - - - - - - - - - - - - - - - - - - - - - - - - - - - - 11.1-1611.2-1COMPONENT DESIGN DATA FOR RADIOACTIVE GAS TREATMENT (Sheets 1-8) - 11.2-1011.2-2ESTIMATEDANNUALGASEOUSRELEASE BYISOTOPE(TWOUNITS) - - - - - - 11.2-1811.2-3GASTREATMENTSYSTEMMALFUNCTIONANALYSIS - - - - - - - - - - - - - - 11.2-1911.2-4GAS DECAY TANK ACCIDENT ANALYSIS INPUT PARAMETERS - - - - - - - - - 11.2-20 11.2-5VOLUME CONTROL TANK ACCIDENT ANALYSIS INPUT PARAMETERS - - - - - 11.2-2111.2-6CHARCOAL FILLED DELAY TANK ACCIDENT ANALYSIS INPUT PARAMETERS - 11.2-2211.2-7CALCULATED DOSES FOR GDT, VCT, AND CDT RUPTURES - - - - - - - - - - - - 11.2-23 11.4-1STORAGE LOCATION OF EQUIPMENT - - - - - - - - - - - - - - - - - - - - - - - - 11.4-1211.4-2RADIATION PROTECTION EQUIPMENT - - - - - - - - - - - - - - - - - - - - - - - 11.4-1311.4-3RADIATION PROTECTION AND RADIOCHEMICAL FACILITIES - - - - - - - - - - 11.4-1411.5-1ARADIATION MONITORING SYSTEM AREA MONITORS (Sheets 1-3) - - - - - - - - - 11.5-1111.5-1BRADIATION MONITORING SYSTEM AREA MONITORS (Sheets 1-2) - - - - - - - - - 11.5-1411.5-2ARADIATION MONITORING SYSTEM PROCESS MONITORS (Sheets 1-5) - - - - - - - 11.5-16 11.5-2BRADIATIONMONITORINGSYSTEM PROCESSMONITORS (Sheets 1-3) - - - - - - - 11.5-2111.5-3RADIATIONMONITORINGSYSTEM SPECIAL PARTICULATE IODINE AND NOBLE GASMONITORS SPINGS(Sheets 1-2)- - - - - - - - - - - - - - - - - - - - - - - - - - 11.5-2411.6-1SHIELDING DESIGN ZONE CLASSIFICATIONS - - - - - - - - - - - - - - - - - - - 11.6-1311.6-2ORIGINAL PRIMARY SHIELD NEUTRON FLUXES AND DESIGNPARAMETERS (Historical) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 11.6-1411.6-3ORIGINAL SECONDARY SHIELD DESIGN PARAMETERS (Historical) - - - - - - - - 11.6-15 List of TablesFSAR UFSAR 2015Page LOT - 5 of 11 11.6-4ORIGINAL ACCIDENT SHIELD DESIGN PARAMETERS (Historical) - - - - - - - - - 11.6-1611.6-5ORIGINAL PRINCIPAL AUXILIARY SHIELDING (Historical) - - - - - - - - - - - - - 11.6-1711.6-6ORIGINAL RESIDUALHEATREMOVALSYSTEMRADIATION SOURCES ANDEVALUATION PARAMETERS (Historical) - - - - - - - - - - - - - - - - - - - - - - - 11.6-1812.4-1EMERGENCYOPERATINGPROCEDURES(EOPs) EMERGENCY CONTINGENCYACTIONS (ECAs) (Pages 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 12.4-412.4-2STATUSTREES(STS) CRITICALSAFETYPROCEDURES(CSPS) (Page) 2 - - - - - - 12.4-513.2-1PREOPERATIONALTESTS (Sheets 1-7) - - - - - - - - - - - - - - - - - - - - - - - - 13.2-1314.0-1
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED (Pages 1-2) - 14.0-914.0-2NOMINAL VALUES OF PERTINENT PLANT PARAMETERS FOR NON-LOCAACCIDENT ANALYSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.0-1114.0-3TRIP POINTS AND TIME DELAYS TO TRIP ASSUMED IN ACCIDENTANALYSES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.0-1214.1.1-1TIME SEQUENCE OF EVENTS FOR UNCONTROLLED RCCA WITHDRAWALFROM A SUBCRITICAL CONDITION - - - - - - - - - - - - - - - - - - - - - - - - - 14.1.1-514.1.2-1TIME SEQUENCE OF EVENTS FOR UNCONTROLLED RCCA WITHDRAWALAT POWER (maximum nominal RCS Tavg; Minimum Feedback) - - - - - - - - - - - - - 14.1.2-614.1.7-1TIME SEQUENCE OF EVENTS FOR EXCESSIVE LOAD INCREASE INCIDENT - - - - 14.1.7-314.1.8-1LOSS OF FORCED REACTOR COOLANT FLOW TIME SEQUENCE OF EVENTS - - - - 14.1.8-914.1.8-2
SUMMARY
OF LIMITING RESULTS FOR LOCKED ROTOR ACCIDENT - - - - - - - - 14.1.8-1014.1.8-3ASSUMPTIONS USED FOR DOSE ANALYSES - - - - - - - - - - - - - - - - - - - - - 14.1.8-1114.1.8-4ASSUMPTIONS USEDFOR DOSE ANALYSES - - - - - - - - - - - - - - - - - - - - - 14.1.8-1214.1.8-5ASSUMPTIONS USEDFOR DOSE ANALYSES (Pages 1-2) - - - - - - - - - - - - - - - 14.1.8-1314.1.8-6CONTROL ROOM PARAMETERS USED FOR DOSE ANALYSES - - - - - - - - - - - - 14.1.8-1514.1.9-1TIME SEQUENCE OF EVENTS FOR LOSS OF EXTERNAL ELECTRICAL LOAD - - - - 14.1.9-414.1.9-2MSSV CHARACTERISTICS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.1.9-514.1.10-1TIME SEQUENCE OF EVENTS FOR LOSS OF NORMAL FEEDWATER FLOW INCIDENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.1.10-414.1.11-1TIME SEQUENCE OF EVENTS FOR LOSS OF OFFSITE POWER INCIDENTS* - - - - - 14.1.11-414.2.1-1ACTIVITY IN AN AVERAGE FUEL ASSEMBLY AT 65HOURS POST SHUTDOWN - - 14.2.1-714.2.1-2ASSUMPTIONS USED FOR THE FHA DOSE ANALYSIS - - - - - - - - - - - - - - - - 14.2.1-814.2.4-1STEAM GENERATOR TUBE RUPTURE ACCIDENT DOSES - - - - - - - - - - - - - - 14.2.4-814.2.4-2MASS TRANSFER USED FOR SGTR DOSE ANALYSES- - - - - - - - - - - - - - - - 14.2.4-914.2.5-1MAIN STEAMLINE BREAK ACCIDENT DOSES- - - - - - - - - - - - - - - - - - - - 14.2.5-1414.2.5-2RUPTURE OF A STEAM PIPE ANALYSIS ASSUMPTIONS AND SEQUENCE OFEVENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.2.5-1514.2.5-3GOTHIC MODEL INPUTS MSLB CONTAINMENT RESPONSE ANALYSIS - - - - - - - 14.2.5-1614.2.6-1PARAMETERS USED IN THE ANALYSIS OF THE ROD CLUSTER CONTROLASSEMBLY EJECTION ACCIDENT - - - - - - - - - - - - - - - - - - - - - - - - - - 14.2.6-1014.2.6-2ASSUMPTIONS USED FOR CONTROL ROD EJECTION ACCIDENT ANALYSIS - - - - 14.2.6-1114.2.6-3DOSES DUE TO THE RADIOACTIVITY RELEASED DURING THECONTROL ROD EJECTION ACCIDENT - - - - - - - - - - - - - - - - - - - - - - - - 14.2.6-1214.3.1-1INPUT ASSUMPTIONS USED IN THE SMALL BREAK ANALYSIS - - - - - - - - - - - 14.3.1-614.3.1-2AHHSI FLOWS WITH THE FAULTED LOOP SPILLING TO RCS PRESSURE - - - - - - - 14.3.1-7 List of TablesFSAR UFSAR 2015Page LOT - 6 of 11 14.3.1-2BHHSI FLOWS WITH THE FAULTED LOOP SPILLING TO CONTAINMENT PRESSURE14.3.1-814.3.1-2CLHSI FLOWS INJECTING TO RCS PRESSURE- - - - - - - - - - - - - - - - - - - - - 14.3.1-914.3.1-3ATIME SEQUENCE OF EVENTS FOR UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - 14.3.1-1014.3.1-3BTIME SEQUENCE OF EVENTS FOR UNIT 2 - - - - - - - - - - - - - - - - - - - - - - 14.3.1-11 14.3.1-4ASBLOCTA BOL RESULTS FOR UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - 14.3.1-12 14.3.1-4BSBLOCTA BOL RESULTS FOR UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - 14.3.1-1314.3.2-1PLANT OPERATING RANGE ANALYZED BY THE BEST-ESTIMATE LARGEBREAK LOCA ANALYSIS (Sheets 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.2-1014.3.2-2LARGE BREAK LOCA CONTAINMENT DATA USED FOR CALCULATION OFCONTAINMENT PRESSURE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.2-1214.3.2-3CONTAINMENT FAN COOLER HEAT REMOVAL RATE FOR ECCS CONTAINMENTBACKPRESSURE ANALYSIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.2-1314.3.2-4STRUCTURAL HEAT SINK DATA FOR ECCS CONTAINMENT BACKPRESSUREANALYSIS (Sheets 1 to 4) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.2-1414.3.2-5PEAK CLAD TEMPERATURE INCLUDING ALL PENALTIES AND BENEFITS,BEST-ESTIMATE LARGE BREAK LOCA (BE LBLOCA) UNIT 1 - - - - - - - - - - - 14.3.2-18 14.3.2-6UNIT 1 BEST-ESTIMATE LARGE BREAK LOCA RESULTS - - - - - - - - - - - - - - 14.3.2-1914.3.2-7PEAK CLAD TEMPERATURE INCLUDING ALL PENALTIES AND BENEFITS,BEST-ESTIMATE LARGE BREAK LOCA (BE LBLOCA) UNIT 2 - - - - - - - - - - - 14.3.2-2014.3.2-8UNIT 2 BEST-ESTIMATE LARGE BREAK LOCA RESULTS- - - - - - - - - - - - - - 14.3.2-2114.3.2-9INJECTED SAFETY INJECTION FLOW USED IN BEST-ESTIMATE LARGE-BREAKLOCA ANALYSIS FOR UNITS 1 AND 2 - - - - - - - - - - - - - - - - - - - - - - - - 14.3.2-2214.3.3-1MULTI-MASSVIBRATIONALMODEL-DEFINITIONOFSYMBOLS - - - - - - - - - - 14.3.3-714.3.4-1SYSTEM PARAMETERS INITIAL CONDITIONS - - - - - - - - - - - - - - - - - - - - 14.3.4-2 514.3.4-2SAFETY INJECTION FLOW - MINIMUM SAFEGUARDS - - - - - - - - - - - - - - - - 14.3.4-2 614.3.4-3SAFETY INJECTION FLOW - MAXIMUM SAFEGUARDS - - - - - - - - - - - - - - - - 14.3.4-2 714.3.4-4LOCA MASS AND ENERGY RELEASE ANALYSIS - CORE DECAY HEATFRACTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-2 814.3.4-5DEHL BREAK BLOWDOWN M&E RELEAASE (Sheets 1-3) - - - - - - - - - - - - - - - 14.3.4-2 914.3.4-6DEHL BREAK MASS BALANCE- - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-3 214.3.4-7DEHL BREAK ENERGY BALANCE - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-3 314.3.4-8DEPS BREAK BLOWDOWN M&E RELEASE (MINIMUM AND MAXIMUMSAFEGUARDS (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-3 414.3.4-9DEPS BREAK REFLOOD M&E RELEASE - MINIMUM SI (Sheets 1-5) - - - - - - - - - 14.3.4-3 714.3.4-10DEPS BREAK REFLOOD M&E RELEASE - MAXIMUM SI (Sheets 1-4) - - - - - - - - 14.3.4-4 214.3.4-11DEPS - MINIMUM SAFETY INJECTION PRINCIPAL PARAMETERS DURINGREFLOOD (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-4 614.3.4-12DEPS - MAXIMUM SAFETY INJECTION PRINCIPAL PARAMETERS DURINGREFLOOD (Sheets 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-4 914.3.4-13DEPS BREAK POST-REFLOOD M&E RELEASE - MINIMUM SI (Sheets 1-4)- - - - - - 14.3.4-5 114.3.4-14DEPS BREAK POST-REFLOOD M&E RELEASE - MAXIMUM SI (Sheets 1-3) - - - - - 14.3.4-5 514.3.4-15DEPS BREAK MASS BALANCE MINIMUM SAFEGUARDS- - - - - - - - - - - - - - 14.3.4-5 814.3.4-16DEPS BREAK MASS BALANCE MAXIMUM SAFEGUARDS - - - - - - - - - - - - - 14.3.4-5 914.3.4-17DEPS BREAK ENERGY BALANCE MINIMUM SAFEGUARDS - - - - - - - - - - - - 14.3.4-6014.3.4-18DEPS BREAK ENERGY BALANCE MAXIMUM SAFEGUARDS- - - - - - - - - - - - 14.3.4-6 114.3.4-19DOUBLE-ENDED HOT LEG BREAK SEQUENCE OF EVENTS - - - - - - - - - - - - 14.3.4-6 2
List of TablesFSAR UFSAR 2015Page LOT - 7 of 11 14.3.4-20DOUBLE-ENDED PUMP SUCTION BREAK SEQUENCE OF EVENTS(MINIMUM SAFEGUARDS) (Sheets 1-2) - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-6 314.3.4-21DOUBLE-ENDED PUMP SUCTION BREAK SEQUENCE OF EVENTS(MAXIMUM SAFEGUARDS) (Sheets 1-2)- - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-6 514.3.4-22RCS CONDITIONS FOR SHORT-TERM MASS AND ENERGY RELEASES- - - - - - - 14.3.4-6 714.3.4-23SHORT-TERM LOCA M&E RELEASES- - - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-6 814.3.4-24CONTAINMENT INTEGRITY LOCA ANALYSIS PARAMETERS (Sheets 1-2) - - - - - 14.3.4-6 914.3.4-25CONTAINMENT FAN COOLER PERFORMANCE - - - - - - - - - - - - - - - - - - - 14.3.4-7 114.3.4-26CONTAINMENT SPRAY PERFORMANCE - - - - - - - - - - - - - - - - - - - - - - - 14.3.4-7 214.3.4-27CONTAINMENT STRUCTURAL HEAT SINK INPUT (Sheets 1-7)- - - - - - - - - - - - 14.3.4-7 314.3.4-28MATERIAL PROPERTIES FOR CONTAINMENT STRUCTURAL HEAT SINKS- - - - - 14.3.4-8014.3.4-29
SUMMARY
OF PEAK CONTAINMENT PRESSURE AND TEMPERATURES- - - - - - 14.3.4-8 114.3.5-1CORE ACTIVITIES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-814.3.5-2DOSE CONVERSION FACTORS, BREATHING RATES, AND ATMOSPHERICDISPERSION FACTORS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-914.3.5-2ACOMMITTED EFFECTIVE DOSE EQUIVALENT DOSE CONVERSION FACTORS(Pages 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-1014.3.5-2BEFFECTIVE DOSE EQUIVALENT DOSE CONVERSION FACTORS(Pages 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-1214.3.5-3CONTROL ROOM PARAMETERS - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-1414.3.5-4ASSUMPTIONS USED FOR LARGE BREAK LOCA DOSE ANALYSISCONTAINMENT LEAKAGE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-1514.3.5-5ASSUMPTIONS USED FOR LARGE BREAK LOCA DOSE ANALYSISECCS EQUIPMENT LEAKAGE - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14.3.5-1614.3.5-6LARGE BREAK OFFSITE AND CONTROL ROOM DOSES - - - - - - - - - - - - - - - 14.3.5-17A.2-1JET IMPINGEMENT FORCES ON CABLE SPREADING ROOM WALLS - - - - - - - A.2-15 A.2-2JET IMPINGEMENT FORCES (VARIOUS LOCATIONS) - - - - - - - - - - - - - - - - A.2-16A.2-3MASS AND ENERGY USED IN JET IMPINGEMENT AND PIPE WHIP - - - - - - - - A.2-17A.2-4LIST OF CREDITED PROTECTION FEATURES FOR JET IMPINGEMENTAND PIPE WHIP - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.2-18A.5-1INTERNALS DEFLECTIONS UNDER ABNORMAL OPERATION (INCHES)- - - - - - A.5-23A.5-2DAMPING FACTORS- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.5-2 4A.5-3LOADING CONDITIONS AND STRESS LIMITS (Sheets 1-4) - - - - - - - - - - - - - - A.5-25A.6-1SHARED SYSTEMS ANALYSIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.6-2A.7-1DESIGN FEATURES CREDITED FOR MITIGATING INTERNAL PLANT FLOODING (Pages 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.7-5A.7-2DESIGN FEATURES CREDITED FOR MITIGATING EXTERNAL PLANTFLOODING (Pages 1-2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A.7-8B.2-1COMPARISON OF DESIGN PARAMETERS - - - - - - - - - - - - - - - - - - - - - - B.2-3I.2-1SOURCES AND EXPECTED RADIOACTIVITY OF LIQUID WASTES AT POINTBEACH NUCLEAR PLANT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 of 248I.2-2CAPACITIES USED IN CALCULATING HOLDUP TIMES FOR RADIOACTIVELIQUIDS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 of 248I.2-3CALCULATED HOLDUP TIMES FOR COLLECTION, PROCESSING AND RELEASE - 3 of 248I.2-4POINT BEACH NUCLER PLANT RELEASE POINT DESCRIPTIONS (Sheets 1-3) - - - 4 of 248 List of TablesFSAR UFSAR 2015Page LOT - 8 of 11 I.3-1COMPARISONS WITH PARAMETERS USED TO DESCRIBE THE REFERENCEPRESSURIZED WATER REACTOR WITH U-TUBE STEAM GENERATORS - - - - - 7 of 248I.3-2POINT BEACH NUCLEAR PLANT CALCULATED SOURCE TERM CONCENTRATIONS (Ci/gm) (Sheets 1 to 3) - - - - - - - - - - - - - - - - - - - - - - 8 of 248I.3-3POINT BEACH NUCLEAR PLANT CALCULATED SOURCE TERMACTIVITIES (Ci) (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 11 of 24 8I.4-1POINT BEACH NUCLEAR PLANT ON-SITE WIND ROSE FOR 4/19/67 TO 4/18/69(FREQUENCY PERCENT) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 14 of 248I.4-2POINT BEACH NUCLEAR PLANT
SUMMARY
OF ANNUAL AND GRAZINGSEASON /Q's AND /Q's FOR HIGHEST OFFSITE SECTORS - - - - - - - - - - - - 15 of 248I.4-3POINT BEACH NUCLEAR PLANT ANNUAL GROWING SEASON Q's AND/Q's FOR ONSITE RESIDENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - 16 of 248 I.4-4POINT BEACH NUCLEAR PLANT AUXILIARY BUILDING VENT, CONTINUOUSELEVATED RELEASE (IA) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 17 of 248I.4-5POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /QAUXILIARY BUILDING VENT, CONTINUOUS ELEVATED RELEASE (IA)- - - - - - 18 of 248I.4-6POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q AUXILIARYBUILDING VENT, INTERMITTENT ELEVATED RELEASE (IB) - - - - - - - - - - - 19 of 248I.4-7POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /QAUXILIARY BUILDING VENT, INTERMITTENT ELEVATED RELEASE (IB) - - - - 20 of 248I.4-8POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, UNIT 1 OR UNIT 2CONTAINMENT PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIA) AND GAS STRIPPER BUILDING VIA UNIT 2 CONTAINMENT PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIC) - - - - - - - - - - - - - - - - - - - 21 of 248I.4-9POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S, UNIT 1OR UNIT 2 CONTAINMENT PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIA) AND GAS STRIPPER BUILDING VIA UNIT 2 CONTAINMENT PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIC) - - - - - - - - - - - 22 of 248I.4-10POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, UNIT 1 OR UNIT 2CONTAINMENT PURGE VENT, INTERMITTENT RELEASE (IIB) - - - - - - - - - - 23 of 248I.4-11POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S, UNIT 1 ORUNIT 2 CONTAINMENT PURGE VENT, INTERMITTENT RELEASE (IIB) - - - - - - 24 of 248I.4-12POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, TURBINE BUILDINGROOF EXHAUSTERS, CONTINUOUS GROUND LEVEL RELEASE (III) - - - - - - - 25 of 248I.4-13GROWING/GRAZING SEASON /Q'S, TURBINE BUILDING ROOF EXHAUSTERS,CONTINUOUS GROUND LEVEL RELEASE (III) - - - - - - - - - - - - - - - - - - - 26 of 248I.4-14POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, AUXILIARYBUILDING VENT, CONTINUOUS ELEVATED RELEASE (IA) - - - - - - - - - - - - 27 of 248I.4-15POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S,AUXILIARY BUILDING VENT, CONTINUOUS ELEVATED RELEASE (IA) - - - - - 28 of 248I.4-16POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, AUXILIARYBUILDING VENT, INTERMITTENT ELEVATED RELEASE (IB) - - - - - - - - - - - - 29 of 248I.4-17POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S,AUXILIARY BUILDING VENT, INTERMITTENT ELEVATED RELEASE (IB) - - - - 30 of 248 List of TablesFSAR UFSAR 2015Page LOT - 9 of 11 I.4-18POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, UNIT 1 ORUNIT 2 PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIA), GAS STRIPPER BUILDING VIA UNIT 2 PURGE VENT, CONTINUOUS GROUND LEVELRELEASE (IIC), AND TURBINE BUILDING ROOF EXHAUSTERS, CONTINUOUS GROUND LEVEL RELEASE (III) - - - - - - - - - - - - - - - - - - - - - - - - - - - 31 of 248I.4-19POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S,UNIT 1 OR UNIT 2 PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIA),
GAS STRIPPER BUILDING VIA UNIT 2 PURGE VENT, CONTINUOUS GROUND LEVEL RELEASE (IIC), AND TURBINE BUILDING ROOF EXHAUSTERS, CONTINUOUS GROUND LEVEL RELEASE (III) - - - - - - - - - - - - - - - - - - - 32 of 248I.4-20POINT BEACH NUCLEAR PLANT ANNUAL AVERAGE /Q'S, UNIT 1 OR UNIT 2CONTAINMENT PURGE VENT, INTERMITTENT RELEASE (IIB) - - - - - - - - - - 33 of 248I.4-21POINT BEACH NUCLEAR PLANT GROWING/GRAZING SEASON /Q'S, UNIT 1OR UNIT 2 CONTAINMENT PURGE VENT, INTERMITTENT ELEVATEDRELEASE (IIB) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 34 of 248I.4-22POINT BEACH NUCLEAR PLANT PERCENTAGE FREQUENCY DISTRIBUTION OFPASQUILL STABILITY CLASS FOR POINT BEACH, HAVEN, AND MILWAUKEE - - 35 of 248I.4-23POINT BEACH NUCLEAR PLANT PERCENTAGE FREQUENCY DISTRIBUTION OFWIND DIRECTION FOR POINT BEACH, HAVEN, AND MILWAUKEE - - - - - - - - 36 of 248I.4-24POINT BEACH NUCLEAR PLANT WIND SPEED BY QUADRANT FORPOINT BEACH, HAVEN, AND MILWAUKEE - - - - - - - - - - - - - - - - - - - - - 37 of 248I.4-25POINT BEACH NUCLEAR PLANT WIND-PRECIPITATION (FREQUENCYPERCENT)
SUMMARY
FOR 1/1/56 - 12/31/75 AT MILWAUKEE - - - - - - - - - - - 38 of 248I.4-26POINT BEACH NUCLEAR PLANT AVERAGE PRECIPITATION FOR WEATHERSTATIONS IN THE VICINITY OF POINT BEACH NUCLEAR PLANT - - - - - - - - - 39 of 248I.4-27POINT BEACH NUCLEAR PLANT MONTHLY PRECIPITATION TOTALS ANDINTENSITY FREQUNCY DISTRIBUTIONS AT GREEN BAY, WISCONSINAPRIL 19, 1967 THROUGH APRIL 18, 1969 - - - - - - - - - - - - - - - - - - - - - - 40 of 248I.4-28HAVEN JOINT FREQUENCY DISTRIBUTION ANNUAL
SUMMARY
6/1/73THROUGH 5/31/74 HAVEN SITE WIND - STABILITY
SUMMARY
STABILITY CLASS - A - METER WINDS, PERIOD 6/1/73 TO 5/31/74 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 41 of 248I.4-29MILWAUKEE JOINT FREQUENCY DISTRIBUTION ANNUAL
SUMMARY
6/1/73THROUGH 5/31/74 MILWAUKEE WIND - STABILITY
SUMMARY
STABILITY CLASS - A - ANNUAL 6/1/73 TO 5/31/74 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 49 of 248I.4-30MILWAUKEE JOINT FREQUENCY DISTRIBUTION TWO-YEAR
SUMMARY
4/19/67THROUGH 4/18/69 MILWAUKEE WIND - STABILITY
SUMMARY
STABILITY CLASS - A - ANNUAL 4/19/67 TO 4/18/69 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 57 of 248I.4-31MILWAUKEE JOINT FREQUENCY DISTRIBUTION TEN YEAR
SUMMARY
1/1/56THROUGH 12/31/75 MILWAUKEE WIND - STABILITY
SUMMARY
STABILITY CLASS - A - ANNUAL 1/1/56 TO 12/31/75 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 65 of 248I.4-32POINT BEACH JOINT FREQUENCY DISTRIBUTION TWO-YEAR
SUMMARY
, 4/19/67 THROUGH 4/18/69 POINT BEACH WIND - STABILITY
SUMMARY
STABILITY CLASS - A - 150 FT WINDS, PERIOD 4/19/67 TO 4/18/69 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 73 of 248 List of TablesFSAR UFSAR 2015Page LOT - 10 of 11 I.4-33POINT BEACH JOINT FREQUENCY DISTRIBUTION BY MONTH FOR THE PERIOD4/19/67 THROUGH 4/18/69 POINT BEACH WIND - STABILITY
SUMMARY
STABILITY CLASS - A - 150 FT WINDS, (JAN) PERIOD 1/1/68 TO 1/31/69 NUMBER OF HOURLY OBSERVATIONS (Sheets 1-96) - - - - - - - - - - - - - - - - - - - - - - - - - - - - 81 of 248I.6-1POINT BEACH NUCLEAR PLANT NEAREST SITE BOUNDARY (METERS) - - - - - - - -177 of 248 I.6-2POINT BEACH NUCLEAR PLANT DISTANCE TO NEAREST RESIDENCE ANDNEAREST VEGETABLE GARDEN IN SEARCH SECTOR (1) - - - - - - - - - - - - - - - - - - - - 178 of 248I.6-3POINT BEACH NUCLEAR PLANT DISTANCE TO NEAREST MILK COW,MEAT ANIMAL AND MILK GOAT IN EACH SECTOR (1) - - - - - - - - - - - - - - - - - - - - - -179 of 248I.6-4POINT BEACH NUCLEAR PLANT CONTAINMENT PURGE
SUMMARY
(1) - - - - - - - -180 of 248I.6-5POINT BEACH NUCLEAR PLANT GAS DECAY TANK RELEASES (1974-1975) - - - - - 182 of 248I.7 -1POINT BEACH NUCLEAR PLANT CALCULATED TOTAL ANNUAL GASEOUSRELEASES (Ci/yr) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 183 of 24 8I.7-2POINT BEACH NUCLEAR PLANT TOTAL LIQUID RELEASES PERPALNT - CALCULATED(1) (Sheets 1 to 3)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 185 of 248I.7-3POINT BEACH NUCLEAR PLANT CALCULATED ANNUAL RELEASES BYSOURCE (Ci/yr) (Sheets 1 to 3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 88 of 248I.7-4POINT BEACH NUCLEAR PLANT AIRBORNE RELEASES (1974-1975) (Ci/yr)(Sheets 1 to 2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 191 of 248I.7-5POINT BEACH NUCLEAR PLANT OBSERVED MONTHLY GASEOUS RELEASESBY RELEASE POINT (Sheets 1 to 24)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 193 of 248I.7-6POINT BEACH NUCLEAR PLANT LIQUID RELEASES (1974-1975) (Ci/yr)(Sheets 1 to 3)- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 217 of 248I.7-7POINT BEACH NUCLEAR PLANT PARAMETERS FOR RADIOACTIVE GASEOUSRELEASES (Sheets 1 to 2) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 220 of 248I.8-1POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN ADULT GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 222 of 248I.8-2POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN TEEN GROUP FROM RADIOIODINE AND PARTICULATES IN GASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 223 of 248I.8-3POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN CHILD GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 224 of 248I.8-4POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN INFANT GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 225 of 248I.8-5POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM INDIVIDUALFROM NOBLE GASES IN GASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - 226 of 248I.8-6POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN ADULT AGE GROUP FROM LIQUID EFFLUENTS UNDER EQUILIBRIUM CONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 227 of 248I.8-7POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN TEEN AGE GROUP FROM LIQUID EFFLUENTS UNDEREQUILIBRIUM CONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 228 of 248I.8-8POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN CHILD AGE GROUP FROM LIQUID EFFLUENTS UNDEREQUILIBRIUM CONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 229 of 248 List of TablesFSAR UFSAR 2015Page LOT - 11 of 11 I.8-9POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM OFFSITEINDIVIDUAL IN INFANT AGE GROUP FROM LIQUID EFFLUENTS UNDEREQUILIBRIUM CONDITIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 230 of 248I.8-10POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM ONSITEINDIVIDUAL IN ADULT GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 231 of 248I.8-11POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM ONSITEINDIVIDUAL IN TEEN GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 232 of 248I.8-12POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM ONSITEINDIVIDUAL IN CHILD GROUP FROM RADIOIODINE AND PARTICULATES INGASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 233 of 248I.8-13POINT BEACH NUCLEAR PLANT ANNUAL DOSES TO MAXIMUM ONSITEINDIVIDUAL IN INFANT GROUP FROM RADIOIODINE AND PARTICULATES IN GASEOUS EFFLUENTS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 234 of 248I.9-1COMPARISON OF MAXIMUM CALCULATED DOSES FROM POINT BEACHNUCLEAR PLANT WITH DESIGN OBJECTIVES IN DOCKET RM-50-2 (1)- - - - - - - - 235 of 248 List of FiguresFSAR UFSAR 2015Page LOF - 1 of 16 FSAR LIST OF FIGURESFigureTitle1.2-1CONTAINMENT LAYOUT PLAN EQUIPMENT ARRANGEMENT - - - - - - - - - -1.2-61.2-2EQUIPMENT LOCATION PLAN UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - -1.2-71.2-3EQUIPMENT LOCATION PLAN UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - -1.2-81.2-4UNIT-1 EQUIPMENT LOCATION PLAN - - - - - - - - - - - - - - - - - - - - - - - -1.2-9 1.2-5UNIT-1 EQUIPMENT LOCATION PLAN - - - - - - - - - - - - - - - - - - - - - - - -1.2-101.2-6EQUIPMENT LOCATION PLAN - - - - - - - - - - - - - - - - - - - - - - - - - - - -1.2-111.2-7UNIT 1 EQUIPMENT LOCATION - SECTIONS - - - - - - - - - - - - - - - - - - - -1.2-12 1.2-8MISCELLANEOUS SECTIONS UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - -1.2-13 1.2-9UNIT-2 EQUIPMENT LOCATION - PLAN - - - - - - - - - - - - - - - - - - - - - - -1.2-141.2-10EQUIPMENT LOCATION PLAN UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - -1.2-151.2-11EQUIPMENT LOCATION PLAN UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - -1.2-16 1.2-12UNIT 2 EQUIPMENT LOCATION - PLAN - - - - - - - - - - - - - - - - - - - - - - -1.2-171.2-13UNIT-2 EQUIPMENT LOCATION - PLAN - - - - - - - - - - - - - - - - - - - - - - -1.2-181.2-14MISCELLANEOUS SECTIONS UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - -1.2-19 1.2-15GENERAL ARRANGEMENT - WASTE DISPOSAL SYSTEM MODIFICATIONS - - -1.2-202.2-1GENERAL LOCATION MAP - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-22.2-2GENERAL TOPOGRAPHY MAP - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-3 2.2-2AGENERAL TOPOGRAPHY MAP - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-42.2-3SITE TOPOGRAPHY MAP - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-52.2-4UNITS 1 & 2 SITE PLAN - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.2-6 2.3-1POPULATION DISTRIBUTION 0-5 MILES (Historical)- - - - - - - - - - - - - - - - - 2.3-22.3-2POPULATION DISTRIBUTION 5-40 MILES (Historical) - - - - - - - - - - - - - - - - 2.3-32.5-1SHORE PROTECTION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.5-15 2.6-1CLIMATE OF POINT BEACH SITE REGION - - - - - - - - - - - - - - - - - - - - - - 2.6-182.6-2STABILITY CLASS DISTRIBUTION IN PERCENT OF TOTAL OBSERVED - - - - - -2.6-192.6-3PERSISTENCE WIND ROSE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-20 2.6-4DISTRIBUTION OF STABILTY BY DIRECTION - POINT BEACH ANNUALAVERAGE - 4/67-4/68 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-212.6-5ANNUAL /Q DISPERSION FACTOR MILWAUKEE DATA - - - - - - - - - - - - - -2.6-222.6-6ANNUAL AVERAGE /Q DISPERSION FACTOR SITE DATA (4/67-4/68) - - - - - - - 2.6-232.6-7FSAR ACCIDENT MODEL - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-242.6-8REVISED ACCIDENT MODEL - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.6-252.7-1PRE-OPERATIONAL ENVIRONMENTAL RADIOACTIVITY SAMPLING SITES - - - 2.7-6 2.8-1POINT BEACH BORING LOCATIONS - - - - - - - - - - - - - - - - - - - - - - - - - 2.8-42.8-2POINT BEACH BORING LOG (Sheets 1-2) - - - - - - - - - - - - - - - - - - - - - - -2.8-5 List of FiguresFSAR UFSAR 2015Page LOF - 2 of 16 2.9-1MAP SHOWING EPICENTERS OF PRINCIPAL EARTHQUAKES IN THEWISCONSIN REGION - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2.9-33.2-1CONTROL ROD CLUSTER GROUPS - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-49 3.2-2STANDARD FUEL NORMALIZED POWER DENSITY DISTRIBUTION (BOL)MAXIMUM POWER DENSITY = 1.364 - - - - - - - - - - - - - - - - - - - - - - - - 3.2-503.2-3NORMALIZED POWER DENSITY DISTRIBUTION (BOL) MAXIMUM POWERDENSITY = 1.505 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-5 13.2-4STANDARD FUEL NORMALIZED POWER DENSITY DISTRIBUTION (BOL) IN APLANE HAVING NO CONTROL RODS MAXIMUM POWER DENSITY = 1.384 - - - - 3.2-523.2-5INITIAL BURNABLE ABSORBER ROD LOCATION - - - - - - - - - - - - - - - - - 3.2-533.2-6ARRANGEMENT OF BURNABLE ABSORBER RODS WITHIN AN ASSEMBLY - - - 3.2-543.2-7TYPICAL EQUILIBRIUM RELOAD LOADING PATTERN - - - - - - - - - - - - - - - 3.2-55 3.2-8UPGRADED CORE ASSEMBLY EQUILIBRIUM LOADING PATTERN ANDIFBA PLACEMENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-563.2-9OFA NORMALIZED POWER DENSITY DISTRIBUTION NEAR BEGINNING OFLIFE, UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON - - - - - - - 3.2-573.2-10OFA NORMALIZED POWER DENSITY DISTRIBUTION NEAR BEGINNING OFLIFE, GROUP D AT INSERTION LIMIT HOT FULL POWER, EQUILIBRIUM XENON 3.2-583.2-11OFA NORMALIZED POWER DENSITY DISTRIBUTION NEAR END OF LIFE,UNRODDED CORE HOT FULL POWER, EQUILIBRIUM XENON - - - - - - - - - - - 3.2-593.2-12OFA NORMALIZED POWER DENSITY DISTRIBUTION NEAR END OF LIFE,GROUP D AT INSERTION LIMIT HOT FULL POWER, EQUILIBRIUM XENON - - - - 3.2-603.2-13UPGRADED CORE NORMALIZED POWER DISTRIBUTION AT150 MWD/MTU UNRODDED, HOT FULL POWER, EQUILIBRIUM XENON PEAK FH = 1.555 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-613.2-13aUPGRADED CORE NORMALIZED POWER DISTRIBUTION AT150 MWD/MTU D-BANK AT ROD INSERTION LIMIT, HOT FULL POWER, EQUILIBRIUM XENON PEAK FH = 1.574 - - - - - - - - - - - - - - - - - - - - - - 3.2-623.2-14UPGRADED CORE NORMALIZED POWER DISTRIBUTION AT10600 MWD/MTU UNRODDED, HOT FULL POWER, EQUILIBRIUM XENON PEAK FH = 1.50 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-633.2-14aUPGRADED CORE NORMALIZED POWER DISTRIBUTION AT10600 MWD/MTU D-BANK AT ROD INSERTION LIMIT, HOT FULL POWER, EQUILIBRIUM XENON PEAK FH = 1.515 - - - - - - - - - - - - - - - - - - - - - - 3.2-643.2-15EQUILIBRIUM CYCLE BOC, MOC AND EOC ASSEMBLY POWERDISTRIBUTIONS FOR 422V+ FUEL - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-653.2-16EQUILIBRIUM CYCLE LOADING PATTERN WITH BOC AND EOCASSEMBLY BURNUPS FOR 422V+ FUEL - - - - - - - - - - - - - - - - - - - - - - - 3.2-663.2-17MODERATOR TEMPERATURE COEFFICIENT vs. MODERATORTEMPERATURE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-673.2-18DOPPLER COEFFICIENT vs. EFFECTIVE FUEL TEMPERATURE (BOL) - - - - - - - 3.2-683.2-19POWER COEFFICIENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-693.2-20POWER COEFFICIENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-70 3.2-21CALCULATED AND MEASURED DOPPLER DEFECT AND COEFFICIENTSAT BEGINNING OF LIFE, TWO-LOOP PLANT, 121 ASSEMBLIES, 12-FOOT CORE - 3.2-71 List of FiguresFSAR UFSAR 2015Page LOF - 3 of 16 3.2-22COMPARISON OF CALCULATED AND MEASURED BORON CONCENTRATIONFOR 2-LOOP PLANT, 121 ASSEMBLIES, 12-FOOT CORE - - - - - - - - - - - - - - - 3.2-723.2-23THERMAL CONDUCTIVITY OF UO 2 (DATA CORRECTED TO 95%THEORETICAL DENSITY) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-733.2-24HIGH POWER FUEL ROD EXPERIMENTAL PROGRAM - - - - - - - - - - - - - - - 3.2-743.2-25COMPARISON OF W-3 PREDICTION AND UNIFORM FLUX DATA - - - - - - - - - 3.2-753.2-26W-3 CORRELATION PROBABILITY DISTRIBUTION CURVE - - - - - - - - - - - - 3.2-76 3.2-27COMPARISON OF W-3 CORRELATION WITH ROD BUNDLE DNB DATA(SIMPLE GRID WITHOUT MIXING VANE) - - - - - - - - - - - - - - - - - - - - - - 3.2-773.2-28COMPARISON OF W-3 CORRELATION WITH ROD BUNDLE DNB DATA(SIMPLE GRID WITH MIXING VANE) - - - - - - - - - - - - - - - - - - - - - - - - 3.2-783.2-29STABLE FILM BOILING HEAT TRANSFER DATA AND CORRELATION - - - - - - 3.2-79 3.2-30COMPARISON OF W-3 PREDICTION AND NON UNIFORM FLUX DATA (-0.15 XDNB +0.15) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-803.2-31COMPARISON OF W-3 PREDICTION WITH MEASURED DNB LOCATION - - - - - 3.2-813.2-32RADIAL POWER DISTRIBUTION - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-823.2-33MEASURED vs. PREDICTED CRITICAL HEAT FLUX WRB-1 CORRELATION - - - - 3.2-83 3.2-34REACTOR CORE CROSS SECTION - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-843.2-35REACTOR VESSEL INTERNALS - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-853.2-36BOTTOM NOZZLE FLOW HOLE COMPARISON - - - - - - - - - - - - - - - - - - - 3.2-86 3.2-37LOWER CORE SUPPORT STRUCTURE - - - - - - - - - - - - - - - - - - - - - - - - 3.2-873.2-38UPPER CORE SUPPORT ASSEMBLY - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-883.2-39GUIDE TUBE ASSEMBLY - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3.2-89 3.2-40FUEL ASSEMBLY AND CONTROL CLUSTER CROSS SECTION - - - - - - - - - - - 3.2-903.2-41FUEL ASSEMBLY OUTLINE (Sheets 1-5) - - - - - - - - - - - - - - - - - - - - - - - 3.2-913.2-4114 X 14 422VANTAGE + (422V+) FUEL ASSEMBLY OUTLINE (Sheet 6) - - - - - - - 3.2-96 3.2-41COMPARISON OF 14 X 14 OFA AND 422V + FUEL ROD DESIGNS (Sheet 7) - - - - - 3.2-973.2-42SPRING CLIP GRID ASSEMBLY WITH SPLIT MIXING VANES - - - - - - - - - - - 3.2-983.2-42aSPRING CLIP GRID ASSEMBLY WITH SPLIT MIXING VANES - - - - - - - - - - - 3.2-99 3.2-43REACTOR VESSEL STRESS CONCENTRATIONS (Sheets 1-3) - - - - - - - - - - - - 3.2-1003.4-1TYPICAL ROD CLUSTER CONTROL ASSEMBLY - - - - - - - - - - - - - - - - - - 13.4-123.4-2CONTROL ROD DRIVE MECHANISM ASSEMBLY - - - - - - - - - - - - - - - - - - 3.4-13 3.4-3CONTROL ROD DRIVE MECHANISM SCHEMATIC - - - - - - - - - - - - - - - - - 3.4-143.4-4DETAIL OF BURNABLE POISON ROD - - - - - - - - - - - - - - - - - - - - - - - - 3.4-154.2-1UNIT 1 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 1) - - - -4.2-22 4.2-1UNIT 1 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 2) - - - -4.2-234.2-1UNIT 1 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 3) - - - -4.2-244.2-1AUNIT 2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 1) - - - -4.2-25 4.2-1AUNIT 2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 2) - - - -4.2-264.2-1A UNIT 2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM (Sheet 3) - - -4.2-27 List of FiguresFSAR UFSAR 2015Page LOF - 4 of 16 4.2-2REACTOR VESSEL SCHEMATIC - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-284.2-3PRESSURIZER - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-294.2-4UNIT 1 STEAM GENERATOR - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-304.2-5UNIT 2 STEAM GENERATOR - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-314.2-6REACTOR COOLANT PUMP - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-32 4.2-7REACTOR COOLANT PUMP ESTIMATED PERFORMANCE CHARACTERISTICS - - 4.2-334.2-8REACTOR COOLANT PUMP FLYWHEEL - - - - - - - - - - - - - - - - - - - - - - 4.2-344.2-9FLYWHEEL STRESS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 4.2-3 55.1-1CONTAINMENT STRUCTURE - GENERAL ARRANGEMENT (Sheets 1-3) - - - - - -5.1-7 55.1-2CONTAINMENT STRUCTURE - TYPICAL PIPING PENETRATIONS - - - - - - - - -5.1-7 85.1-3CONTAINMENT STRUCTURE - TYPICAL ELECTRICAL PENETRATIONS - - - - -5.1-795.1-4CONTAINMENT STRUCTURE - PERSONNEL LOCK - - - - - - - - - - - - - - - - -5.1-8 05.1-5CONTAINMENT STRUCTURE - EQUIPMENT HATCH - - - - - - - - - - - - - - - -5.1-8 15.1-6DESIGN THERMAL GRADIENT ACROSS CONTAINMENT WALLPOINT BEACH NUCLEAR PLANT - - - - - - - - - - - - - - - - - - - - - - - - - - -5.1-8 25.1-7EARTHQUAKE RESPONSE SPECTRUM - 0.06g - - - - - - - - - - - - - - - - - - - -5.1-8 35.1-8EARTHQUAKE RESPONSE SPECTRUM - 0.12g - - - - - - - - - - - - - - - - - - - -5.1-8 45.1-9CONTAINMENT STRUCTURE - FINITE ELEMENT MESH - - - - - - - - - - - - - -5.1-8 55.1-10CONTAINMENT STRUCTURE - ISO-STRESS PLOTS: DOME AND WALL(Sheets 1-5) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -5.1-8 65.1-11CONTAINMENT STRUCTURE - ISO-STRESS PLOTS: BASE AND WALL(Sheets 1-8) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -5.1-9 15.1-12CONTAINMENT STRUCTURE - FINITE ELEMENT MESH FOR BUTTRESS - - - - -5.1-995.1-13ISO-STRESS PLOTS - CONTAINMENT STRUCTURE BUTTRESS (Sheets 1-2) - - - -5.1-10 05.1-14CONTAINMENT STRUCTURE - EARTHQUAKE RESPONSE DATA - - - - - - - - -5.1-10 25.1-15CONTAINMENT STRUCTURE - 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- - - - - - - -7.2-35 List of FiguresFSAR UFSAR 2015Page LOF - 8 of 16 7.2-4DESIGN TO ACHIEVE ISOLATION BETWEEN CHANNELS - - - - - - - - - - - - -7.2-367.2-5BASIC ELEMENTS OF AN ANALOG CHANNEL - - - - - - - - - - - - - - - - - - -7.2-377.2-6SIMPLIFIED TRIP LOGIC TRAINS - - - - - - - - - - - - - - - - - - - - - - - - - -7.2-38 7.2-7LOGIC CHANNEL TEST PANELS (UNIT 1) - - - - - - - - - - - - - - - - - - - - - -7.2-397.2-8TAVG/T CONTROL AND PROTECTION SYSTEM - - - - - - - - - - - - - - - - - -7.2-407.2-9ANALOG SYSTEM SYMBOLS - - - - - - - - - - - - - - - - - - - - - - - - - - - -7.2-41 7.2-10PRESSURIZER PRESSURE CONTROL AND PROTECTION SYSTEM - - - - - - - - -7.2-427.2-11PRESSURIZER LEVEL CONTROL AND PROTECTION SYSTEM - - - - - - - - - - -7.2-437.2-12STEAM GENERATOR LEVEL CONTROL AND PROTECTION SYSTEM - - - - - - -7.2-44 7.3-1ENGINEERED SAFETY FEATURE LOGIC DIAGRAM - - - - - - - - - - - - - - - -7.3-217.3-2ENGINEERED SAFETY FEATURE LOGIC MATRIX - - - - - - - - - - - - - - - - -7.3-227.4-1LOSS OF FEEDWATER TURBINE TRIP - 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- - - - - - - - - - - - - - - -8.0-98-4480V ONE LINE DIAGRAM ALTERNATE SHUTDOWN SYSTEM - - - - - - - - - -8.0-128-5UNITS 1 & 2 125 V ONE LINE DIAGRAM - - - - - - - - - - - - - - - - - - - - - - -8.0-13 8-6UNITS 1 & 2 125 VDC ONE LINE DIAGRAM - - - - - - - - - - - - - - - - - - - - -8.0-148-7125V ONE LINE DIAGRAM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -8.0-158-8UNITS 1 & 2 INSTRUMENT BUS ONE LINE DIAGRAM - - - - - - - - - - - - - - -8.0-16 8.1-1345 kV SWITCHYARD AND INTERCONNECTIONS - - - - - - - - - - - - - - - - -8.1-48.1-2PBNP 345 kV INTERCONNECTIONS - - - - - - - - - - - - - - - - - - - - - - - - -8.1-58.2-113.8 kV SIMPLIFIED ONE LINE DIAGRAM - - - - - - - - - - - - - - - - - - - - - -8.2-4 8.4-14.16 kV AC DISTRIBUTION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - -8.4-48.6-1INSTRUMENT POWER RED AND BLUE CHANNELS - - - - - - - - - - - - - - - - -8.6-48.6-2INSTRUMENT POWER WHITE AND YELLOW CHANNELS - - - - - - - - - - - - -8.6-5 8.6-3INSTRUMENT POWER NON-PROTECTION SECTION - - - - - - - - - - - - - - - -8.6-68.7-1125 VDC ELECTRICAL DISTRIBUTION - - - - - - - - - - - - - - - - - - - - - - - -8.7-59.1-1UNIT 1 AUXILIARY COOLANT SYSTEM - - - - - - - - - - - - - - - - - - - - - - -9.1-11 9.1-2UNIT 1 AUXILIARY COOLANT SYSTEM - - - - - - - - - - - - - - - - - - - - - - -9.1-129.2-1UNIT 1 AUXILIARY COOLANT SYSTEM - - - - - - - - - - - - - - - - - - - - - - -9.2-79.3-1UNIT 1 CHEMICAL AND VOLUME CONTROL - - - - - - - - - - - - - - - - - - - -9.3-30 List of FiguresFSAR UFSAR 2015Page LOF - 9 of 16 9.3-2UNIT 1 CHEMICAL AND VOLUME CONTROL - - - - - - - - - - - - - - - - - - - -9.3-319.3-3UNIT 1 CHEMICAL AND VOLUME CONTROL - - - - - - - - - - - - - - - - - - - -9.3-329.3-4UNIT 1 CHEMICAL AND VOLUME CONTROL - - - - - - - - - - - - - - - - - - - -9.3-33 9.3-5UNIT 1 CHEMICAL AND VOLUME CONTROL - - - - - - - - - - - - - - - - - - - -9.3-349.4-1FUEL TRANSFER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.4-149.6-1UNIT 1 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-9 9.6-2UNIT 1 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-109.6-3UNIT 1 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-119.6-4UNIT 1 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-12 9.6-5UNIT 1 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-139.6-6UNIT 2 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-149.6-7UNIT 2 SERVICE WATER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - -9.6-159.8-1CONTROL ROOM VENTILATION OPERATING MODES (Sheets 1-5) - - - - - - - - -9.8-79.9-1UNIT 1 SPENT FUEL POOL COOLING SYSTEM - - - - - - - - - - - - - - - - - - -9.9-12 9.10-1FIRE PROTECTION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.10-29.10-2FIRE PROTECTION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.10-39.10-3FIRE PROTECTION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.10-4 9.10-4FIRE PROTECTION SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.10-59.11-1UNIT 1 SAMPLING SYSTEM - - - - - - - - - - - - - - - - - - - - - - - - - - - - -9.11-1010.1-1UNITS 1 & 2 MAIN AND REHEAT STEAM FLOW DIAGRAM (Sheet 1) - - - - - - - -10.1-22 10.1-1UNIT 1 MAIN AND REHEAT STEAM FLOW DIAGRAM (Sheets 2-3) - - - - - - - - -10.1-2310.1-1AUNIT 2 MAIN AND REHEAT STEAM FLOW DIAGRAM (Sheets 1-3) - - - - - - - - -10.1-2510.1-2UNIT 1 CONDENSATE AND FEEDWATER FLOW DIAGRAM (Sheets 1-3) - - - - - -10.1-2810.1-2AUNIT 2 CONDENSATE AND FEEDWATER FLOW DIAGRAM (Sheets 1-3) - - - - - -10.1-3110.1-3UNIT 1 EXTRACTION STEAM FLOW DIAGRAM (Sheets 1-2) - - - - - - - - - - - - -10.1-3410.1-3AUNIT 2 EXTRACTION STEAM FLOW DIAGRAM (Sheets 1-2) - - - - - - - - - - - - -10.1-36 10.1-4UNIT 1 FEEDWATER HEATER DRAINS FLOW DIAGRAM (Sheets 1-3) - - - - - - - -10.1-3810.1-4AUNIT 2 FEEDWATER HEATER DRAINS FLOW DIAGRAM (Sheets 1-3) - - - - - - - -10.1-4110.1-6UNIT 1 CIRCULATING WATER CONDENSER AIR REMOVAL - - - - - - - - - - - -10.1-44 10.1-6AUNIT 2 CIRCULATING WATER CONDENSER AIR REMOVAL - - - - - - - - - - - -10.1-4510.1-6BUNITS 1 & 2 CIRCULATING WATER SYSTEM SCREEN WASH (Sheet 2) - - - - - - -10.1-4610.1-7UNIT 1 FEEDWATER HEATER VENTS AND RELIEFS FLOW DIAGRAM - - - - - -10.1-4710.1-7AUNIT 2 FEEDWATER HEATER VENTS AND FLOW DIAGRAM - - - - - - - - - - -10.1-4810.1-8UNIT 1 GLAND STEAM AND DRAINS FLOW DIAGRAM - - - - - - - - - - - - - - -10.1-4910.1-8AUNIT 2 GLAND STEAM AND DRAINS FLOW DIAGRAM - - - - - - - - - - - - - - -10.1-50 10.2-1UNITS 1 & 2 AUXILIARY FEEDWATER SYSTEM FLOW DIAGRAM (Sheet 1) - - - -10.2-1210.2-1UNITS 1 & 2 AUXILIARY FEEDWATER SYSTEM FLOW DIAGRAM (Sheet 2) - - - -10.2-1310.2-1UNIT 1 AUXILIARY FEEDWATER SYSTEM FLOW DIAGRAM (Sheet 3) - - - - - - -10.2-1411.1-1UNITS 1 & 2 WASTE DISPOSAL SYSTEM PROCESS FLOW DIAGRAM (Sheets 1-2) -11.1-17 11.1-2UNITS 1 & 2 BLOWDOWN EVAPORATOR SYSTEM - - - - - - - - - - - - - - - - -11.1-19 List of FiguresFSAR UFSAR 2015Page LOF - 10 of 16 11.1-3UNITS 1 & 2 CONDENSATE WASTE POLISHING DEMINERALIZER - - - - - - - - -11.1-2011.2-1UNITS 1 & 2 WASTE GAS DISPOSAL SYSTEM PROCESS FLOW DIAGRAM(Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -11.2-2411.2-2UNITS 1 & 2 GAS STRIPPER SYSTEM - - - - - - - - - - - - - - - - - - - - - - - -11.2-2711.2-3UNITS 1 & 2 CRYOGENIC GAS SEPARATION SYSTEM (Sheets 1-2) - - - - - - - - -11.2-2811.2-4UNITS 1 & 2 CONDENSER AIR REMOVAL DECAY SYSTEM - - - - - - - - - - - -11.2-30 11.4-1UNIT 1 CONTAINMENT OPERTING FLOOR AND MISCELLANIOUS UPPERFLOORS SOUTH - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -11.4-1511.4-2UNIT 1 RADIATION CONTROL AREA - OPERATING FLOOR - - - - - - - - - - - -11.4-16 11.4-3UNIT 1 RADIATION CONTROL AREA - INTERMEDIATE FLOOR - - - - - - - - - -11.4-1711.4-4UNIT 1 RADIATION CONTROL AREA - GROUND FLOOR - - - - - - - - - - - - - -11.4-1811.4-5UNIT 2 CONTAIMENT OPERATING FLOOR AND MISCELLANOUS UPPERFLOORS NORTH - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -11.4-1911.4-6UNIT 2 OPERATING FLOOR LEVELS NORTH - - - - - - - - - - - - - - - - - - - -11.4-20 11.4-7UNIT 2 INTERMEDIATE FLOOR LEVELS NORTH - - - - - - - - - - - - - - - - - -11.4-2111.4-8UNIT 2 GROUND FLOOR NORTH - - - - - - - - - - - - - - - - - - - - - - - - - - -11.4-2211.5-1TYPICAL RMS CHANNEL FUNCTIONAL BLOCK DIAGRAM - - - - - - - - - - - -11.5-26 11.5-2RADIATION MONITORING SYSTEM FUNCTIONAL BLOCK DIAGRAM - - - - - -11.5-2711.6-1MAXIMUM RADIATION LEVELS SURROUNDING 14 IN. DIAMETERR.H.R. PIPE CIRCULATING WATER CONTAINING FISSION PRODUCTACTIVITY FROM FUEL ROD GAPS (Historical) - - - - - - - - - - - - - - - - - - - -11.6-1911.6-2SENSITIVITY OF DOSE TO ACTIVITY IN THE RESIDUAL HEAT REMOVAL WATER (Historical) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -11.6-2014.0-1ILLUSTRATION OF OVERTEMPERATURE AND OVERPOWER DELTA-TPROTECTIO N - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.0-1314.0-2RCCA NORMALIZED ROD POSITION VS. TIME CURVE - - - - - - - - - - - - - - -14.0-14 14.0-3NORMALIZED REACTIVITY VS ROD POSITION - - - - - - - - - - - - - - - - - - -14.0-1514.0-4NORMALIZED TRIP REACTIVITY VS TIME - - - - - - - - - - - - - - - - - - - - -14.0-1614.1.1-1UNCONTROLLED RCCA BANK WITHDRAWAL FROM SUBCRITICALNUCLEAR POWER TRANSIENT - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.1-614.1.1-2UNCONTROLLED RCCA BANK WITHDRAWAL FROM SUBCRITICALHEAT FLUX TRANSIENT - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.1-714.1.1-3UNCONTROLLED RCCA BANK WITHDRAWAL FROM SUBCRITICALFUEL TEMPERATURE TRANSIENT - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.1-814.1.2-1ROD WITHDRAWAL AT POWER 100%, MINIMUM FEEDBACK100 PCM/SECOND (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.2-714.1.2-2ROD WITHDRAWAL AT POWER 100%, MINIMUM FEEDBACK1PCM/SECOND (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.2-1014.1.2-3ROD WITHDRAWAL AT POWER 100% (Sheets 1-3) - - - - - - - - - - - - - - - - - -14.1.2-1314.1.3-1NUCLEAR POWER TRANSIENT AND CORE HEAT FLUX TRANSIENTFOR DROPPED RCCA - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.3-314.1.3-2PRESSURIZER PRESSURE TRANSIENT AND VESSEL AVERAGETEMPERATURE TRANSIENT FOR DROPPED RCCA - - - - - - - - - - - - - - - - -14.1.3-414.1.4-1RATIO OF THE INITIAL BORON CONCENTRATION TO THE CRITICAL BORONCONCENTRATION (DILUTION FACTOR, DLF) AS A FUNCTION OF RHRFLOW RATE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.
4-5 List of FiguresFSAR UFSAR 2015Page LOF - 11 of 16 14.1.5-1START-UP OF AN INACTIVE REACTOR COOLANT LOOP - - - - - - - - - - - - - -14.1.5-314.1.5-2START-UP OF AN INACTIVE REACTOR COOLANT LOOP - - - - - - - - - - - - - -14.1.5-414.1.5-3START-UP OF AN INACTIVE REACTOR COOLANT LOOP - - - - - - - - - - - - - -14.1.5-5 14.1.5-4START-UP OF AN INACTIVE REACTOR COOLANT LOOP - - - - - - - - - - - - - -14.1.5-614.1.7-1EXCESSIVE LOAD INCREASE BOL, MANUAL CONTROL (Sheets 1-4) - - - - - - - -14.1.7-414.1.7-2EXCESSIVE LOAD INCREASE BOL, AUTO CONTROL (Sheets 1-4) - - - - - - - - - -14.1.7-8 14.1.7-3EXCESSIVE LOAD INCREASE EOL, MANUAL CONTROL (Shets 1-4)- - - - - - - - -14.1.7-1214.1.7-4EXCESSIVE LOAD INCREASE EOL, AUTO CONTROL (Sheets 1-4) - - - - - - - - - -14.1.7-1614.1.8-1UNDERFREQUENCY EVENT (5 Hz/sec FREQUENCY DECAY RATE) (Sheets 1-3)- - -14.1.8-16 14.1.8-2COMPLETE LOSS OF FLOW (2/2 RCP COASTDOWN) (Sheets 1-3) - - - - - - - - - -14.1.8-1914.1.8-3RCP LOCKED ROTOR (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.8-2214.1.9-1LOSS OF ELECTRICAL LOAD WITH PRESSURE CONTROL (DNB Case) (Sheets 1-3) 14.1.9-614.1.9-2LOSS OF ELECTRICAL LOAD WITHOUT PRESSURE CONTROL(RCS Overpressure Case) (Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.9-914.1.9-3LOSS OF ELECTRICAL LOAD WITH PRESSURE CONTROL (SG Overpressure Case)(Sheets 1-3) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.1.9-1214.1.10-1UNIT 1 (MODEL 44F SG) LOSS OF NORMAL FEEDWATER (Sheets 1-6)- - - - - - - -14.1.10-514.1.10-2UNIT 2 (Delta - 47 SG) LOSS OF NORMAL FEEDWATER (Sheets 1-6) - - - - - - - - -14.1.10-11 14.1.11-1UNIT1 (MODEL 44F SG) LOSS OF AC POWER (Sheets 1-6) - - - - - - - - - - - - - -14.1.11-514.1.11-2UNIT2 (DELTA - 47 SG) LOSS OF AC POWER (Sheets 1-6) - - - - - - - - - - - - - -14.1.11-1114.2.5-1RUPTURE OF A STEAM PIPE UNIT 1 WITH OFFSITE POWER (Sheets 1-6) - - - - - -14.2.5-17 14.2.5-2RUPTURE OF A STEAM PIPE UNIT 1 WITHOUT OFFSITE POWER (Sheets 1-6)- - - -14.2.5-2314.2.5-3CONTAINMENT PRESSURE MSLB CONTAINMENT RESPONSE ANALYSIS - - - -14.2.5-2914.2.5-4CONTAINMENT TEMPERATURE MSLB CONTAINMENT RESPONSE ANALYSIS -14.2.5-3014.2.6-1RCCA EJECTION TRANSIENT BEGINNING OF LIFE ZERO POWER - - - - - - - - -14.2.6-1314.2.6-2RCCA EJECTION TRANSIENT BEGINNING OF LIFE FULL POWER - - - - - - - - -14.2.6-1414.2.6-3RCCA EJECTION TRANSIENT END OF LIFE ZERO POWER - - - - - - - - - - - - -14.2.6-15 14.2.6-4RCCA EJECTION TRANSIENT END OF LIFE FULL POWER - - - - - - - - - - - - -14.2.6-1614.3.1-1HOT ROD AXIAL POWER DISTRIBUTION - - - - - - - - - - - - - - - - - - - - - -14.3.1-1414.3.1-2PUMPED HHSI SAFETY INJECTION FLOW RATE FAULTED LOOPSPILLING TO RCS PRESSURE - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-1514.3.1-3PUMPED HHSI SAFETY INJECTION FLOW RATE FAULTED LOOPSPILLING TO CONTAINMENT PRESSURE - - - - - - - - - - - - - - - - - - - - - -14.3.1-1614.3.1-3APUMPED LHSI SAFETY INJECTION FLOW RATE UPPER PLENUM INJECTION - - -14.3.1-1714.3.1-4REACTOR COOLANT SYSTEM PRESSURE - 3 INCH BREAK POINT BEACH UNIT 1 14.3.1-1814.3.1-5CORE MIXTURE LEVEL AND TOP OF CORE - 3 INCH BREAK POINT BEACHUNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-1914.3.1-6TOTAL REACTOR COOLANT SYSTEM MASS - 3 INCH BREAK POINT BEACHUNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2014.3.1-7TOP CORE EXIT VAPOR TEMPERATURE - 3 INCH BREAK POINT BEACHUNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2114.3.1-8VAPOR MASS FLOW RATE OUT OF TOP OF CORE - 3 INCH BREAK POINT BEACHUNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-22 List of FiguresFSAR UFSAR 2015Page LOF - 12 of 16 14.3.1-9TOTAL BREAK FLOW AND SAFETY INJECTION FLOW - 3 INCH BREAKPOINT BEACH UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2314.3.1-10CLADDING SURFACE HEAT TRANSFER COEFFICIENT AT PCT ELEVATION- 3 INCH BREAK POINT BEACH UNIT 1- - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2414.3.1-11FLUID TEMPERATURE AT PCT ELEVATION - 3 INCH BREAK POINT BEACHUNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2514.3.1-12CLADDING TEMPERATURE TRANSIENT AT PCT ELEVATION - 3 INCH BREAKPOINT BEACH UNIT 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2614.3.1-13LOCAL ZRO2 THICKNESS AT MAXIMUM LOCAL ZRO2 ELEVATION - 3 INCHBREAK POINT BEACH UNIT 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2714.3.1-14REACTOR COOLANT SYSTEM PRESSURE - 3 INCH BREAK POINT BEACHUNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2814.3.1-15CORE MIXTURE LEVEL AND TOP OF CORE - 3 INCH BREAK POINT BEACHUNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-2914.3.1-16TOTAL REACTOR COOLANT SYSTEM MASS - 3 INCH BREAK POINT BEACHUNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3014.3.1-17TOP CORE EXIT VAPOR TEMPERATURE - 3 INCH BREAK POINT BEACH UNIT 2 -14.3.1-31 14.3.1-18VAPOR MASS FLOW RATE OUT OF TOP OF CORE - 3 INCH BREAKPOINT BEACH UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3214.3.1-19TOTAL BREAK FLOW AND SAFETY INJECTION FLOW - 3 INCH BREAKPOINT BEACH UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3314.3.1-20CLADDING SURFACE HEAT TRANSFER COEFFICIENT AT PCT ELEVATION- 3 INCH BREAK POINT BEACH UNIT 2- - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3414.3.1-21FLUID TEMPERATURE AT PCT ELEVATION - 3 INCH BREAK POINT BEACHUNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3514.3.1-22CLADDING TEMPERATURE TRANSIENT AT PCT ELEVATION - 3 INCH BREAKPOINT BEACH UNIT 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -14.3.1-3614.3.1-23LOCAL ZR02 THICKNESS AT MAXIMUM LOCAL ZRO2 ELEVATION - 3 INCHBREAK POINT BEACH UNIT 2- - 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