ML15279A240
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Security Related Information Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from Attachment 1.Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-183 September 11, 2015 10 CFR 50.4 10 CFR 50.34(b)10 CFR 2.390(d)(1)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Construction Permit No. CPPR-92 Docket No. 50-391
Subject:
Watts Bar Nuclear Plant -Unit 2 -Final Safety Analysis Report, Amendment 114
Reference:
TVA letter to NRC, CNL-1 5-023, "Watts Bar Nuclear Plant -Unit 2 -Final Safety Analysis Report, Amendment 113," dated February 23, 2015 This letter transmits the Watts Bar Nuclear Plant (WBN) Unit 2 Final Safety Analysis Report (FSAR) Amendment 114 (Al114), which reflects changes made since the submittal of Amendment 113 on February 23, 2015.Enclosure 1 contains a listing of sections affected, description of the Al114 changes, and the corresponding Unit 2 change package numbers. In discussions with the NRC Staff, it was determined that the figures would not be updated at this time. The figures will be updated as part of the Unit 1 Updated Final Safety Analysis Report (UFSAR) and Unit 2 FSAR merger during the first update of the Unit 1 UFSAR after Unit 2 receives an operating license.Amendment 114 is provided on the attached Optical Storage Media (OSM #1)(Attachment 1). The FSAR contains security-related information identified by the designation "Security-Related Information
-Withhold Under Title 10 Code of Federal Regulations (CFR) 2.390." Tennessee Valley Authority hereby requests this information be withheld from public disclosure in accordance with the provisions of 10 CER 2.390. A redacted version of the FSAR is contained on OSM #2 (Attachment 2), which is suitable for public disclosure.
U.S. Nuclear Regulatory Commission CNL-1 5-183 Page 2 September 1 1, 2015 Enclosure 2 contains a listing of I he FSAR pages that have been redacted, Enclosture 3 lists the files and file sizes on the security-related OSM (OSM #1), anti Enclosure 4 lists the files and file sizes on the publicly available O.SM (OSM #2). Enclosure 5 contains the cominmtment contained in this letter.If you have any questions, please contact GordOn Ar~ent at (423) 365-2004.I declare under penalty of pe~rjury that the foregoing is true and correct. Executed on the'11lth day of September 2015.Res~pectf,!/lY, Vic~etPr~esident, Nuclear Licensing
Enclosures:
'1. WBN Unit 2 FSAR Al 14, Suriimary Listing df Al1i.4 FSAR Changes 2. WBN unit 2 FSAR Al 14. Summary. of Redacted Pages.3. WBN Unit 2 FSAR Al114, List of Files and File Sizes onthe Security-Related OSM (OSM #1)4. Unit 2 FSAR List of Files and File Sizes on the Publicly Available OSM. (OSM #2)5. List of Commitments Attachments:
1..OSM #1: WBN. Unit 2 FSAR Amendment "114 -Security-Related Iliformationi
-Withhold Under Title 10 Code~of Federal Regulations (CER) 2.390 2. OSM #,2: WBN Unit 2 FSAR Amendment.
114 -Publicly Availabdle.Version cc: NRC Regional Administrator
-Region II'NRC Senior Resident Inspector
-watts Bar Nuclear Plant, Unit 2 NR.C. Project Manager -Watts Bar. Nuclear Plant, Unit 2 ENCLOSURE 1 WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Change Item Change Change Description Package No. Area Number In Section 5.5.7.2.2 on Page 5.5-30, replace Item No. 3 verbiage from: "(3) UNIT 2 ONLY- The WINCISE thermocouples are installed from the bottom of the vessel and are always available." Section to 5.5.7.2.2 2140"(3) UNIT 2 ONLY- Maintenance of at least two incore thermocouples when the reactor head is in place with irradiated fuel in the reactor vessel except when the Incore Instrument Thimble Assemblies (IITAs) are disconnected for refueling and the liTAs are reconnected following the completion of refueling." In Section 7.3.1.1.3 on Page 7.3-4, in the first paragraph, make changes to the sentence that reads: "The various components have been qualified to IEEE Standard 323-1983 (R-1 996) "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations", IEEE Standard 344-1987 (R-1 993) "IEEE Standard Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations", and IEEE 2. Section Standard 384-1984 (R-1 992) "IEEE Standard Criteria for 2-114-02 7.3.1.1.3 Independence of Class IE Equipment and Circuits" replace with"The various components have been qualified to IEEE Standard 323-1974 "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations" and IEEE Standard 344-1975 "IEEE Standard Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations." Table In Table 10.4-6, Sheet I of 3, under Item 1, change the number of 3 1046 Auxiliary Feedwater Pumps required for a Loss of Normal 2-114-03 10.-6 Feedwater (LONF) from "2 MD or TD" to "Any 2 Pumps." Table For Table 14.2-1 on Page 14.2-96, insert the word "pocket" 4. 14.2-1 between the words "drain" and "sump" in Item No. 3 under the 2-1 14-04 heading of Test Method.El-I p's ENCLOSURE 1 WBN Unit 2 FSAR Al14 Summary Listing of Al 14 FSAR Changes Item hangeChange Item CAngea Change Description Package Number 1. On FSAR Table 10.4-5, Sheet 1 of 8, for check valve 2-3-806 (Item 1), under the column entitled "Effect on System," change the pump UNID from "MOP 2A-A" to "MDP 2B-B." Table4- 2. On FSAR Table 10.4-5, Sheet 1 of 8, for Items 1 through 3, 2-114-05 move the information currently included in the column entitled"Effect on Plant" to the column entitled "Remarks" and the information currently included in the column entitled "Remarks" to the column entitled "Effect on Plant." Table On FSAR Table 14.2-1, Sheet 69 of 89, change the required flow 6. 14.2-1 range in Acceptance Criteria 2 from "3300 to 3500 gpm" to "3500 2-114-06 to 3800 gpm." 1. In FSAR Section 6.2.2.2 (FSAR page 6.2.2-4), delete the sentence "Each pump is rated for 4000 gpm flow at a design head of 435 ft." from the first paragraph under the Component Description subsection entitled "Pumps." 2. In FSAR Section 6.2.2.2 (FSAR page 6.2.2-4), delete the word"additional" from the last sentence of the first paragraph under the Component Description
subsection entitled Pumps." 3. On ESAR Table 6.2.2-1 (FSAR page 6.2.2-10), add a reference to Note 1 to "Design Head, ft." Section 6.2.2 4. On FSAR Table 6.2.2-1 (FSAR page 6.2.2-10), add Note 1 to 2140 state the following: "The minimum acceptable developed head at 4,000 gpm is 391.5 ft. (includes 5% pump wear allowance and is based on LO-LO level in the RWST), thereby assuring that the safety limit for accident analysis (372.9 ft. at 4000 gpm) is met.Preoperational testing results indicate that initial CS pump performance is somewhat below the certified pump curves, but well in excess of the minimum required CS pump performance as evaluated in LTR-SEE-I-15-19." For Section 10.4.5 on page 10.4-14 (A113), insert the following as the last paragraph of Section 10.4.5.3: Section 8. 10.4.5.3 "The seismic ruggedness of the 102-inch CCW piping in the 2-114-08 Turbine Building will limit the size of a break such that sufficient time exists for the break to be isolated by manual operator action_____ __________prior to flooding the Turbine Building above the 708.0 elevation." _____El1-2 ENCLOSURE1I WBN Unit 2FSAR AI14 Summary Listing of Al14 FSAR Changes Item hangeChange Ntem CAngea Change Description IPackage No. Ara ..N umber 9.Table 14.2-1 1. On FSAR Table 14.2-1, Sheet 85 of 89, to align the ESAR text with the test scoping document for the operation of the highest demand loads, revise Test Method 2 as follows: From"2. With the Auxiliary Control Air System operating in a steady state condition, operate at least two of the highest demand loads supplied from the same train, simultaneously." To"2. With the Auxiliary Control Air System operating in a steady state condition, operate several of the highest demand loads supplied from the same train, simultaneously." 2. On FSAR Table 14.2-1, Sheet 86 of 89, to align the FSAR text with the test scoping document for the operation of the highest demand loads, revise Acceptance Criteria 3 as follows: From"3. Simultaneous operation of the two highest demand loads supplied from each train will not cause unacceptable system pressure transients as described in applicable design documents." To"3. Simultaneous operation of several highest demand loads supplied from each train will not cause unacceptable system pressure transients as described in applicable design documents." 2-114-09 For Penetration 19A, on Page 12 of 69 of Table 6.2.4-1, replace"RHR Pump lA-A" with "RHR Pump 2A-A" in the System number Table and penetration description column.10. 2-114-10 6.2.4-1 For Penetration 19B, on Page 12 of 69 of Table 6.2.4-1, replace"RHR Pump lB-B" with "RHR Pump 2B-B" in the System number____ ___________and penetration description column._____
El1-3 ENCLOSURE 1 WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaNumber
- 1. On Page 6.2.1-49, revise Regulatory Guide 1.7 revision level from "Rev. 2 November 1978," to "Rev. 3, March 2007." Revise the title by deleting the phrase, "Following a Loss of Coolant Accident." 2. On Page 7.5-15, correct the revision date for Regulatory Guide 1.7, Revision 3 from "May 2003" to "March 2007." Secton 62.13. On Page 7.5-36, replace the existing verbiage for "Unit 2 only" 11. Section 7.5 heading under the "Justification" heading with the following:
2-114-11 Table 7.5-2"Regulatory guidance from 10 CFR 50.44 Final Rule and RG 1.7, Rev. 3 indicates that hydrogen concentrations in the post-LOCA environment are non risk-significant and will always be below the lower flammability limit of 4% by volume. The Combustible Gas Control System (CGCS) handles degraded core hydrogen releases in the beyond-design-basis accident environment as specified in 10 CFR 50.44 and will keep hydrogen concentration below 10% for these events. Therefore, the instrumentation will always be on scale." 1. On FSAR Table 6.2.4-4, add penetration X-58B as an instrument line penetrating primary containment.
- 2. On FSAR Table 6.2.4-4, change the Line Size from 3/16" to 1/4" for penetrations X-84B, X-84C, X-84D, X-87B, X-87C and X-87D.12. Table 3. On FSAR Table 6.2.4-4, add the following footnote:
2-114-12 6.2.4-4" 2 Capillary lines are 1/4" through the containment penetration.
They transition to 3/16" on both sides of the containment penetration
." 4. On FSAR Table 6.2.4-4, add a superscript "2" to the entry in the line identification column for penetrations X-58B, X-84B,____ __________
X-84C,_X-84D,_X-87B,_X-87C andX-87D.
____El1-4 ENCLOSURE 1 WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange Ntem CAngea Change Description Package Number 1. On FSAR Table 6.2.4-4, add penetration X-58B as an instrument line penetrating primary containment.
- 2. On FSAR Table 6.2.4-4, change the Line Size from 3/16" to 1/4">> for penetrations X-84B, X-84C, X-84D, X-87B, X-87C and X-87D.12. Table 3. On FSAR Table 6.2.4-4, add the following footnote:
2-114-12 6.2.4-4" 2 Capillary lines are 1/4" through the containment penetration.
They transition to 3/16" on both sides of the containment penetration
." 4. On FSAR Table 6.2.4-4, add a superscript "2" to the entry in the line identification column for penetrations X-58B, X-84B, X-84C, X-84D, X-87B, X-87C and X-87D.1. Revise Figure 14.2-2 to better describe the proposed Power Ascension Testing topics and sequence as follows: a. Update the sequence of performance for several testing topics.b. Addition of MODES 5, 4 and 3 to the pseudo time/ powerline (sequence lines).13. Figure 2-114-13 14.2-2 c. Reordering test topics to closer depict proposed testing sequence.d. Changed test topic titles to better identify the test and/or the system being tested.e. Addition of omitted test topic.El-5 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaN umber 1. Updates Section 6.3.2.17 to clarify that certain actions are required to support establishment of the LOCA Recirculation phase of accident mitigation.
- 2. Updates Table 6.3-3 to describe manual actions required to align ERCW and CCS for the LOCA Recirculation phase of accident mitigation.
- 3. Updates Section 9.2.1 to better describe the operation of ERCW during a LOCA event and to describe how ERCW complies with Sectin 6.3 General Design Criterion (GDC) 5.14. Section 9.2 2-114-14 4. Updates Section 9.2.2 to better describe the operation of CCS during a LOCA event and to describe how CCS complies with GDC 5.5. Updates Table 9.2-2 to incorporate changes resulting from EPMIVS011092, Revisions 13, 14 and 15, "Failure Modes and Effects Analysis of the Essential Raw Cooling Water System." 6. Updates Table 9.2-9 to incorporate changes resulting from EPMSGP022892, Revisions 13, 14 and 15, "Failure Modes and_____ __________
EffectsAnalysis of theComponentCoolingSystem."_____
El1-6 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes TChange Item Change Change Description IPackage No. Area INumber For Table 6.3-3, modify the steps provided in Change Package 2-114-14 to align 00S and ERCW system for the LOCA recirculation phase of the plant by replacing the steps as follows: "2. Prepare CCS for recirculation mode by: a. Ensure RHR HX 1(2)A OUTLET 1(2)-FCV-70-156 valve(s) are open b. Ensure RHR HX 1(2)B OUTLET 1(2)-FCV-70-153 valve is throttled to 5,000 gpm on Accident Unit c. If the non-accident is using RHR, while maintaining at least 5,000 gpm 00S flow to the RHR HX on the Accident Unit, ensure the Non-Accident Unit RHR HX 1 (2)B OUTLET 1 (2)-FCV-70-1 53 valve is throttled to approximately to 2725 gpm (or whatever is achievable)
- d. Start all available CCS pumps e. For a LOCA on Unit 1 Only, if both CCS pumps lA-A and lB-B (aligned to CCS Header 1A) are not running, close SEP HEAT EXCHANGER A CCS SUPPLY (0-FCV-70-1 97)"'with the following Table 1. 6.3 "2. Prepare CCS for recirculation mode by: 2-114-15 a. Start all available CCS pumps.b. Ensure RHR HX 1 (2)A OUTLET 1 (2)-FCV-70-156 valve(s) are open.c. Ensure RHR HX 1 (2)B OUTLET 1(2)-FCV-70-153 valve is throttled to 5,000 gpm on Accident Unit.dl. If the non-accident is using RHR and with only one (1)CCS pump supplying CCS HX C, while maintaining at least 5,000 gpm CCS flow to the RHR HX on the Accident Unit, ensure the Non-Accident Unit RHR HX 1 (2)B OUTLET 1 (2)-FCV-70-153 valve is throttled to approximately 2,725 gpm (or whatever is achievable).
d2. If the non-accident is using RHR and with two (2) CCS pumps supplying CCS HX C, while maintaining at least 5,000 gpm CCS flow to the RHR HX on the Accident Unit, ensure the Non-Accident Unit RHR HX 1 (2)B OUTLET I (2)-FCV-70-1 53 valve is throttled to approximately 5,000 gpm.e. For a LOCA on Unit 1 Only, if both CCS pumps IA-A and lB-B (aligned to CCS Header 1A) are not running, close SFP HEAT EXCHANGER A CCS SUPPLY (0-F CV-70-1 97)" El1-7 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al 14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaNumber Section 8.3.1.1 was updated to describe provisions for manual loading of a second EROW pump on each diesel generator when a unit is in a shutdown condition.
This is accomplished by adding the phrase, "with one exception:" to the last line of the last paragraph of Section 8.3.1.1 on page 8.3-25 (Al113) and by inserting the following paragraph after the newly inserted phrase above: 16. Sectin1. I one unit is on RHR cooling and has been shutdown for not more 2-114-16 than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and a LOCA occurs on the other unit with a concurrent loss of offsite power, the loss of one train as a single failure would require that three ERCW pumps be powered from the remaining train to provide the required heat removal. Therefore control features are provided to allow the manuai loading of a second ERCW pump on each diesel generator when a unit is in a_____shutdown condition." For Table 5.1-1, "System Design and Operating Parameter," change the values for "Total System Volume Including Pressurizer
- 17. Table 5.1-1 and Surge Line, ft 3"' and "System Liquid Volume, Including 2-114-17 Pressurizer Water at Maximum Guaranteed Power, ft 3 , from"12,145" and "11,789" to "11,671" and "10,929," respectively.
- 18. Figure Replace Figure 9.3-21 with new figure. 2-114-18_____ 9.3-21 Revise Table 9.3-5 to add Notes 1 and 2 at the end of the table on sheet 7 of 7 as follows: "Notes: 19. Table 9.3-5 2-114-19 1) During preoperational testing, only 41.5 gpm was achieved.2) During preoperational testing, the two 75 gpm orifices only_____ __________
achieved_73.3_gpm and_72.4_gpm respectively."_____
El1-8 ENCLOSURE 1 WBN Unit 2 FSAR A114 Summary Listing of Al14 FSAR Changes Item hangeChange INem CAngea Change Description Package No. AreaN umber 1. For Section 14.2.10.1, perform the following because the initial U2 core load monitoring differs from what was monitored for initial Ul core load: a. In the 6th paragraph, delete the number "8" from "...nucleus of 8 fuel assemblies..." b. In the 8th paragraph, delete the word, "eight" from ".nucleus of eight fuel assemblies..." Section 20. 14.2.10.1
- c. In the 9th paragraph, item (1), delete the number "8" from the 2-114-20 Table 14.2-2 "...nucleus of 8 fuel assemblies..." d. In the 9th paragraph, item (2), delete the number "8" from".nucleus of 8 fuel assemblies..." 2. For Table 14.2-2 (Sheet 3 of 39)In the TEST METHOD, 5th sentence, delete the word "eight" from "... nucleus of eight assemblies..." 1. In ESAR Section 6.1.3.3, delete the period at the end of the first sentence of the second paragraph and add "which bounds the 2.585 x 106 lbs of ice assumed in the current containment analysis." Section 6.1 2. In FSAR Section 6.2.1.1.1 (FSAR page 6.2.1-1 ), change the 21 Section 6.2 design basis blowdown energy identified in assumption (1) from 2142 21 Section 6.7 "314.9 X 106 Btu" to "315.5 x 106 Btu." 2142 Section 6.8 3. In FSAR Section 6.2.1.1.1 (ESAR page 6.2.1-1), change the design basis blowdown mass identified in assumption (1) from"498.1 x 10 Ib" to "498.9 x 10 3 lb." El1-9 ENCLOSURE 1 WBN Unit 2 FSAR Al114 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaNumber
- 4. In the first sentence of the second paragraph of FSAR Section 6.2.1.2 (FSAR page 6.2.1-3), change the wording "The design internal pressure for the containment is 13.5 psig," to "The maximum internal pressure for the containment is 15.0 psig." 5. In FSAR Section 6.2.1.3.3 (FSAR page 6.2.1-5), change the amount of ice identified in assumption (2) from "2.33 x 106 lbs" to "2.585 x 106 lbs." 6. In FSAR Section 6.2.1.3.3 (FSAR page 6.2.1-6), change the RHR spray initiation time identified in the last sentence of the second paragraph of assumption (12) from "4346.7 seconds" to"3600.0 seconds." Secion6.17.
In FSAR Section 6.2.1.3.3 (FSAR page 6.2.1-7), change the 21. Section 6.2 component cooling system heat exchanger UA identified in the (con.) Sctio 6.7 last sentence of assumption (14) from "5.778 x 106 Btulhr-°F" to 2-1 14-21 Sectin 6.8 "3.17 x 106 Btulhr-°F.
- 8. In FSAR Section 6.2.1.3.3 (ESAR page 6.2.1-7), change the essential raw cooling water flow rate to the component cooling hear exchanger identified in the last sentence of assumption (22) from "6250 gpm" to "3500 gpm." 9. In FSAR Section 6.2.1.3.3 (ESAR page 6.2.1-8), change the maximum calculated containment pressure occurs from "12.40 psig" to "1 1.73 psig." 10. In FSAR Section 6.2.1.3.3 (ESAR page 6.2.1-8), change the time that the maximum calculated containment pressure occurs from "approximately 4346 seconds" to "approximately 3600 seconds." E1-10 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description IPackage No. Aea INumber 11. In FSAR Section 6.2.1.3.6 (FSAR page 6.2.1-26), move the header for the subsection entitled "Post-Reflood Mass and Energy Release Data" from the very bottom of page 6.2.1-26 to the top of page 6.2.1-27.12. In FSAR Section 6.2.1.3.8 (FSAR page 6.2.1-30) revise the paragraph discussing the energy release from the zirc-water reaction so the referenced "WCAP-10325-P-A" is not split over two lines.13. On FSAR Table 6.2.1-1, Page 2 of 2, (FSAR page 6.2.1-51)change the area of slab 13 from "75,860 ft 2 to "75,865 ft 214. Revise the values provided on FSAR Table 6.2.1-3 (FSAR page 6.2.1-53) for the Energy Balances and the Approximate End of Reflood time with the revised values provided by Westinghouse in WBT-D-5395.
- 15. Revise the values included on FSAR Table 6.2.1-4 (FSAR page 6.2.1-54) for the Energy Balances, the Approximate Ice Meltout Time and the Approximate Time of Peak Pressure Section 6.1 with the revised values provided by Westinghouse in WBT-D-21. Section 6.2 5395. Also, correct the note to indicate the energy content of 2142 (cont.) Section 6.7 the sump includes active and inactive regions.Section 6.8 16. On FSAR Table 6.2.1-5 (FSAR page 6.2.1-55) add the words"LOTIC1 Model" to the title of the table.17. On ESAR Table 6.2.1-15 (ESAR page 6.2.1-67) add footnote 2 to the table to state "Analysis value includes an additional 13 psi internal steam generator pressure drop." Also, add a reference to footnote 2 to the "Initial Steam Generator Steam Pressure" parameter.
- 18. Revise the values provided on FSAR Table 6.2.1-16 (FSAR pages 6.2.1-68 through 6.2.1-73) for the Double-Ended Pump Suction Guillotine Break Slowdown Mass and Energy Releases for Break Side 1 and Break Side 2 with the revised values provided on Insert A.19. Revise the values provided on FSAR Table 6.2.1-17 (FSAR pages 6.2.1-74 through 6.2.1-80) for the Double-Ended Pump Suction Guillotine Break Reflood Mass and Energy Releases With Minimum Safety Injection for Break Side 1 and Break Side 2 with the revised values provided on Insert B.El-Il ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaNumber
- 20. Revise the values provided on FSAR Table 6.2.1-18 (FSAR pages 6.2.1-81 through 6.2.1-82) for the Double-Ended Pump Suction Guillotine Break With Minimum Safety Injection Principal Parameters During Reflood with the revised values provided on Insert C.21. Revise the values provided on FSAR Table 6.2.1-19 (FSAR pages 6.2.1-83 through 6.2.1-85) for the Double-Ended Pump Suction Guillotine Break Post-Reflood Mass and Energy Releases With Minimum Safety Injection for Break Side 1 and Break Side 2 with the revised values provided on Insert D.22. On FSAR Table 6.2.1-20, Page 1 of 2 (FSAR page 6.2.1-86), change the decay heat value at 15 seconds from "0.477187" to ".0477187." 23. On FSAR Table 6.2.1-25 (ESAR page 6.2.1-107), change the time given for "End of Slowdown" from "26.8" to "27.0," for"Accumulators Empty" from "66.700" to "66.2" and for "End of Reflood" from "239.8" to "243.6." Section 6.1 21. Section 6.2 24. Revise the Mass Balance values provided on FSAR Table (cont.) Section 6.7 6.2.1-26a (FSAR page 6.2.1-108) for the Double-Ended Pump 2142 Section 6.8 Suction Guillotine Break With Minimum Safety Injection with the revised values provided on Insert E.25. Revise the Energy Balance values provided on FSAR Table 6.2 1-26b (FSAR page 6.2.1-1 09) for the Double-Ended Pump Suction Guillotine Break With Minimum Safety Injection with the revised values provided on Insert F.26. Replace FSAR Figure 6.2.1-1.27. Replace FSAR Figure 6.2.1-2a.28. Replace FSAR Figure 6.2.1-2b.29. Replace ESAR Figure 6.2.1-3.30. Replace FSAR Figure 6.2.1-4.31. Replace FSAR Figure 6.2.1-4a.E1-12 ENCLOSURE 1 WBN Unit 2 FSAR A114 Summary Listing of Al14 FSAR Changes Item hangeChange Item CAngea Change Description Package No. AreaNumber
- 32. In FSAR Section 6.7.4.1 (FSAR page 6.7-16) change the amount of ice identified in Interface Requirement (4) from"2.33 x 106 pounds" to "2.585 x 106 pounds." 33. In FSAR Section 6.7.6.1 (ESAR page 6.7-22) change the amount of ice identified in Design Condition (2)(A)(ii) from"2.33 x 106 Ibs" to "2.585 x 106 lbs." Section 6.1 34. On FSAR Table 6.7-18, Sheet 2 of 2 (FSAR page 6.7-101)21. Section 6.2 change the minimum amount of ice identified in Section 3.1 2142 (cont.) Section 6.7 from "2.33 x 106 Ibs" to "2.585 x 106 lbs." 2142 Section 6.8 35. In FSAR Section 6.8.3 (FSAR page 6.8-2), change value for peak containment pressure from "12.40 psig" to "11.73 psig." 36. In FSAR Section 6.8.3 (FSAR page 6.8-2), change the time that the maximum calculated containment pressure occurs from "approximately 4346 seconds" to "approximately 3600 seconds." For FSAR Table 10.1-1, Sheet 5 of 5, add valve mark numbers 22. Table 47W400-A3796, 47W400-A3797, 47W400-A3798, 47W400- 2-114-22 10.1-1 A3799, 47W400-A3800 and associated information for the new Unit 2 Main Steam Safety Valves (MSSVs).1. In ESAR Section 6.2.1.3.10 (FSAR page 6.2.1-34), under the Sectionsubsection entitled "Pipe Break Blowdowns
-Spectra and 6.2.1Assumptions," replace the last sentence of assumption 2 with 6.2.1the sentence included in insert as follows: Tables 6.2.1-39 "An allowance of 8.5 seconds is assumed for feedwater line 6.2.1-41isolation by the air-operated feedwater regulation valve or 13.5 6.2.1-43 seconds by the motor operated main feedwater isolation valve 6.2.1-44 including generation, processing, and delay, of the isolation 23. signal and valve closure. 2-114-23 Figures 2. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-34), under the 6.2.1-69 subsection entitled "Pipe Break Blowdowns
-Spectra and 6.2.1-70 6.2.1-71 Assumptions," replace the words "diesel generator" in the first 6.2.1-72 sentence of assumption 3 with "train of electrical power." 6.21- 3.3 In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-34), under the 6.2.1-74 subsection entitled "Pipe Break Blowdowns
-Spectra and Assumptions," replace the word "isolation" with "regulation" and the abbreviation "FlV" with "FRY" in assumption 6.E1-13 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Itm Cag Change Item CAngea Change Description Package No. j AreaN umber 4. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-35), under the subsection entitled "Single Failure Effects," replace the paragraph in item 2 with the paragraph included in insert as follows: 'The additional mass inventory in the feedwater line that would not be isolated from the steam generator following main feedwater isolation can flash into steam and pass through the steam generator and exit out the break. Failure of the air-operated feedwater regulation valve results in an increase of 5 seconds for main feedwater isolation by the motor-operated feedwater isolation valve, but also results in a decrease in the feedwater piping volume that is not isolated from the steam generator.
The feedwater regulation valve closes in no more Section than 6.5 seconds and the feedwater isolation valve closes in 6.2.1 no more than 11.5 seconds precluding any additional feedwater from being pumped into the steam generator." Tables 6.2.1-39 5. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-36), under the 6.2.1-41 subsection entitled "Worst-Case Mass and Energy Releases," 6.2.1-43 replace the abbreviation "FlV" with "MSIV" in the description of 6.2.1-44 case 1.23. 2-114-23 Figures 6. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-36), under the 6.2.1-69 subsection entitled 'Maximum Containment Temperature 6.2.1-70 Analysis for Steam Line Break," replace the abbreviation 6.2.1-71 "LOTIC" with "LOTIC-3" in the last sentence of the first 6.2.1-72 paragraph.
6.2.1-73 6.2.1-74 7. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-37), under the subsection entitled "Containment Transient Calculations," replace the words "LOTIC at the 30% power level" with"LOTIC-3 at the full power and 30% power levels" in the last sentence of assumption 10.8. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-37), under the subsection entitled "Containment Transient Calculations," replace the word "limited" with "limiting" at the end of the third sentence of assumption 11.9. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-38), under the subsection entitled "Large Break," change the calculated peak temperature from "324.3°F
to "324.4°F
and the word"feedwater" to "steamline" in the first sentence.E1-14 ENCLOSURE1I WBN Unit 2 FSAR AII4 Summary Listing of A114 FSAR Changes Item hangeChange Ntem CAngea Change Description Package No. AreaNumber
- 10. In FSAR Section 6.2.1.3.10 (FSAR page 6.2.1-38), under the subsection entitled "Small Break,' change the peak temperature in the second sentence of the first paragraph from "325.1 0 F" to"325.0OF".
- 11. On FSAR Table 6.2.1-39 (FSAR pages 6.2.1-137 and 6.2.1-138), revise the title of Run 1 on both pages by changing the abbreviation "MFIV" with "MSIV." 12. On FSAR Table 6.2.1-39 (FSAR pages 6.2.1-137 through 6.2.1.142), replace the values provided for Run 1, 2 and 3 with the values provided on Inserts C, D and E, respectively.
Section 6.2.1 13. On FSAR Table 6.2.1-41 (FSAR page 6.2.1-144), change the line break description "100.6% Power -Feedwater Isolation Tables Valve (FWlV) Failure" to "100.6% Power -Feedwater 6.2.1-39 Regulation Valve (FRV) Failure." 6.2.1-41 6.2.1-43 14. On FSAR Table 6.2.1-43 (FSAR page 6.2.1-146), change the 6.2.1-44 case "1.4 ft, 100.6% Power- FWIV Failure" to "1.4 ft 2 , 100.6%23. Power -FRV Failure." 2-114-23 Figures 6.2.1-69 15. On FSAR Table 6.2.1-43 (FSAR page 6.2.1-146), revise the 6.2.1-70 values for "Maximum Lower Compartment Temperature
(°F)" 6.2.1-71 and "Time, Tmax (sec)" values for the Large Break Analysis 6.2.1-72 cases.6.2.1-73 6.2.1-74 16. On FSAR Table 6.2.1-44 (FSAR page 6.2.1-147), revise the values for "Maximum Lower Compartment Temperature
(°F)" and "Time, Tmax (sec)" for the Small Break Analysis cases.17. On FSAR Figure 6.2.1-69 (FSAR page 6.2.1-219), change the title from "Compartment Temperatures 1.4 ft 2/Loop, 100.6%Power FIV Failure" to "Compartment Temperatures 1.4 ft 2/Loop, 100.6% Power MSIV Failure" and replace the figure.18. On FSAR Figure 6.2.1-70 (FSAR page 6.2.1-220), change the title from "Lower Compartment Pressure 1.4 ft 2/Loop, 100.6%Power FIV Failure" to "Lower Compartment Pressure 1.4 ft 2/Loop, 100.6% Power MSIV Failure" and replace the figure.E1-15 ENCLOSURE1I WBN Unit 2 FSAR AI14 Summary Listing of Al14 FSAR Changes Item hangeChange Ntem CAngea Change Description Package No. AreaN umber Section 19. On FSAR Figure 6.2.1-71 (FSAR page 6.2.1-221), replace the 6.2.1 figure.Tables 20. On FSAR Figure 6.2.1-72 (FSAR page 6.2.1-222), replace the 6.2.1-39 figure.6.2.1-41 6.2.1-43 21. On FSAR Figure 6.2.1-73 (FSAR page 6.2.1-223), replace the 6.2.1-44 figure.23. 2-114-23 Figures 22. On FSAR Figure 6.2.1-74 (FSAR page 6.2.1-224), replace the 6.2.1-69 figure.6.2.1-70 6.2.1-7 1 6.2.1-72 6.2.1-73 6.2.1-74 E1-16 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hangeChange INem CAngea Change Description Package_____ _________N urnber 1. In FSAR Section 9.2.6.1 (FSAR page 9.2-34), add the paragraph from the insert below after the first paragraph.
'When the CSTs are intact and offsite power is available, the inventory available in the CSTs plus makeup from the additional make-up water treatment plant and the demineralized water storage tank (FSAR Section 10.4), is capable of supplying clean water to support maintaining the plant on auxiliary feedwater for longer than seven hours without the need to transfer the AFW pump suction to ERCW.No credit is taken for this additional water in the design and safety evaluations of condensate storage or AFW." 2. In FSAR Section 9.2.6.1 (FSAR page 9.2-34), add the sentence from Insert B after the first sentence of the last paragraph."The supply from the additional make-up water treatment plant and the demineralized water storage tank and associated Sections piping are not engineered safety features and are not 9.2.6.1 seismically qualified." 9.2.6.3 24. 10.4.9.2 3. In FSAR Section 9.2.6.3 (FSAR page 9.2-35), insert the words 2142"for either unit" after the words "auxiliary feedwater" in the 2-144 Tablefourth sentence of the first paragraph.
10.4-1 4. In FSAR Section 9.2.6.3 (FSAR page 9.2-35), replace the words "an extreme emergency" with the word "events" in the first sentence of the second paragraph.
- 5. In FSAR Section 9.2.6.3 (FSAR page 9.2-35), delete the words "and its connecting piping" from the third sentence of the third paragraph.
- 6. In ESAR Section 9.2.6.3 (FSAR page 9.2-35), add the sentence "The AFW piping can accommodate water whose temperature is in the range of 40°F to 1 30°F to the end of the third paragraph.
- 7. In FSAR Section 10.4.9.2 (ESAR page 10.4-34), change the temperature of "120°F to "130°F in the first sentence of the fourth paragraph.
- 8. On FSAR Table 10.4-1 (ESAR page 10.4-39), change the design temperature of "120°F" to "130°F.E1-17 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of Al14 FSAR Changes Item hang F ]Change Item Areange Change Description Package No. Area_ Number 1. In FSAR Section 6.7.14.3, revise the title of the subsection entitled "Sublimation" to "Sublimation
-Historical." 2. In FSAR Section 6.7.14.3, insert the paragraph from the insert as provided below before the first paragraph of the newly titled subsection "Sublimation
-Historical."The following information was developed during the design and initial operation of the ice condenser system. Actual sublimation rates have been established during the operation of Watts Bar and are discussed in the Section below entitled"Sublimation
-Operational." 3. In FSAR Section 6.7.14.3, insert the new subsection entitled"Sublimation
-Operational" from the insert as shown below after the last paragraph of the newly titled subsection"Sublimation-Historical."Sublimation
-Operational The method used for determining the sublimation rate is from cycle to cycle ice basket weighing.
The as-left basket weight is 25. Section compared to the as-found basket weight in the next cycle for 2-114-25 6.7.14.3 the same basket. Overall trends for the ice bed at large and on a row group basis are also used to validate the sublimation rate. Historical data for Watts Bar Unit 1 and for the Sequoyah Nuclear Plant have shown cycle to cycle sublimation rates of around three percent. The selection of six percent is based on engineering judgment to provide a large safety margin.The surveillance acceptance criteria contain a sublimation allowance of six percent. The value does not include a margin for measurement uncertainty.
Instrument uncertainty must be added to the surveillance requirement ice weight value to determine an acceptable basket weight. The allowance for instrument uncertainty is approximately
+15 lbs.The Ice Bed Temperature is maintained between 15°F and 20°F during plant operation.
The empirical sublimation rates described above are the results of operating in this temperature range. Procedures for ice bed temperature monitoring recommend the implementation of actions if the mean ice bed temperature exceeds 19°F. Procedures require actions to restore normal operating temperatures when ice bed temperatures reach 23°F.E1-18 ENCLOSURE1I WBN Unit 2 FSAR Al14 Summary Listing of A114 FSAR Changes Change Item Change Change Description Package No. Area Nme 1. Revise FSAR Table 3.2-2 entry on page 9 of 18 to include Coil Units for Unit 2.2. Revise Note 12 on FSAR pages 3.2-27 & 3.2-28 to add, "Unit 2 26. Table 3.2-2 Upper Compartment Cooler coils." 2-1 14-26 Section 3.2 3. Revise Note 3 on ESAR page 3.2-37 to delete the phrase,"and 2," from the second line of the top paragraph and add"Unit 2 Upper Compartment Cooler coils." In FSAR Section 9.2.2.4, reword the four examples as follows: (1) During normal operation, the CCS can supply the highest flow demand of both units in Startup with a flow requirement of approximately 22,950 gpm and remove the highest heat removal demand of one unit in Hot Shutdown and the other unit in Cold Shutdown with a heat load of approximately 192.1 MBtu/hr.(2) Under design basis accident conditions with offsite power available, the CCS can supply the highest flow demand of one unit in Startup and the other unit in LOCA-Recirculation with a flow requirement of approximately 21,600 gpm and remove the highest heat removal demand of one unit in Cold SectionShutdown and the other unit in LOCA-Recirculation with a 27 9.2.2.4 heat load of approximately 154.5 MBtu/hr. 2-114-27 (3) Under design basis accident conditions with a LOOP coupled with a Loss of Train A, CCS Train B can supply the highest flow / heat removal demand of one unit in Hot Shutdown and the other in LOCA-Recirculation with a flow requirement of approximately 10,200 gpm and a heat load of approximately 145 MBtulhr.(4) Under design basis accident conditions with a LOOP coupled with a Loss of Train B, CCS Train A can supply the highest flow I heat removal demand of one unit in Hot Shutdown and the other in LOCA-Recirculation with a flow requirement of approximately 15,800 gpm and a heat load of approximately 170 MBtulhr.E1-19 ENCLOSURE 2 WBN Unit 2 FSAR Al14 Summary of Redacted Pages IChapter I~g,, Section No. IFigure No.I Basis For Redaction I 1 1.2-15 1.2 1.2-1 Security Related, 10CFR2.390(d)(1) 1 1.2-16 1.2 1.2-2 Security Related, 10CFR2.390(d)(1) 1 1.2-17 1.2 1.2-3 Security Related, 10CFR2.390(d)(1) 1 1.2-18 1.2 1.2-4 Security Related, 10CFR2.390(d)(1) 1 1.2-19 1.2 1.2-5 Security Related, 10CFR2.390(d)(1) 1 1.2-20 1.2 1.2-6 Security Related, 10CFR2.390(d)(1) 1 ___1.2-21 1.2 1.2-7 Security Related, 10CFR2.390(d)(1) 1 1.2-22 1.2 1.2-8 Security Related, 10CFR2.390(d)(1) 1 1.2-23 1.2 1.2-9 Security Related, 10CFR2.390(d)(1) 1 1.2-24 1.2 1.2-10 Security Related, 10CFR2.390(d)(1) 1___ 1.2-25 1.2 1.2-11 Security Related, 10CFR2.390(d)(1) 1 1.2-26 1.2 1.2-12 Security Related, 10CFR2.390(d)(1
)1 1.2-27 1.2 1.2-13 Security Related, 10CFR2.390(d)(1) 1 1.2-28 1.2 1.2-14 Security Related, 10CFR2.390(d)(1
)1 1.2-29 1.2 1.2-15 Security Related, 10CFR2.390(d)(1) 2 2.2-7 2.2 2.2-1 Security Related, 10CFR2.390(d)(1
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)2 24-81 .42.4-40g Security Related, 10OCFR2.390(d)(1) 2.4-181__
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)E2-1I ENCLOSURE 2 WBN Unit 2 FSAR Al14 Summary of Redacted Pages Ichapter Page(S)I Section No. IFigure No.I Basis For RedactionI 2 2.5-934 2.5 2.5-592 Security Related, 10CFR2.390(d)(1) 3 3.5-53 3.5 3.5-3 Security Related, 10CFR2.390(d)(1) 3 3.5-54 3.5 3.5-4 Security Related, 10CFR2.390(d)(1) 3 3.6-73 3.6 3.6-21 Security Related, 10CFR2.390(d)(1) 3 3.6-74 3.6 3.6-22 Security Related, 10CFR2.390(d)(1) 3 3.6-75 3.6 3.6-23 Security Related, 10CFR2.390(d)(1
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)3 3.7-222 3.7 3.7-44 Security Related, 10CFR2.390(d)(1) 3 3.8.3-60 3.8.3 3.8.3-6 Security Related, 10CFR2.390(d)(1) 3 3.8.3-61 3.8.3 3.8.3-7 Security Related, 10CFR2.390(d)(1) 3 3.8.4-94 3.8.4 3.8.4-2 Security Related, 10CFR2.390(d)(1
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)3 3.8.4-120 3.8.4 3.8.4-28 Security Related, 10CFR2.390(d)(1
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)6 6.2.2-24 6.2.2 6.2.2-4 Security Related, 10CFR2 .390(d)(1) 6 6.2.3-76 6.2.3 6.2.3-4 Security Related, 10CFR2.390(d)(I) 6 6.2.3-77 6.2.3 6.2.3-5 Security Related, 10CFR2.390(d)(1
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)8 8.2-30 8.2 8.2-3 Security Related, 10CFR2.390(d)(1)
E2-2 ENCLOSURE 2 WBN Unit 2 FSAR Al14 Summary of Redacted Pages SChapter I~g(S Section No. jFigure No.1 Basis For Redaction I 8 8.2-31 8.2 8.2-4 Security Related, 10CFR2.390(d)(1) 8 8.2-44 8.2 8.2-11 Security Related, 10CFR2.390(d)(1
)8 8.3-97 8.3 8.3-1 Security Related, 100FR2.390(d)(1) 8 8.3-99 8.3 8.3-2 Security Related, 100FR2.390(d)(1) 8 8.3-1 00 8.3 8.3-3 Security Related, 10CFR2.390(d)(1) 8 8.3-1 02 8.3 8.3-4b Security Related, 10CFR2.390(d)(1
)8 8.3-205 8.3 8.3-46 Security Related, 100FR2.390(d)(1) 8 8.3-218 8.3 8.3-59 Security Related, 10CFR2.390(d)(1) 9 9.2-211 9.2 9.2-40 Security Related, 10CFR2.390(d)(1
)9 9.4-276 9.4 9.4-21 Security Related, 10CFR2.390(d)(1) 9 9.4-280 9.4 9.4-22c Security Related, 10CFR2.390(d)(1
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)12 12.3-39 12.3 12.3-1 Security Related, 10CFR2.390(d)(1) 12 12.3-40 12.3 12.3-2 Security Related, 10CFR2.390(d)(1) 12 12.3-41 12.3 12.3-3 Security Related, 10CFR2.390(d)(1) 12 12.3-42 12.3 12.3-4 Security Related, 10CFR2.390(d)(1) 12 12.3-43 12.3 12.3-5 Security Related, 10CFR2.390(d)(1 12 12.3-44 12.3 12.3-6 Security Related, 10CFR2.390(d)(1) 12 12.3-45 12.3 12.3-7 Security Related, 10CFR2.390(d)(1) 12 12.3-46 12.3 12.3-8 Security Related, 10CFR2.390(d)(1) 12 12.3-47 12.3 12.3-9 Security Related, 10CFR2.390(d)(1) 12 12.3-48 12.3 12.3-10 Security Related, 10CFR2.390(d)(1) 12 12.3-49 12.3 12.3-11 Security Related, 10CFR2.390(d)(1) 12 12.3-50 12.3 12.3-12 Security Related, 10CFR2.390(d)(1) 12 12.3-51 12.3 12.3-13 Security Related, 10CFR2.390(d)(1) 12 12.3-52 12.3 12.3-14 Security Related, 10CFR2.390(d)(1) 12 12.3-53 12.3 12.3-15 Security Related, 10CFR2.390(d)(1) 12 12.3-54 12.3 12.3-16 Security Related, 10CFR2.390(d)(1) 12 12.3-55 12.3 12.3-17 Security Related, 10CFR2.390(d)(1) 12 12.4-7 12.4 12.4-1 Security Related, 10CFR2.390(d)(1)
E2-3 ENCLOSURE 3 WBN Unit 2 FSAR Al14 List of Files and File Sizes on the Security-Related OSM (OSM #1)E3-1 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 113 -List of Files on Security-Related OSM File Name File Size -Bytes TVAWBN-2_FSAR_Files___
_________001 _TVAWBFSARTOC.
pdf 381,627 002_TVAWBFSARLRP.pdf 97,688 003_TVA_WB_FSAR_Section_1I.pdf 4,268,834 004_TVAWBFSARSection_2_A.pdf 17,667,127 005_TVAWBFSARSection 2 B Part 1 of_9.pdf 41,038,695 005 TVAWB FSARSection 2 B Part 2 of 9.pdf 16,706,619 005 TVAWBFSARSection 2 B Part 3 of 9.pdf 48,335,648 005 TVAWBFSARSection 2 B Part 4 of_9.pdf 63,802,614 005 TVAWBFSARSection 2 B Part 5 of 9.pdf 42,822,720 005 TVA WBFSARSection 2 B Part 6 of_9.pdf 49,063,796 005 TVAWBFSARSection 2 B Part 7 of 9.pdf 45,916,261 005_TVAWBFSARSection 2 B Part 8 of_9.pdf 47,912,564 005 TVAWBFSARSection 2 B Part 9 of 9.pdf 21,865,668 006 TVA WBFSARSection_2_C.pdf 1,038,363 007 TVAWBFSARSection_2_D.pdf 30,355,014 008_TVAWBFSARSection_2_E.
pdf 46,980,034 009_TVAWBFSARSection_3_A.pdf 1,882,439 010 TVAWBFSARSection_3_B.
pdf 7,109,939 011 TVAWBFSARSection_3_C.pdf 29,387,762 012 TVAWBFSAR Section_3_D.pdf 10,776,729 013 TVAWBFSARSection_4.pdf 25,317,862 014 TVAWBFSARSection_5.pdf 9,327,773 015 TVAWBFSARSection_6_A.pdf 29,912,646 016 TVAWBFSARSection_6 B.pdf 9,658,746 017 TVAWBFSARSection_7.pdf 13,865,345 018 TVAWBFSAR Section_8.pdf 29,249,257 Page 1 of 4 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 113 -List of Files on Security-Related OSM File Name File Size -Bytes 019 TVAWBFSARSection_9_A.pdf 23,442,486 020 TVAWBFSARSection_9_B.pdf 15,274,264 021 TVAWBFSAR Section_10.pdf 13,729,969 022 TVAWBFSARSection_
11 .pdf 3,254,054 023 TVAWBFSAR S ectionl 12. pdf 5,562,704 024 TVAWBFSAR Sectionl 13.pdf 3,116,887 025 TVA_WB_FSAR_Section_
14.pdf 4,999,374 02 V_WBFAeto_I5pd 28,010,208 02 V _WBFAeto_I5pd 35,918,011 02 V_WBFAeto .d 126,138 028 TVAWBFSARSection_
- 17. pdf 128,255 Total 778,304,120 TVA_WBN-2_Oversized_FSAR_Figures______________
001 TVAWBFSARFigure_2.5_3.pdf 1,757,743 002_TVA WB ESARFigure 2.5 11 .pdf 1,689,538 003_TVAWBFSARFigure 2.5 71 .pdf 2,263,087 004 TVAWBFSARFigure 2.5 222.pdf 909,429 005 TVAWBFSARFigure 2.5 281_1.pdf 2,155,627 006_TVA_WB_FSAR_Figure 2.5 281_2.pdf 2,117,562 007_TVA_WB_FSARFigure
2.5 549_1
.pdf 3,600,807 008_TVAWBFSARFigure 2.5 549_2.pdf 3,989,180 009_TVAWBFSARFigure 2.5 549_3.pdf 2,863,719 010 TVAWBFSAR Figure 2.5 549_4.pdf 2,809,599 011 TVAWBFSARFigure 2.5 550.pdf 1,803,985 012 TVAWBFSARFigure 2.5 551.pdf 1,996,869 013 TVAWBFSARFigure
.2.5 554 l.pdf 3,081,060 Page 2 of 4 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 113 -List of Files on Security-Related OSM File Name File Size -Bytes 014_TVAWBFSARFigure 2.5 554_2.pdf 1,996,707 015_-TVAWBFSARFigure 2.5 555.pdf 1,993,312 016_TVAWBFSARFigure 2.5 556.pdf 2,998,087 017_TVAWBFSARFigure 2.5 571_1.pdf 844,484 018_TVA WB FSARFigure 2.5 571_2.pdf 3,128,329 019_TVA WB FSARFigure 2.5 571_3.pdf 3,284,555 020_TVA WB FSARFigure 2.5 571_4.pdf 2,142,316 021_TVA WB FSARFigure 2.5 572.pdf 2,196,945 022_TVA WB FSARFigure 2.5 573.pdf 2,013,286 023_TVA WB FSARFigure 2.5 576_1l.pdf 3,238,525 024_TVA WB FSARFigure 2.5 576_2.pdf 2,151,750 025_TVA WBFSAR Figure 2.5 577.pdf 2,207,622 026_TVAWBFSARFigure 2.5 578.pdf 2,080,032 027_TVAWBFSARFigure 2.5 579.pdf 2,308,985 028 TVAWBFSARFigure 2.5 583.pdf 2,487,346 029_TVAWB_FSAR_Figure 2.5 588.pdf 2,528,515 030 TVAWBFSARFigure 2.5 589.pdf 2,480,438 031_TVAWBFSARFigure 2.5 594.pdf 13,054,127 032_TVAWBFSARFigure 2.5 595.pdf 2,323,267 033_TVAWB_FSARFigure 2.5 596.pdf 5,732,107 034_TVAWBFSARFigure 2.5 597.pdf 1,287,336 035_TVAWBFSARFigure 2.5 602.pdf 5,549,537 036_TVAWBFSARFigure 2.5 603.pdf 4,830,835 037_TVAWBFSARFigure 2.5 604.pdf 6,392,279 038_TVAWBFSARFigure 2.5 605.pdf 20,823,108 Total 131,112,035 Page 3 of 4 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 113 -List of Files on Security-Related OSM File Name File Size -Bytes TVA WBN-2_OversizedFSARTable
_____________
001 _TVAWBFSARTable_6.2.4-1 .pdf 1,087,232 Total 1,087,232 Page 4 of 4 ENCLOSURE 4 WBN Unit 2 FSAR A114 List of Files and File Sizes on the Publicly Available OSM (OSM #2)E4-1I ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 114 List of Files on Publicly Available OSM File Name File Size -Bytes TVAWBN-2_FSAR_Files 001 ITVAWBFSARTOC.
pdf "381,627 002_TVAWBFSARLRP.
pdf 97,688 003_TVAWBFSARSection l.pdf 462,502 004_TVAWBFSARSection_2_A.pdf 17,331,214 005_TVAWBFSARSection 2 B Part lof_9.pdf 39,955,058 005_TVAWBFSARSection 2 B Part 2 of_9.pdf 16,706,619 005_TVAWBFSARSection 2 B Part 3 of_9.pdf 48,335,648 005_TVAWBFSARSection 2 B Part 4 of_9.pdf 63,802,614 005_TVAWBFSARSection 2 B Part 5 of_9.pdf 42,822,720 005_-IVAWBFSARSection 2 B Part 6 of._9.pdf 49,063,796 005_TVAWBFSARSection 2 B Part 7of_9.pdf 39,225,659 005_TVAWBFSARSection 2 B Part_8_of_9.pdf 41,654,678 005_TVAWBFSARSection 2 B Part 9 of_9.pdf 21,865,668 006_TVAWBESAR Section_2_C.
pdf 1,038,363 007_TVA WBFSARSection_2 D. pdf 30,355,014 008_TVAWBFSARSection_2_E.pdf 45,601,516 009_TVAWBFSARSection_3_A.pdf 1,591,203 010_TWA_ WBFSAR RSection_3_B.pdf 5,709,324 011_TVA_ WBFSARSection_3_C.pdf 24,556,092 012_TVAWBFSARSection_3_D.pdf 10,508,106 013_TVA_WB_FSAR_Section_4.pdf 25,317,862 014_l-VAWBFSARSection_5.pdf 9,327,773 015_TVAWBFSARSection_6_A.pdf 27,033,047 016_TVAWBFSAR Section_6_B.
pdf 9,658,746 017_TVAWBFSARSection
- 7. pdf 13,865,345 018_TWAWBFSARSection_8.pdf 26,289,115 Note: Byte amounts in italics are redacted files. Pg f Page 1 of 4 ENCLOSURE 4* TA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 114 List of Files on Publicly Available OSM File Name File Size -Bytes 019_fl/AWBFSARSection_9_A.pdf 23,180,653 020_ TVA_ WBFSAR RSection_9_B.pdf 14,059,844 021 TIVAWBFSARSection_
- 10. pdf 13,729,969 022_TVAWBFSARSection_
11 .pdf 3,254,054 023_TVAWBFSARSection_12.pdf 1,295,374 024 TVA WBFSARSection_
13.pdf 3,116,887 025_TVA_WB_FSAR_Section_14.pdf 4,999,374 026_TVAWBESAR_Section_1 5A.pdf 28,010,208 026_TVA WBESARSection_
15B.pdf 35,918,011 027_TVA_WB_ESAR_Section_1
- 6. pdf 126,138 028_TVAWBFSARSection_
17.pdf 128,255 Total 740,375,764 TVAWBN-2_Oversized_FSARFig ures 001 _TVA WBFSARFig ure_2.5_3,.pdf 1,757,743 002_TVAWBFSARFigure 2.51 11 .pdf 1,689,538 003_TVAWBFSARFigure 2.5 71 .pdf 2,263,087 004_TVAWBFSARFigure 2.5 222.pdf 909,429 005_TVAWBFSARFigure
2.5 281_1
.pdf 2,155,627 006_TVAWBFSARFigure 2.5 281_2.pdf 2,117,562 007_TVAWBFSARFigure 2.5 5491 .pdf 3,600,807 008_TVAWB FSARFigure 2.5 549_2. pdf 3,989,180 009_TVAWBFSARFigure 2.5 549_3.pdf 2,863,719 010_TVAWBFSARFigure 2.5 549_4. pdf 2,809,599 011_TVAWBFSARFigure 2.5 550.pdf 1,803,985 012_TVAWB FSARFigure 2.5 551 .pdf 1,996,869 013_TVAWBFSARFigure 2.5 554_1.pdf 3,081,060 Note: Byte amounts in italics are redacted files. Pae2o4 Page 2 of 4 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 114 List of Files on Publicly Available OSM File Name File Size -Bytes 014_TVAWBFSARFigure 2.5 554_2.pdf 1,996,707 016_TVAWB_FSARFigure 2.5 555.pdf 1,993,312 016_TVAWB_FSARFigure 2.5 556.pdf 2,998,087 017_TVA WBFSARFigure 2.5 571 l.pdf 844,484 018_TVAWBFSARFig ure_2.5_571_2,.pdf 3,128,329 019_TVAWBFSARFigure 2.5 571_3.pdf 3,284,555 020_TVAWB_FSARFig ure_2.5_571
- 4. pdf 2,142,316 021_TVAWBFSARFigure 2.5 572.pdf 2,196,945 022_TVAWBFSARFigure 2.5 573.pdf 2,013,286 023_TVA WB FSARFigure 2.5 576_1.pdf 3,238,525 024_TVAWBFSARFigure_2.5_576_2.pdf 2,151,750 025_TVAWBFSARFigure_2.5_577.
pdf 2,207,622 026_TVAWBFSARFig ure_2.5_578,.pdf 2,080,032 027 TVA WBFSARFig ure_2.5_579,.pdf 2,308,985 028_TVAWBFSARFigure_2.5_583.pdf 2,487,346 029_TVAWBFSARFigure_2.5 588.pdf 2,528,515 030_TVAWBFSAR Figure 2.5 589.pdf 2,480,438 031 ITVAWB_FSARFigure 2.5 594.pdf 13,054,127 032_TVAWB_FSARFigure 2.5 595.pdf 2,323,267 033_TVAWB_FSARFigure 2.5 596.pdf 5,732,107 034_TVAWBFSAR Figure 2.5 597.pdf 1,287,336 035_TVA WBFSARFig ure_2.5_602, pdf 5,549,537 036 TVA WBFSARFigure 2.5 603.pdf 4,830,835 037_TVA WB FSARFigure 2.5 604.pdf 6,392,279 038_TVA WB FSARFigure 2.5 605.pdf 20,823,108 Total 131,112,035 Note: Byte amounts in italics are redacted files. ae3o Page 3 of 4 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 114 List of Files on Publicly Available OSM File Name File Size -Bytes TVAWBN-2_Oversized_FSAR_Table
____________
001 _TVAWBFSARTable_6.2.4-1 .pdf 1,087,232 Total 1,087,232 Note: Byte amounts in italics are redacted files. Pge4o4 Page 4 of 4 ENCLOSURE 5 List of Commitments
- 1. In discussions with the NRC Staff, it was determined that the figures would not be updated at this time. The figures will be updated as part of the Unit 1 Updated Final Safety Analysis Report (UFSAR) and Unit 2 FSAR merger during the first update of the Unit I UFSAR after Unit 2 receives an operating license.E5-1