ML102530216

(WBN) - Unit 2 - Final Safety Analysis Report (Fsar), Amendment 100

ML102530216
Person / Time
Site:	Watts Bar
Issue date:	09/01/2010
From:	Bajestani M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML102530216 (32)

Text

Withhold from Public Disclosure Under 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 September 1, 2010 10 CFR 50.4(b)(6) 10 CFR 50.34(b)10 CFR 2.390(d)(1)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391

Subject:

WATTS BAR NUCLEAR PLANT (WBN) -UNIT 2 -FINAL SAFETY ANALYSIS REPORT (FSAR), AMENDMENT 100

References:

1. TVA letter to the NRC dated May 27, 2010, 'Watts Bar Nuclear Plant (WBN) -Unit 2 -Final Safety Analysis Report Amendment 99" 2. TVA letter to the NRC dated May 24, 2010, 'Watts Bar Nuclear Plant (WBN) Unit 2 Final Safety Analysis Report (FSAR) -RegulatoryCommitment Regarding Instrumentation Setpoint Methodology" 3. TVA letter to the NRC dated February 8, 2008, 'Watts Bar Nuclear Plant (WBN) -Unit 2 -Final Safety Analysis Report (FSAR) Red-Line for Unit 2"This letter transmits WBN Unit 2 FSAR Amendment 100 (A100), which reflects changes made since the issuance of Amendment 99 on May 27, 2010 (Reference 1).Enclosure 1 contains a "Summary Listing" of FSAR sections and corresponding Unit 2 change package numbers associated with the Al 00 FSAR changes. Most of these changes were the result of resolutions to Requests for Additional Information.

A portion of the changes provided in A100 satisfies a commitment made in letter dated May 24, 2010 (Reference

2) to incorporate "Instrumentation Setpoint Methodology," which is provided in FSAR Chapter 7.0, "Instrumentation and Controls." A revision to the WBN Unit 2 Technical Specifications will be provided via separate letter to provide consistency with the setpoint methodology changes provided in A100 and Technical Specification Tracking Form 493.With this letter, TVA modifies a commitment previously made in TVA letter dated February 8, 2008 (Reference 3). Modify the previous commitment from, "Prior to Unit 2 fuel load, TVA will submit a combined Unit 1 and Unit 2 UFSARs," to state "TVA will submit a combined Unit 1 and Unit 2 FSAR with the first update of the Unit 1 UFSAR after Unit 2 is licensed." Withhold from Public Disclosure Under 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 September 1, 2010 10 CFR 50.4(b)(6) 10 CFR 50.34(b) 10 CFR 2.390(d)(1)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001

Subject:

Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391 WATTS BAR NUCLEAR PLANT (WBN) -UNIT 2 -FINAL SAFETY ANALYSIS REPORT (FSAR), AMENDMENT 100

References:

1. TVA letter to the NRC dated May 27,2010, 'Watts Bar Nuclear Plant (WBN) -Unit 2 -Final Safety Analysis Report Amendment 99" 2. TVA letter to the NRC dated May 24,2010, 'Watts Bar Nuclear Plant (WBN) Unit 2 Final Safety Analysis Report (FSAR) -Regulatory Commitment Regarding Instrumentation Setpoint Methodology" 3. TVA letter to the NRC dated February 8,2008, 'Watts Bar Nuclear Plant (WBN) -Unit 2 -Final Safety Analysis Report (FSAR) Red-Line for Unit 2" This letter transmits WBN Unit 2 FSAR Amendment 100 (A 100), which reflects changes made since the issuance of Amendment 99 on May 27,2010 (Reference 1). Enclosure 1 contains a "Summary Listing" of FSAR sections and corresponding Unit 2 change package numbers associated with the A 100 FSAR changes. Most of these changes were the result of resolutions to Requests for Additional Information.

A portion of the changes provided in A 100 satisfies a commitment made in letter dated May 24, 2010 (Reference

2) to incorporate "Instrumentation Setpoint Methodology," which is provided in FSAR Chapter 7.0, "Instrumentation and Controls." A revision to the WBN Unit 2 Technical Specifications will be provided via separate letter to provide consistency with the setpoint methodology changes provided in A100 and Technical Specification Tracking Form 493. With this letter, TVA modifies a commitment previously made in TVA letter dated February 8,2008 (Reference 3). Modify the previous commitment from, "Prior to Unit 2 fuel load, TVA will submit a combined Unit 1 and Unit 2 UFSARs," to state "TVA will submit a combined Unit 1 and Unit 2 FSAR with the first update of the Unit 1 UFSAR after Unit 2 is licensed."

U.S. Nuclear Regulatory Commission Page 2 September 1, 2010 FSAR A100 is contained on the enclosed Optical Storage Media (OSM #1) (Attachment 1). The FSAR contains security-related information identified by the designation "Security-Related Information -Withhold Under 10 CFR 2.390." TVA hereby requests this information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A redacted version of the FSAR is contained on OSM #2 (Attachment 2), which is suitable for public disclosure.

Enclosure 2 contains a listing of the FSAR pages that have been redacted.

Enclosure 3 lists the files and file sizes on the security-related OSM (OSM #1), and Enclosure 4 lists the files and file sizes on the publicly available OSM (OSM #2). Enclosure 5 provides a list of commitments made in this submittal.This letter does not close any "Generic Communications." If you have any questions, please contact Bill Crouch at (423) 365-2004.I declare under the penalty of perjury that the foregoing is true and correct. Executed on September 1, 2010.Sincerely, Masoud B e Ktani Watts Bar U it 2 Vice President

Enclosures:

1. WBN Unit 2 FSAR A100, "Summary Listing of A100 FSAR Changes" 2. WBN Unit 2 FSAR A100, "Summary of Redacted Pages" 3. WBN Unit 2 FSAR A100, "List of files and file sizes on the security-related OSM (OSM #1)" 4. WBN Unit 2 FSAR A100, "List of files and file sizes on the publicly available OSM (OSM #2)" 5. WBN Unit 2 FSAR A100, "List of Commitments" Attachments:

1. OSM #1: WBN Unit 2 FSAR Amendment 100 -Security-Related Information -

Withhold Under 10 CFR 2.390 2. OSM #2: WBN Unit 2 FSAR Amendment 100 -Publicly Available Version cc: See Page 3 U.S. Nuclear Regulatory Commission Page 2 September 1, 2010 FSAR A 100 is contained on the enclosed Optical Storage Media (OSM #1) (Attachment 1). The FSAR contains security-related information identified by the designation "Security-Related Information

-Withhold Under 10 CFR 2.390." TVA hereby requests this information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A redacted version of the FSAR is contained on OSM #2 (Attachment 2), which is suitable for public disclosure.

Enclosure 2 contains a listing of the FSAR pages that have been redacted.

Enclosure 3 lists the files and file sizes on the security-related OSM (OSM #1), and Enclosure 4 lists the files and file sizes on the publicly available OSM (OSM #2). Enclosure 5 provides a list of commitments made in this submittal.

This letter does not close any "Generic Communications." If you have any questions, please contact Bill Crouch at (423) 365-2004.

I declare under the penalty of perjury that the foregoing is true and correct. Executed on September 1, 2010. Sincerely, Masoud B 'e tani Watts Bar: U it 2 Vice President

Enclosures:

1. WBN Unit 2 FSAR A 100, "Summary Listing of A 100 FSAR Changes" 2. WBN Unit 2 FSAR A 100, "Summary of Redacted Pages" 3. WBN Unit 2 FSAR A 100, "List of files and file sizes on the security-related OSM (OSM #1)" 4. WBN Unit 2 FSAR A 100, "List of files and file sizes on the publicly available OSM (OSM #2)" 5. WBN Unit 2 FSAR A 100, "List of Commitments" Attachments:

1. OSM #1: WBN Unit 2 FSAR Amendment 100 -Security-Related Information

-Withhold Under 10 CFR 2.390 2. OSM #2: WBN Unit 2 FSAR Amendment 100 -Publicly Available Version cc: See Page 3 U,S. Nuclear Regulatory Commission Page 3 September 1, 2010 cc (Enclosures):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission Page 3 September 1, 2010 cc (Enclosures):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar NuclearPlant 1260 Nuclear Plant Road Spring City, Tennessee 37381 ENCLOSUREI WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number Revise Unit-2 FSAR Section 5.5.11, Sub-Section 5.5.11.3 second paragraph, first sentence to read: "The two rupture 1. Section 5.5.11 discs on the relief tank have a total relief capacity equal to 2-100-01 or greater than the combined capacity of the three pressurizer safety valves." Revise Table 6.2.4-1 as Follows: 1. In Table 6.2.4-1, X-13B, change the valve type of 1-517 from a gate valve ("GA") to a relief valve ("RV").2. In Table 6.2.4-1, X-13C, change the valve type of 1-2. Table 6.2.4-1 512 from a gate valve ("GA") to a relief valve ("RV). 2-100-02 3. In Table 6.2.4-1, X-64, change "31 C-306" to "31-306." Also for X-65, change "31C-308" to "31-308." 4. In Table 6.2.4-1, X-66, change "31C-327" to "31-327." Also for X-67, change "31 C-329" to "31-329." 1. In Section 6.2.6.2(1)(3), change "Testing is performed in accordance with ASME XI." to "Water testing for piping integrity is performed in accordance with ASME XI." 2. In Section 6.2.6.2(11)(1

), change two occurrences of"Pac" to "Pa".3. In Section 6.2.6.2, pg 6.2.6-5, change "Either air, nitrogen or water is used as the pressurizing medium... "to "Either air or nitrogen is used as the pressurizing medium..." 3. Section 6.2.6 2100 4. In Table 6.2.6-2, penetration X-52, delete "1-" from 2-100-03"1-70-100" and "1-70-790." 5. In Table 6.2.6-2, penetration X-56, delete "1-" from"1-67-113" and "1-67-1054D." 6. In Table 6.2.6-3, penetration X-19A, change "FCV63-072" and "FCV 72-044" to "FCV 63-72" and "FCV 72-44." 7. In Table 6.2.6-3, penetration X-19B, change "FCV 63-073" and "FCV 72-045" to "FCV 63-73" and "FCV 72-45." 4. Table 14.2-1 Sheet 66, Delete Item 4 under Test Method 2-100-04 Revise FSAR Table 14.2-1, sheets 48 and 49 to reflect testing methods to demonstrate that each common station

5. Table 14.2-1 service transformer has the capability to carry the load 2-100-05 required to supply ESF loads of one unit under LOCA conditions, in addition to power required for shutting downthe non-accident unit.E1-1 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A 100 FSAR Changes" Item Change Area Change Description Change Package No. Number Revise Unit-2 FSAR Section 5.5.11, Sub-Section 5.5.11.3 second paragraph, first sentence to read: "The two rupture 1. Section 5.5.11 discs on the relief tank have a total relief capacity equal to 2-100-01 or greater than the combined capacity of the three pressurizer safety valves." Revise Table 6.2.4-1 as Follows: 1. In Table 6.2.4-1, X-13B, change the valve type of 1-517 from a gate valve ("GA") to a relief valve ("RV"). 2. In Table 6.2.4-1, X-13C, change the valve type of 1-2. Table 6.2.4-1 512 from a gate valve ("GA") to a relief valve CRY). 2-100-02 3. In Table 6.2.4-1, X-64, change "31 C-306" to "31-306." Also for X-65, change "31C-308" to "31-308." 4. In Table 6.2.4-1, X-66, change "31C-327" to "31-327." Also for X-67, change "31C-329" to "31-329." 1. In Section 6.2.6.2(1)(3), change "Testing is performed in accordance with ASME XI." to "Water testing for piping integrity is performed in accordance with ASME XI." 2. In Section 6.2.6.2(11)(1

), change two occurrences of "Pac"to "Pan. 3. In Section 6.2.6.2, pg 6.2.6-5, change "Either air, nitrogen or water is used as the pressurizing medium ... "to "Either air or nitrogen is used as the pressurizing medium ... " 3. Section 6.2.6 4. In Table 6.2.6-2, penetration X-52, delete "1-" from 2-100-03 "1-70-100" and "1-70-790." 5. In Table 6.2.6-2, penetration X-56, delete "1-" from "1-67-113" and "1-67-10540." 6. In Table 6.2.6-3, penetration X-19A, change "FCV 63-072" and "FCV 72-044" to "FCV 63-72" and "FCV 72-44." 7. In Table 6.2.6-3, penetration X-19B, change "FCV 63-073" and "FCV 72-045" to "FCV 63-73" and "FCV 72-45." 4. Table 14.2-1 Sheet 66, Delete Item 4 under Test Method 2-100-04 Revise FSAR Table 14.2-1, sheets 48 and 49 to reflect testing methods to demonstrate that each common station 5. Table 14.2-1 service transformer has the capability to carry the load 2-100-05 required to supply ESF loads of one unit under LOCA conditions, in addition to power required for shutting down the non-accident unit. E1-1 ENCLOSUREI WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change PackageNo. INumber

1. Revise FSAR Figure 6.2.4-16 to remove the reference to UFSAR Amendment 1.2. On FSAR Table 6.2.4-1, revise the total page numbers on the first 64 pages from 64 to 69; change Page _ of 64 to Page of 69).3. Revise FSAR Table 6.2.6-2 to remove spare penetrations X-23, X-28, X-85A, X-86A, X-86B, X-86C, X-92A, X-92B and X-92C and the containment isolation valves listed for these penetrations.

4. Revise FSAR Table 6.2.4-1 to identify the following test connection valves as being Type A tested during the ILRT: 30-42B/2 (X-60B), 30-43B/2 (X-26C), 30-31 0B/2 (X-26C), 30-44B/2 (X-57B),30-311 B/2 (X-57B), 30-30CB/2 (X-98) and 30-45B/2 (X-102).5. Revise FSAR Table 6.2.4-1 to move the 'A' from the Essential/Non-Essential column to the Appendix J Table 6.2.4-1, Test column for penetrations X-38, X-39C and X-58B.Figure 6.2.4-16, Also, for penetration X-58B, identify the instrument

6. Table 6.2.6-1, line through the penetration as "E" (Essential) in the 2-100-06 Table 6.2.6-2, Essential/Non-Essential column.6. On FSAR Table 6.2.4-1, remove the valve and dP sensor information for penetration X-86D and identify the penetration as spare and Appendix J, Type A tested. Also, change the drawing number for penetration X-86D to 47W331-2 and the drawing number for X-1 02 to 2-47W600-89.

7. On FSAR Table 6.2.4-1, revise the drawing number for penetrations X-25B, X-25C, X-85A and X-85C to 47W331-2.8. On FSAR Table 6.2.4-1, remove the "E" in the Shield Building Penetration column for penetration X-26C.9. On FSAR Table 6.2.4-1, revise the relief valve number shown in the sketch for penetration for X-41 from 1-77-2874 to 77-2875. Also, change the valve number 2874 in the listing of valves for this penetration to 2875.E1-2 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Revise FSAR Figure 6.2.4-16 to remove the reference to UFSAR Amendment

1. 2. On FSAR Table 6.2.4-1, revise the total page numbers on the first 64 pages from 64 to 69; change Page _ of 64 to Page _ of 69). 3. Revise FSAR Table 6.2.6-2 to remove spare penetrations X-23, X-28, X-85A, X-86A, X-868, X-86C, X-92A, X-928 and X-92C and the containment isolation valves listed for these penetrations.

4. Revise FSAR Table 6.2.4-1 to identify the following test connection valves as being Type A tested during the ILRT: 30-428/2 (X-608), 30-438/2 (X-26C), 30-3108/2 (X-26C), 30-448/2 (X-578), 30-3118/2 (X-578), 30-30C8/2 (X-98) and 30-458/2 (X-1 02). 5. Revise FSAR Table 6.2.4-1 to move the 'A' from the Essential/Non-Essential column to the Appendix J Table 6.2.4-1, Test column for penetrations X-38, X-39C and X-588. Figure 6.2.4-16, Also, for penetration X-588, identify the instrument

6. Table 6.2.6-1, line through the penetration as "En (Essential) in the 2-100-06 Table 6.2.6-2, Essential/Non-Essential column. 6. On FSAR Table 6.2.4-1, remove the valve and dP sensor information for penetration X-86D and identify the penetration as spare and Appendix J, Type A tested. Also, change the drawing number for penetration X-86D to 47W331-2 and the drawing number for X-102 to 2-47W600-89.

7. On FSAR Table 6.2.4-1, revise the drawing number for penetrations X-258, X-25C, X-85A and X-85C to 47W331-2.

8. On FSAR Table 6.2.4-1, remove the "En in the Shield 8uilding Penetration column for penetration X-26C. 9. On FSAR Table 6.2.4-1, revise the relief valve number shown in the sketch for penetration for X-41 from 1-77-2874 to 77-2875. Also, change the valve number 2874 in the listing of valves for this penetration to 2875. E1-2 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Change Number 10. On FSAR Table 6.2.4-1, remove the "Unit 1" from the sketches for penetrations X-76, X-90 and X-91. Also remove the "Unit 2" from the notes for penetrations X-92A and X-92B.11. On FSAR Table 6.2.4-1, revise the penetration descriptions for penetrations X-96A and X96B to remove the typographical error; change ILRTZ to ILRT.12. On UFSAR Table 6.2.4-1, change the ILRT valve position for valve 2 in the listing for penetration X-1 07 from closed to open.13. On FSAR Table 6.2.4-1, revise the listing for penetration X-107 to indicate valves 74-2, 74-8 and 63-185 are not Appendix J, Type A tested.1. On FSAR Table 6.2.4-1, Sheet 20 of 69, identify the normal and shutdown positions of check valve 26-1296 in penetration X-31 as 'C (Closed)." 7. Table 6.2.4-1 2-100-07 2. On FSAR Table 6.2.4-1, Sheet 43 of 69, identify the normal and shutdown positions of check valve 26-1260 in penetration X-78 as "C (Closed)." E1-3 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A 100 FSAR Changes" Item Change Area Change Description Change Package No. Number 10. On FSAR Table 6.2.4-1, remove the "Unit 1" from the sketches for penetrations X-76, X-90 and X-91. Also remove the "Unit 2" from the notes for penetrations X-92A and X-92B. 11. On FSAR Table 6.2.4-1, revise the penetration descriptions for penetrations X-96A and X96B to remove the typographical error; change ILRTZ to ILRT. 12. On UFSAR Table 6.2.4-1, change the ILRT valve position for valve 2 in the listing for penetration X-1 07 from closed to open. 13. On FSAR Table 6.2.4-1, revise the listing for penetration X-1 07 to indicate valves 74-2, 74-8 and 63-185 are not Appendix J, Type A tested. 1. On FSAR Table 6.2.4-1, Sheet 20 of 69, identify the normal and shutdown positions of check valve 26-1296 in penetration X-31 as 'C (Closed)." 7. Table 6.2.4-1 2-100-07 2. On FSAR Table 6.2.4-1, Sheet 43 of 69, identify the normal and shutdown positions of check valve 26-1260 in penetration X-78 as "C (Closed)." E1-3 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. 1 C A Number 1. In Chapter 1, page 1.6-5, delete Report "Hybrid B4C Absorber Control Rod Evaluation Report, "WCAP-8846, September 1976 ANN.2. In Section 4.2.3.2.1, page 4.2-34, change the first sentence in the third paragraph to read, "The absorber materials used in the control rods are silver-indium-cadmium alloy slugs which are essentially

'black' to thermal neutrons." 3. In Section 4.2.3.2.1, page 4.2-34, change the third sentence to read, "The extruded Ag-In-Cd slugs are sealed in stainless steel tubes to prevent them from coming in direct contact with the coolant." 4. In Section 4.2.3.2.1, page 4.2-34, change the fifth sentence to read, "In construction, the silver indium-Section 1.6 cadmium slugs are inserted into cold-worked

8. Section 4.2.3.2.1 stainless steel tubing which is then sealed at the 2-100-08 Section 1 1A bottom and the top by welded end plugs as shown inSection 12.2.1.3 Figure 4.2-16." 5. In Section 1 1A, Tritium Control, change the sentence to read, "This section discusses the reduced tritium production in the plant as a result of employing Zircaloy clad fuel and silver-indium-cadmium (Ag-In-Cd) control rods." 6. In Section 1 1A.2, Control Rod Source, change the first sentences to read, "The full length control rods for this plant are silver-indium-cadmium (Ag-In-Cd)." Delete the second sentence.7. In Section 12.2.1.3, Sources During Refueling, change the first sentence in the fourth paragraph toread, "The absorber material used in the control rods is silver-indium-cadmium (Ag-In-Cd)." Delete the last sentence.E11-4 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. In Chapter 1, page 1.6-5, delete Report "Hybrid B4C Absorber Control Rod Evaluation Report, "WCAP-8846, September 1976 ANN. 2. In Section 4.2.3.2.1, page 4.2-34, change the first sentence in the third paragraph to read, "The absorber materials used in the control rods are silver-indium-cadmium alloy slugs which are essentially

'black' to thermal neutrons." 3. In Section 4.2.3.2.1, page 4.2-34, change the third sentence to read, "The extruded Ag-In-Cd slugs are sealed in stainless steel tubes to prevent them from coming in direct contact with the coolant." 4. In Section 4.2.3.2.1, page 4.2-34, change the fifth sentence to read, "In construction, the silver indium-Section 1.6 cadmium slugs are inserted into cold-worked

8. Section 4.2.3.2.1 stainless steel tubing which is then sealed at the 2-100-08 Section 11A bottom and the top by welded end plugs as shown in Section 12.2.1.3 Figure 4.2-16." 5. In Section 11A, Tritium Control, change the sentence to read, "This section discusses the reduced tritium production in the plant as a result of employing Zircaloy clad fuel and silver-indium-cadmium (Ag-In-Cd) control rods." 6. In Section 11A.2, Control Rod Source, change the first sentences to read, "The full length control rods for this plant are silver-indium-cadmium (Ag-In-Cd)." Delete the second sentence.

7. In Section 12.2.1.3, Sources During Refueling, change the first sentence in the fourth paragraph to read, "The absorber material used in the control rods is silver-indium-cadmium (Ag-In-Cd)." Delete the last sentence.

E1-4 ENCLOSURE I WBN Unit 2 FSAR AI00"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. In Section 6.2.5.2, second paragraph -first sentence, change "... must remain intact following a LOCA to assure... "to "... must remain intact following a beyond-design-basis accident to assure...

" 2. In Section 6.2.5.2, third paragraph

-first sentence, change "... buildup of pressure-during a LOCA." to"... buildup of pressure during a beyond-design-basis accident." 3. In Section 6.2.5.2, third paragraph

-second sentence, change "Ductwork not protected by embedment is designed to withstand the LOCA environment." to "Ductwork not protected by embedment is also designed to withstand the beyond-design-basis accident environment." 4. In Section 6.8.1, second sentence, change "...following a design basis accident, which includes a LOCA." to "... following a beyond-design-basis accident." 9. Section 6.2.5.2 5. In Section 6.8.2, first paragraph -last sentence, 2-100-09 Section 6.8 change "... initial stages of a LOCA." to "... initial stages of beyond-design-basis accident." 6. In Section 6.8.2, fourth paragraph

-first sentence, change"...

to operate continuously during accident conditions." to "... to operate continuously during degraded core conditions." 7. In Section 6.8.2, fifth paragraph

-first sentence, change "... to the lower compartment, post LOCA hydrogen mixing... "to "... to the lower compartment, post severe accident hydrogen mixing ......8. In Section 6.8.3, first paragraph

-first sentence, change "... after blowdown from a LOCA or a non local pipe break, prevent... "to "... after blowdown from a severe accident pipe break, prevent.

.. " 9. In Section 6.8.3, first paragraph last sentence, change "... assumed to be produced as a result of the accident." to "... assumed to be produced as a result of the severe accident." E1-5 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. In Section 6.2.5.2, second paragraph

-first sentence, change " ... must remain intact following a LOCA to assure ... "to " ... must remain intact following a beyond-design-basis accident to assure ... " 2. In Section 6.2.5.2, third paragraph

-first sentence, change " ... buildup of pressure*during a LOCA" to " ... buildup of pressure during a beyond-design-basis accident." 3. In Section 6.2.5.2, third paragraph

-second sentence, change "Ductwork not protected by embedment is designed to withstand the LOCA environment." to "Ductwork not protected by embedment is also designed to withstand the beyond-design-basis accident environment." 4. In Section 6.8.1, second sentence, change " ... following a design basis accident, which includes a LOCA" to " ... following a

accident." 9. Section 6.2.5.2 5. In Section 6.8.2, first paragraph -last sentence, 2-100-09 Section 6.8 change " ... initial stages of a LOCA" to " ... initial stages of beyond-design-basis accident." 6. In Section 6.8.2, fourth paragraph

-first sentence, change" ... to operate continuously during accident conditions." to " ... to operate continuously during degraded core conditions." 7. In Section 6.8.2, fifth paragraph

-first sentence, change " ... to the lower compartment, post LOCA hydrogen mixing ... "to " ... to the lower compartment, post severe accident hydrogen mixing .... " 8. In Section 6.8.3, first paragraph

-first sentence, change " ... after blowdown from a LOCA or a non local pipe break, prevent... "to " ... after blowdown from a severe accident pipe break, prevent. .. " 9. In Section 6.8.3, first paragraph last sentence, change " ... assumed to be produced as a result of the accident." to " ... assumed to be produced as a result of the severe accident." E1-5 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 10. In Section 6.8.3, second paragraph

-last sentence, change "... reverse flow during the initial loss-of coolant blowdown." to "... reverse flow during the-initial severe accident blowdown."11. In Section 6.8.3, fourth paragraph

-first sentence, change "... to withstand the post-accident containment environment." to "... to withstand the beyond-design-basis accident containment environment." 12. In Section 6.8.5, first paragraph

-first sentence, change "... at the appropriate time after LOCA and that... "to "... at the appropriate time after a beyond-design-basis accident and that..." 1. Revise FSAR Table 6.2.4-1 to remove the blind flange listed as being in the containment building for penetration X-1 18.10. Table 6.2.4-1 2. Revise FSAR Table 6.2.4-1 to change the drawing 2-100-10 listed for penetration X-1 18 from 72-4333-318 to 72-4334-318.3. Revise FSAR Table 6.2.4-1 to remove drawing 47W862-1 from the listing for penetration X-1 18.E1-6 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 10. In Section 6.8.3, second paragraph

-last sentence, change" ... reverse flow during the initial loss-of coolant blowdown." to " ... reverse flow during the* initial severe accident blowdown." 11. In Section 6.8.3, fourth paragraph

-first sentence, change " ... to withstand the post-accident containment environment." to " ... to withstand the beyond-design-basis accident containment environment. " 12. In Section 6.8.5, first paragraph

-first sentence, change " ... at the appropriate time after LOtA and that. .. " to " ... at the appropriate time after a beyond-design-basis accident and that. .. " 1. Revise FSAR Table 6.2.4-1 to remove the blind flange listed as being in the containment building for penetration X-118. 10. Table 6.2.4-1 2. Revise FSAR Table 6.2.4-1 to change the drawing 2-100-10 listed for penetration X-118 from 72-4333-318 to 72-4334-318.

3. Revise FSAR Table 6.2.4-1 to remove drawing 47W862-1 from the listing for penetration X-118. E1-6 ENCLOSURE1 WBN Unit 2 FSAR AIOO"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. II Number 1. Revise FSAR Table 6.2.4-1 to remove test connection valves from the listings for containment penetrations X-26C, X-57B, X-60B, X-97, X-98 and X-102.2. Revise FSAR Table 6.2.4-1 to remove the test connection valve numbering from the sketches for containment penetrations X-26C, X-57B, X-60B, X-97, X-98 and X-102.3. Revise FSAR Table 6.2.4-1 to remove 30-43A and 30-31 OA from the listing for containment penetration X-26C,30-44A and 30-311 A from the listing for containment penetration X-57B,30-42A from the listing for containment penetration X-60B, 30-133A from the listing for containment penetration X-97, and 30-45A from the listing for containment penetration X-102.4. Revise FSAR Table 6.2.4-1 to remove 30-43A and 30-31 OA from the sketch for containment penetration Table 6.2.4-1 X-26C,30-44A and 30-311 A from the sketch for 2-100-11 Table 6.2.6-3 containment penetration X-57B, 3042A from the sketch for containment penetration X-60B, 30-133A from the sketch for containment penetration X-97, and 30-45A from the sketch for containment penetration X-102.5. Revise FSAR Table 6.2.4-1 to add normally open manual isolation valve 30-30C/A to the sketch for X-98. (Do not add the valve number to the sketch).

6. Revise FSAR Table 6.2.6-3 to remove containment penetrations X-26C,- X-57B, X-60B, X-97, X-98 and X-102 and the associated valves. Also delete Note 11 from the table.7. Revise FSAR Table 6.2.6-3 to change the total page numbers on the first 4 pages from "4" to "6"; change"Page _ of 4" to "Page _ of 6)". Also add page numbers to the notes for the table.8. Revise Note 4 on FSAR Table 6.2.6-3 to change the word "an" to "and." E1-7 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Revise FSAR Table 6.2.4-1 to remove test connection valves from the listings for containment penetrations X-26C, X-57B, X-60B, X-97, X-98 and X-102. 2. Revise FSAR Table 6.2.4-1 to remove the test connection valve numbering from the sketches for containment penetrations X-26C, X-57B, X-60B, X-97, X-98 and X-102. 3. Revise FSAR Table 6.2.4-1 to remove 30-43A and 30-310A from the listing for containment penetration X-26C,30-44A and 30-311A from the listing for containment penetration X-57B,30-42A from the listing for containment penetration X-60B, 30-133A from the listing for containment penetration X-97, and 30-45A from the listing for containment penetration X-102. 4. Revise FSAR Table 6.2.4-1 to remove 30-43A and 30-310A from the sketch for containment penetration

11. Table 6.2.4-1 X-26C,30-44A and 30-311A from the sketch for 2-100-11 Table 6.2.6-3 containment penetration X-57B, 3042A from the sketch for containment penetration X-60B, 30-133A from the sketch for containment penetration X-97, and 30-45A from the sketch for containment penetration X-1 02. 5. Revise FSAR Table 6.2.4-1 to add normally open manual isolation valve 30-30C/A to the sketch for X-98. (Do not add the valve number to the sketch). 6. Revise FSAR Table 6.2.6-3 to remove containment penetrations X-26C; X-57B, X-60B, X-97, X-98 and X-102 and the associated valves. Also delete Note 11 from the table. 7. Revise FSAR Table 6.2.6-3 to change the total page numbers on the first 4 pages from "4" to "6"; change "Page _ of 4" to "Page _ of 6)". Also add page numbers to the notes for the table. 8. Revise Note 4 on FSAR Table 6.2.6-3 to change the word "an" to "and." E1-7 ENCLOSURE 1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Revise FSAR Table 6.2.4-1 to remove the blind flange listed-as being in the Auxiliary Building for penetration X-54.12. Table 6.2.4-1 2. Revise FSAR Table 6.2.4-1 to align the data for the 2-100-12 blind flange in the Shield Building for penetration X-54.3. Delete the first sentence of FSAR Table 6.2.4-1 Note 16.13. Table 3.2-1 For Primary Water Make-up System, Tank Unit 1, change 2-100-13 G(22) to G(25) in the TVA/ANS Safety Class Column1. On FSAR Table 6.2.4-1, Sheet 28 of 69, change the Appendix J Test column for valves61-192, 61-191 and 61-533 in penetration X-47A to indicate the valves are not Appendix J Type A tested.2. On FSAR Table 6.2.4-1, Sheet 29 of 69, change the Appendix J Test column for valves61-194, 61-193 and 61-680 in penetration X-478 to indicate the valves are not Appendix J Type A tested.3. On FSAR Table 6.2.4-1, Sheet 29 of 69, add Note 8 to the listing for penetration X-478.4. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the 14. Table 6.2.4-1 position shown for valve 61-110 during the ILRT in 2-100-14 penetration X-114 from "closed (C)" to "open (0)".5. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the Appendix J Test column for valves61-122, 61-110 and 61-745 in penetration X-1 14 to indicate the valves are not Appendix J Type A tested.6. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the position shown for valve 61-96 during the ILRT in penetration X-1 15 from "closed (C)" to "open (0)".7. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the Appendix J Test column for valves 61-97, 61-96 and 61-692 in penetration X-1 15 to indicate the valves are not Appendix J Type A tested.E11-8 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Revise FSAR Table 6.2.4-1 to remove the blind flange listed-as being in the Auxiliary Building for penetration X-54. 12. Table 6.2.4-1 2. Revise FSAR Table 6.2.4-1 to align the data for the 2-100-12 blind flange in the Shield Building for penetration X-54. 3. Delete the first sentence of FSAR Table 6.2.4-1 Note 16. 13. Table 3.2-1 For Primary Water Make-up System, Tank Unit 1, change 2-100-13 G(22) to G(25) in the TVAIANS Safety Class Column 1. On FSAR Table 6.2.4-1, Sheet 28 of 69, change the Appendix J Test column for valves61-192,61-191 and 61-533 in penetration X-47A to indicate the valves are not Appendix J Type A tested. 2. On FSAR Table 6.2.4-1, Sheet 29 of 69, change the Appendix J Test column for valves61-194,61-193 and 61-680 in penetration X-478 to indicate the valves are not Appendix J Type A tested. -3. On FSAR Table 6.2.4-1, Sheet 29 of 69, add Note 8 to the listing for penetration X-478. 4. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the 14. Table 6.2.4-1 position shown for valve 61-110 during the ILRT in 2-100-14 penetration X-114 from "closed (C)" to "open (0)". 5. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the Appendix J Test column for valves61-122,61-11 0 and 61-745 in penetration X-114 to indicate the valves are not Appendix J Type A tested. 6. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the position shown for valve 61-96 during the ILRT in penetration X-115 from "closed (C)" to "open (0)". 7. On FSAR Table 6.2.4-1, Sheet 62 of 69, change the Appendix J Test column for valves 61-97,61-96 and 61-692 in penetration X-115 to indicate the valves are not Appendix J Type A tested. E1-8 ENCLOSURE 1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Correct Spelling of "Instrumentation" and"Intermediate" 2. Insert missing space between Multiple and Contract

3. Replaced generic title of Thermo Fisher Scientific report with actual report title.4. Replaced placeholder information for Westinghouse seismic qualification of the NIS cabinet with Gamma Metrics equipment installed with the actual report number and title.5. Replaced placeholder information for the Ametek 15. Section 3.10 seismic qualification report for the containment sump 2-100-15 level transmitters with the actual report number and title.6. Replaced placeholder information for Weed seismic qualification report for the diverse pressure transmitter with the actual report number and title.7. Deleted "(Unit 2 Only)" 8. Deleted "Post Accident Monitoring Recorders" and Westinghouse and Westronics recorder qualification references

9. Add text to include Reference 26 for qualification of the Nuclear Instrumentation System cabinet.E1-9 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Correct Spelling of "Instrumentation" and "Intermediate" 2. Insert missing space between Multiple and Contract 3. Replaced generic title of Thermo Fisher Scientific report with actual report title. 4. Replaced placeholder information for Westinghouse seismic qualification of the NIS cabinet with Gamma Metrics equipment installed with the actual report number and title. 5. Replaced placeholder information for the Ametek 15. Section 3.10 seismic qualification report for the containment sump 2-100-15 level transmitters with the actual report number and title. 6. Replaced placeholder information for Weed seismic qualification report for the diverse pressure transmitter with the actual report number and title. 7. Deleted "(Unit 2 Only)" 8. Deleted "Post Accident Monitoring Recorders" and Westinghouse and Westronics recorder qualification references

9. Add text to include Reference 26 for qualification of the Nuclear Instrumentation System cabinet. E1-9 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change PackageNo. IINumber 16.Section 2.4 Section 3.5.1.6 Section 3.9 Section 4.4 Table 7.1-1 Section 7.6 Table 11.2-7 Table 14.2-1 Section 15.41. On pages 2.4-16 and -17 change "the March 21,400 -square-mile storm with" to "the 21,400-square-mile storm in March with" 2. Correct alignment issues in Tables 2.4-5 and 2.4-14.3. In Section 3.5.1.6, Change footnote from 17 to 16 to reflect deletion of reference 13 which resulted due to Unit 2 to Unit 1 difference in main turbine.4. On page 3.9-37, Replace "1.1.S" with "1.IS" 5. On page 3.9-69, in note 3 replace "othe" with "other" 6. On page 4.4-1, under the heading of Discussion, change "DBN" to "DNB".7. On page 4.4-15, replace "4.4.15" with "4.4-15" 8. Table 7.1-1 -Correct type from "pe" to "per" on Sheet 9 of 9 9. Section 7.6.7 -Revise reference at the end of the first paragraph from "7.1-7" to "7.1-1".10 On page 11.2-39, Revise value for Adult, "Lung" from 0.352 to 0.136 in Table 11.2-7.11. Section 14.2, Sheet 73 of 89 -Correct "EF" to "OF" in the objective section.12. Section 14.2, Sheet 84 of 89- In item 3 under acceptance criteria, correct # in two places to less than or equal symbol 13. On page 15.4-46, Correct "Deplartment" typo in Item 43, 2-100-16 Change FSAR Section 5.2.2.4.2.1 to "At-Power 17. Section 5.2 Overpressure Transients." Renumber "Evaluation of Low 2-100-17 Temperature Overpressure Transients" and "Operating Basis Earthquake Evaluation" to 5.2.2.4.2.2 and 5.2.2.4.3.

El-10 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. On pages 2.4-16 and -17 change "the March 21,400 -square-mile storm with" to "the 21 ,400-square-mile storm in March with" 2. Correct alignment issues in Tables 2.4-5 and 2.4-14. 3. In Section 3.5.1.6, Change footnote from 17 to 16 to reflect deletion of reference 13 which resulted due to Unit 2 to Unit 1 difference in main turbine. 4. On page 3.9-37, Replace "1.1.S" with "1.1 S" 5. On page 3.9-69, in note 3 replace "othe" with "other" Section 2.4 6. On page 4.4-1, under the heading of Discussion, Section 3.5.1.6 change "DBN" to "DNB". Section 3.9 7. On page 4.4-15, replace "4.4.15" with "4.4-15" Section 4.4 16. Table 7.1-1 8. Table 7.1-1 -Correct type from "pe" to "per" on Sheet 2-100-16 Section 7.6 Table 11.2-7 9 of 9 Table 14.2-1 9. Section 7.6.7 -Revise reference at the end of the first Section 15.4 paragraph from "7.1-7" to "7.1-1". 10 On page 11.2-39, Revise value for Adult, "Lung" from 0.352 to 0.136 in Table 11.2-7. 11. Section 14.2, Sheet 73 of 89 -Correct "EF" to "oF" in the objective section. 12. Section 14.2, Sheet 84 of 89 -In item 3 under acceptance criteria, correct # in two places to less than or equal symbol 13. On page 15.4-46, Correct "Deplartment" typo in Item 43, Change FSAR Section 5.2.2.4.2.1 to "At-Power

17. Section 5.2 Overpressure Transients." Renumber "Evaluation of Low 2-100-17 Temperature Overpressure Transients" and "Operating Basis Earthquake Evaluation" to 5.2.2.4.2.2 and 5.2.2.4.3.

E1-10 ENCLOSUREI WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number This FSAR Change Request is being processed to add item 2, "Power supply to safety related loads will automatically and manually transfer to the onsite (standby)diesel units from the normal or alternate supply or manually from the diesel generator units back to the normal or alternate supply as described by FSAR Section 18. Table 14.2 8.3.1" back to FSAR table 14.2-1, Sheet 49. 2-100-18 This test will be performed by 2-PTI-262-01 (Unit 2 Integrated Safeguards Test, Train 2A) and 2-PTI-262-02(Unit 2 Integrated Safeguards Test, Train 28).The marked up FSAR Table 14.2-1, Sheet 49 of 90, incorporates this change.Sections 3.9.6 and 6.3.4.2

-Updated Code of Record reference.

Since the issue date of the Unit 2 OL is unknown at present, the CFR requirement until the date ofSection 3.9.6 the OL is known.19. Section 6.3.4.2 2-100-19 Section 9.3.6.4 Section 9.3.6.4

-Changed the Code of Record reference to match the words in the Ul UFSAR. The reference will be changed to reference the Augmented Inservice Test Program for pumps and valves.

Table 14.2, Sheet 44 of 89, Add as Item 3 the following: "Demonstrate the WBN U2 Diesel generators automatic 20. Table 14.2 trip are bypassed on automatic or emergency start signal 2-100-20 except for engine over speed and generator differential current." Change FSAR Unit 2 Table 3.9-5 to match FSAR Unit 1 21. Table 3.9-5 Table 3.9-5. In replacing this table, the value of the no 2-100-21 loss-of-function limit for the upper package axial deflection should be changes to "1.5 inches." 1. Add the words "Capability is also provided to supply the Class IE circuits through the 161 kV system via CSST A or B in the event CSST D or C, respectively, is unavailable." on Page 8.1-1 as the fourth 22. Section 8.1 paragraph.

2-100-22 Section 8.2 2. In Section 8.2.1.8, Page 8.2-17 Delete the word "the supplying", insert the words "C or D", and insert the words "and transformers A or B within its FA rating" in the second paragraph on Page 8.2-17.1. In Table 11.4-2, Page 2 of 3 under Nuclide for TVA Instrument No. 2-RE-90-255 replace "CI-36"with "Xe-133" & "Kr-85".23. Table 11.4-2 2-100-23 2. In Table 11.4-2, Page 2 of 3 under Nuclide for TVA Instrument No. 2-RE-90-256 replace "Cs-137" with"Xe-133" & "Kr-85".El-11 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number This FSAR Change Request is being processed to add item 2, "Power supply to safety related loads will automatically and manually transfer to the onsite (standby) diesel units from the normal or alternate supply or manually from the diesel generator units back to the normal or alternate supply as described by FSAR Section 18. Table 14.2 8.3.1" back to FSAR table 14.2-1, Sheet 49. 2-100-18 This test will be performed by 2-PTI-262-01 (Unit 2 Integrated Safeguards Test, Train 2A) and 2-PTI-262-02 (Unit 2 Integrated Safeguards Test, Train 28). The marked up FSAR Table 14.2-1, Sheet 49 of 90, incorporates this change. Sections 3.9.6 and 6.3.4.2 -Updated Code of Record reference.

Since the issue date of the Unit 2 OL is unknown at present, the CFR requirement until the date of Section 3.9.6 the OL is known. 19. Section 6.3.4.2 2-100-19 Section 9.3.6.4 Section 9.3.6.4 -Changed the Code of Record reference to match the words in the U1 UFSAR. The reference will be changed to reference the Augmented Inservice Test Program for pumps and valves. Table 14.2, Sheet 44 of 89, Add as Item 3 the following: "Demonstrate the WBN U2 Diesel generators automatic

20. Table 14.2 trip are bypassed on automatic or emergency start signal 2-100-20 except for engine over speed and generator differential current." Change FSAR Unit 2 Table 3.9-5 to match FSAR Unit 1 21. Table 3.9-5 Table 3.9-5. In replacing this table, the value of the no 2-100-21 loss-of-function limit for the upper package axial deflection should be changes to "1.5 inches." 1. Add the words "Capability is also provided to supply the Class IE circuits through the 161 kV system via CSST A or B in the event CSST D or C, respectively, is unavailable." on Page 8.1-1 as the fourth 22. Section 8.1 paragraph.

2-100-22 Section 8.2 2. In Section 8.2.1.8, Page 8.2-17 Delete the word "the supplying", insert the words "C or D", and insert the words "and transformers A or B within its FA rating" in the second paragraph on Page 8.2-17. --1. In Table 11.4-2, Page 2 of 3 under Nuclide for TVA Instrument No. 2-RE-90-255 replace "CI-36"with "Xe-133" & "Kr-85". 23. Table 11.4-2 2-100-23 2. In Table 11.4-2, Page 2 of 3 under Nuclide for TVA Instrument No. 2-RE-90-256 replace "Cs-137" with "Xe-133" & "Kr-85". E1-11 ENCLOSURE1 WBN Unit 2 FSAR AIOO"Summary Listing of AIOO FSAR Changes" Item Change Area Change Description Change Package No. Number 1. The safety function of valve 0-FCV-70-206 has been removed. This valve is now labeled as a Unit 1/2 interface point and is shown as "Locked Closed." Valve 0-FCV-70-206 is locked to ensure the isolation of the previously abandoned CDWE as shown on 1-47W859.2. With the change above, valve 0-CKV-70-753 nolonger provides a safety function due to valve 0-FCV-70-206 being locked closed and having a full face gasket and silicone casting installed. This results in the deletion of item D-4. Justification is provided in Calculation EPMSGP-022892 Table 7.1.24. 9.2 2-100-24 3. Editorial Changes: The Component Cooling System (CCS) designator (70) was added to the UNIDs listed in the Effects on Plant column of items C-4, C-5, C-6, 2C-6A, and 2C-7 in Table 9.2-9.4. Delete Note 3 and replace to read "Not Used" to correctly reflect Appendix A of calculation EPMSGP02892.

5. Title of Table 9.2-9 is mislabeled as "Essential-Raw Cooling Water System" the entire Table 9.29 should be titled "Component Cooling System Failure Modes and Effects Analysis" E1-12 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. The safety function of .valve 0-FCV-70-206 has been removed. This valve is now labeled as a Unit 1/2 interface point and is shown as "Locked Closed." Valve 0-FCV-70-206 is locked to ensure the isolation of the previously abandoned CDWE as shown on 1-47W859.

2. With the change above, valve 0-CKV-70-753

'1Q longer provides a safety function due to valve O-FCV-70-206 being locked closed and having a full face gasket and silicone casting installed.

This results in the deletion of item D-4. Justification is provided in Calculation EPMSGP-022892 Table 7.1. 24. 9.2 2-100-24 . 3. Editorial Changes: The Component Cooling System (CCS) designator (70) was added to the UNIDs listed in the Effects on Plant column of items C-4, C-5, C-6, 2C-6A, and 2C-7 in Table 9.2-9. 4. Delete Note 3 and replace to read "Not Used" to correctly reflect Appendix A of calculation EPMSGP02892.

5. Title of Table 9.2-9 is mislabeled as "Essential*

Raw Cooling Water System" the entire Table 9.29 should be titled "Component Cooling System Failure Modes and Effects Analysis" E1-12 ENCLOSURE1 WBN Unit 2 FSAR AIOO"Summary Listing of AIOO FSAR Changes" Item Change Area Change Description Change Package No. II Number 25.Table 1.3-3 Section 1.9.2.7 Table 4.3-1 Section 6.2.1 Section 6.2.5 Section 7.1.1.2 Section 7.1.2.1.8 Table 7.1-1 Section 7.3.2.2.5 Section 7.4.1.3 Table 9.3-3 Section 11.2.4 1. Correct spelling, page numbering and punctuation noted during the FSAR review

2. Replace the terms "service water" "emergency raw cooling water" and "essential service water" with"essential raw cooling water" 3. Correct, add and update cross reference information

4. Deleted the additional source range monitor and replaced it with the seismically qualified source and intermediate range monitor system.5. Deleted the entry for the gross failed fuel detector system 6. Added a note to the elbow-tab flow measurement discussion.

7. Added the ERFDS computer to the line item concerning the P2500 replacement by ICS.8. Added additional cross reference information and expanded the discussion of the Foxboro IA changes to more accurately reflect the changes being made.9. Added additional cross reference information, added Post Accident Monitoring to the description and Core Exit Thermocouples to the Common Q PAMS line item.10. Added a description of the changes associated withthe containment atmosphere combustible gas control permitted by 10CFR50.44 rulemaking.

11, Added the replacement of the safety related Bailey and Robert Shaw ESFAS instrumentation with Foxboro Spec 200 hardware.12. Added replacement of the majority of the Westinghouse supplied Foxboro and Barton (Cameron) transmitters with Rosemount Transmitters.

13. Added replacement of the rod position indication system with the CERPI system 14. Added replacement of the Loose Part Monitoring System with a Westinahouse DIMMS-DX System 2-100-25 El-13 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Correct spelling, page numbering and punctuation noted during the FSAR review 2. Replace the terms "service water" "emergency raw cooling water" and "essential service water" with "essential raw cooling water" 3. Correct, add and update cross reference information

4. Deleted the additional source range monitor and replaced it with the seismically qualified source and intermediate range monitor system. 5. Deleted the entry for the gross failed fuel detector system 6. Added a note to the elbow-tab flow measurement discussion.

Table 1.3-3 7. Added the ERFDS computer to the line item Section 1.9.2.7 Table 4.3-1 concerning the P2500 replacement by ICS. Section 6.2.1 8. Added additional cross reference information and Section 6.2.5 expanded the discussion of the Foxboro IA changes Section 7.1.1.2 25. Section 7.1.2.1.8 to more accurately reflect the changes being made. 2-100-25 Table 7.1-1 9. Added additional cross reference information, added Section 7.3.2.2.5 Section 7.4.1.3 Post Accident Monitoring to the description and Core Table 9.3-3 Exit Thermocouples to the Common Q PAMS line Section 11.2.4 item. 10. Added a description of the changes associated with the containment atmosphere combustible gas control permitted by 10CFR50.44 rulemaking.

11, Added the replacement of the safety related Bailey and Robert Shaw ESFAS instrumentation with Foxboro Spec 200 hardware.

12. Added replacement of the majority of the Westinghouse supplied Foxboro and Barton (Cameron) transmitters with Rosemount Transmitters.

13. Added replacement of the rod position indication system with the CERPI system 14. Added replacement of the Loose Part Monitoring System with a Westinghouse DIMMS-DX System E1-13 ENCLOSUREI WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" item Change Area Change Description Change PackageNo. IINumber

15. Added replacement of the Reactor Coolant Pumpand Turbine Generator vibration monitoring system with a Bentley Nevada 3500 System 16. Added replacement of the containment high range radiation monitors with RM-1000 monitors 17. Added relocation of the core exit thermocouples and reduction in number from 65 to 58 as part of the WINCISE installation

18. Added replacement of the annunciator system with a Ronan server based system.19 Added upgrade of the generator voltage regulator 20. Added elimination of turbine trips 21. Added missing I.D. and O.D. designators

22. Added "The non-safety related plant computer system provides the Safety Parameter Display System and the Bypassed and Inoperable Status Indication System." 23. Added "Table 7.5-2 provides a complete listing of Reg. Guide 1.97 variables that includes both safetyrelated and non safety-related indications/equipment." 24. Reworded the second paragraph of the note to clarify that the Loose Part Detection System has been relocated to the Technical Requirements Manual.Flow Indicating Switches 2-FIS-74-12 and -24 were 26. Table 5.5-15a replaced with a single flow indicator (2-FI-74-12, -24) and 2-100-26 Table 5.5-15b two flow switches for each component.

(2-ES-74-12A, -12B, -24A, -24B).Flow Indicating Switches 2-FIS-74-12 and -24 were replaced with a single flow indicator (2-FI-74-12, -24) and 27. Table 6.3-8 two flow switches for each component (2-FS-74-12A,-12B, 2-100-27 Table 6.3-9 -24A,-248).

With this replacement of the flow indicating switches, FSAR incorrectly shown. See attached markups to FSAR for changes.28. Figure 5.5-11 Change the wording of a note to remove the reference to 2-100-28 design packages EDCR 54297-A In paragraph 9.1.3.3.3 change the 12 day decay time value, the maximum heat load for a full core discharge to 29. Section 9.1.3.3.3 read 39.06E+06 Btu/hr. In the same paragraph change 2-100-29 the value for the full core discharge following a normal refueling outage case to read 25.62E+06 Btu/hr. refer to mark-up for details.E1-14 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 15. Added replacement of the Reactor Coolant Pump and Turbine Generator vibration monitoring system with a Bentley Nevada 3500 System 16 . Added replacement of the containment high range . radiation monitors with RM-1000 monitors 17. Added relocation of the core exit thermocouples and reduction in number from 65 to 58 as part of the WINCISE installation

18. Added replacement of the annunciator system with a Ronan server based system. 19 Added upgrade of the generator voltage regulator

20. Added elimination of turbine trips 21. Added missing 1.0. and 0.0. designators

22. Added 'The non-safety related plant computer system provides the Safety Parameter Display System and the Bypassed and Inoperable Status Indication System." 23. Added "Table 7.5-2 provides a complete listing of Reg. Guide 1.97 variables that includes both safety related and non safety-related indications/equipment." 24. Reworded the second paragraph of the note to clarify that the Loose Part Detection System has been relocated to the Technical Requirements Manual. Flow Indicating Switches 2-FIS-74-12 and -24 were 26. Table 5.5-15a replaced with a single flow indicator (2-FI-74-12, -24) and 2-100-26 Table 5.5-15b two flow switches for each component.

(2-ES-74-12A, -12B, -24A, -24B). Flow Indicating Switches 2-FIS-74-12 and -24 were replaced with a single flow indicator (2-FI-74-12, -24) and 27. Table 6.3-8 two flow switches for each component (2-FS-74-12A,-12B, 2-100-27 Table 6.3-9 -24A,-248).

With this replacement of the flow indicating switches, FSAR incorrectly shown. See attached markups to FSAR for changes. 28. Figure 5.5-11 Change the wording of a note to remove the reference to 2-100-28 design packages EDCR 54297-A In paragraph 9.1.3.3.3 change the 12 day decay time value, the maximum heat load for a full core discharge to 29. Section 9.1.3.3.3 read 39.06E+06 Btu/hr. In the same paragraph change 2-100-29 the value for the full core discharge following a normal refueling outage case to read 25.62E+06 Btu/hr. refer to mark-up for details. E1-14 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 30. Table 8.3-13 Add Table 8.3-13 2-100-30 Section 4.2.3.4.1

-Change 2nd paragraph under Item 4 just prior to Section 4.2.3.4.2 to read,"The rod cluster control assemblies will be functionally tested, following initial core loading but prior to criticality to demonstrate reliable operation of the assemblies.

Each assembly will be operated four times, once at cold no flow, once at cold full flow, once at hot not flow and hot full flow conditions.

Those assemblies whose trip times fall outside a certain tolerance will be tested an additional 3 times at each failed test condition.

Thus each assembly will be adequately tested to verify that the assemblies are Section 4.2.3.4.1 properly functioning." 3. Section 4.2.3.4.2 2103 Section 4.2.3.4.2

-Revised the first paragraph on page 4.2-53 to read as follows: "These tests include verification that the trip time achieved by the control rod drive mechanisms meets the design requirement from the time the Reactor Trip Breakers change status until dashpot entry occurs. This trip time requirement was confirmed for each control rod drive mechanism prior to initial reactor operation, as required by Technical Specifications." El-15 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A 100 FSAR Changes" Item Change Area Change Description Change Package No. Number 30. Table 8.3-13 Add Table 8.3-13 2-100-30 Section 4.2.3.4.1

-Change 2nd paragraph under Item 4 just prior to Section 4.2.3.4.2 to read, "The rod cluster control assemblies will be functionally tested, following initial core loading but prior to criticality to demonstrate reliable operation of the assemblies.

Each assembly will be operated four times, once at cold no flow, once at cold full flow, once at hot not flow and hot full flow conditions.

Those assemblies whose trip times fall outside a certain tolerance will be tested an additional 3 times at each failed test condition.

Thus each assembly will be adequately tested to verify that the assemblies are Section 4.2.3.4.1 properly functioning." 31. Section 4.2.3.4.2 2-100-31 Section 4.2.3.4.2

-Revised the first paragraph on page 4.2-53 to read as follows: These tests include verification that the trip time achieved by the control rod drive mechanisms meets the design requirement from the time the Reactor Trip Breakers change status until dashpot entry occurs. This trip time requirement was confirmed for each control rod drive mechanism prior to initial reactor operation, as required by Technical Specifications." E1-15 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Change Unit 2 FSAR Section 5.2 reference (page 5.2-67) from: "(4) Conoper, L., Miselis, V., and Starek, R.M., Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, Revision 1, June 1972." to: (4) Smith, M., et al., Overpressure Protection Report for Watts Bar Nuclear Power Plant Unit 2, March Section 5.2 2010." Section 15.2 2. Change Unit 2 FSAR Section 15.2 reference (page 15.2-43) from: "(9) Cooper, K., et al., "Topical Report, Overpressure Protection for Westinghouse Pressurized Water Reactors," WCAP-7769, Revision 1, June 1972.to: (9) Smith, M., et al., Overpressure Protection Report for Watts Bar Nuclear Power Plant Unit 2, March 2010." Revise Unit 2 FSAR Section 4.3.2.2.5 (Limiting Power Distribution), nineteenth paragraph, after the first sentence, insert the following: "The average linear power density, or heating rate (ALHR), is determined by: ALHR = [(Total thermal power (kw)) / (Total fuel length of all rods (ft))] X HGIF HGIF is the fraction of the thermal heat generated in the 33. Section 4.3.2.2.5 fuel (0.974). Densification is accounted for by use of the 2-100-33 densified active fuel length of 143.7 inches or 11.975 ft.Using WBNP Unit 2 values: ALHR =[(341 1000 kw) / (193 assemblies X 2-64 fuel rods X 11.975 ft)] X 0.974 ALHR = 5.45 kw/ft." Revise Unit-2 FSAR Section 4.2.3.1.4, third paragraph, third sentence to read: 34. Section 4.2.3.1.4 2-100-34"The part-length CRDMs are physically and electrically disabled." E1-16 ENCLOSURE 1 WBN Unit 2 FSAR A 100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. Change Unit 2 FSAR Section 5.2 reference (page 5.2-67) from: "(4) Conoper, L., Miselis, V., and Starek, R.M., Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, Revision 1, June 1972." to: (4) Smith, M., et aI., Overpressure Protection Report for Watts Bar Nuclear Power Plant Unit 2, March 32. Section 5.2 2010." 2-100-32 Section 15.2 2. Change Unit 2 FSAR Section 15.2 reference (page 15.2-43) from: "(9) Cooper, K., et aI., "Topical Report, Overpressure Protection for Westinghouse Pressurized Water Reactors," WCAP-7769, Revision 1, June 1972. to: (9) Smith, M., et aI., Overpressure Protection Report for Watts Bar Nuclear Power Plant Unit 2, March 2010." Revise Unit 2 FSAR Section 4.3.2.2.5 (Limiting Power Distribution), nineteenth paragraph, after the first sentence, insert the following: "The average linear power density, or heating rate (ALHR), is determined by: ALHR = [(Total thermal power (kw)) / (Total fuel length of all rods (ft))1 X HGIF HGIF is the fraction of the thermal heat generated in the 33. Section 4.3.2.2.5 fuel (0.974). Densification is accounted for by use of the 2-100-33 densified active fuel length of 143.7 inches or 11.975 ft. Using WBNP Unit 2 values: ALHR =[(3411000 kw) / (193 assemblies X 2-64 fuel rods X 11.975 ft)1 X 0.974 ALHR = 5.45 kwlft." Revise Unit-2 FSAR Section 4.2.3.1.4, third paragraph, third sentence to read: 34. Section 4.2.3.1.4 2-100-34 "The part-length CRDMs are physically and electrically disabled." E1-16 ENCLOSURE1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number Revise Unit-2 FSAR Section 4.3.2.3.2, fifth paragraph, first sentence to read: "The moderator coefficient is calculated for the various plant conditions discussed above by performing two group two or three dimensional

35. Section 4.3.2.3.2 calculations, varying the moderator temperature by plus or 2-100-35 minus 5 0 F (+/- 5 0 F) about each of the mean temperatures, and the density changes consistent with the temperature." B4C (Boron Carbide) removed as this RCCA (Rod Cluster Control Assembly) design will not be used in WBN Unit 2.Since Unit 2 does not use borosilicate glass burnable absorber material, any reference associated with the 36. Section 4.2.3 borosilicate glass burnable absorber material in FSAR 2-100-36 section 4.2.3, "Reactivity Control System," is removed.This includes removing a figure which depicts the burnable absorber assembly that consists of borosilicate, and also changing figures to delete borosilicate glass tube, (Pyrex absorber), and B4C pellets.Section 1.2 Add a statement in FSAR section 4.2.3.3.1, "Reactivity Control Components," on page 4.2-44 to clarify on the Section 4.12 extension of ZIRLO corrosion resistance to ZIRLOSection 4.2 37. Section 4.3 guide thimbles.

2-100-37 Section 4.4 Revise "Zircaloy" and "Zircaloy-4" to ZIRLO in affected Section 15.4 sections.The density of fuel pellets is changed from 94.5% to 95%in Table 4.1-1, "Reactor Design Comparison Table," and Table 4.3-1, "Reactor Core Description (First Cycle) (Page 2 of 2)." The Rod Cluster Control Assemblies (RCCA) section of Table 4.3-1, "Reactor Core Description (First Cycle) (Page Table 4.1-1 2 of 2)," has information which is no longer used in the 38. Table 4.3-1 Watts Bar Unit 2 such as the Boron Carbide (B4C) control 2-100-38 Section 4.3.2.7 rods. The RCCA design using B4C was for WBN Unit 1 Section 4.3.3.2 only and will not be used in WBN Unit 2. In addition, parameters in the Burnable-Poison Rods section of Table 4.3-1 are also changed to reflect the WABA (Wet Annular Burnable Absorber) rods used in Unit 2.The administrative change removes the word "discrete" from Section 4.2.3.2.1, page 4.2-35, Section 4.3.2.7, page 4.3-27, and Section 4.3.3.2, page 4.3-34.E1-17 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number Revise Unit-2 FSAR Section 4.3.2.3.2, fifth paragraph, first sentence to read: "The moderator coefficient is calculated for the various plant conditions discussed above by performing two group two or three dimensional

35. Section 4.3.2.3.2 calculations, varying the moderator temperature by plus or 2-100-35 minus 5°F (+/-5°F) about each of the mean temperatures, and the density changes consistent with the temperature." B4C (Boron Carbide) removed as this RCCA (Rod Cluster Control Assembly) design will not be used in WBN Unit 2. Since Unit 2 does not use borosilicate glass burnable absorber material, any reference associated with the 36. Section 4.2.3 borosilicate glass burnable absorber material in FSAR 2-100-36 section 4.2.3, "Reactivity Control System," is removed. This includes removing a figure which depicts the burnable absorber assembly that consists of borosilicate, and also changing figures to delete borosilicate glass tube, (Pyrex absorber), and B4C pellets. Section 1.2 Add a statement in FSAR section 4.2.3.3.1, "Reactivity Section 4.1.2 Control Components," on page 4.2-44 to clarify on the Section 4.2 extension of ZIRLO corrosion resistance to ZIRLO 37. Section 4.3 guide thimbles.

2-100-37 Section 4.4 Revise "Zircaloy" and "Zircaloy-4" to ZIRLO in affected Section 15.4 sections.

The density of fuel pellets is changed from 94.5% to 95% in Table 4.1-1, "Reactor Design Comparison Table," and Table 4.3-1, "Reactor Core Description (First Cycle) (Page 2 of 2)." The Rod Cluster Control Assemblies (RCCA) section of Table 4.3-1, "Reactor Core Description (First Cycle) (Page Table 4.1-1 2 of 2)," has information which is no longer used in the 38. Table 4.3-1 Watts Bar Unit 2 such as the Boron Carbide (B4C) control 2-100-38 Section 4.3.2.7 rods. The RCCA design using B4C was for WBN Unit 1 Section 4.3.3.2 only and will not be used in WBN Unit 2. In addition, parameters in the Burnable-Poison Rods section of Table 4.3-1 are also changed to reflect the WABA (Wet Annular Burnable Absorber) rods used in Unit 2. The administrative change removes the word "discrete" from Section 4.2.3.2.1, page 4.2-35, Section 4.3.2.7, page 4.3-27, and Section 4.3.3.2, page 4.3-34. E1-17 ENCLOSURE 1 WBN Unit 2 FSAR A100"Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. The Amendment 99 contains three typographical errors at Table 4.1-1. The typos are between Table 4.1-1 and Table 4.4-1 for the same parameters." The exponent on Table 4.1-1 item 8 should be "6" Table 4.1-1 and not "5 39. Section 4.4.3.2.1

° There should be a less than sign before value of 2-100-39 3290 on item 24 of Table 4.1-1* The greater than sign on item 6 of Table 4.1-1 should be deleted2. At Section 4.4.3.2.1, just below "where:" Replace F NAH with F RTPAH40. Table 11.3-8 Revise Land Use Data 2-100-40 41. Section 7.1.2 Modified Section 7.1.2.1.9.

Added cross reference in 2-100-41 Section 7.2.1 Section 7.2.1.1.10 to Section 7.1.2.1.9 El-18 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number 1. The Amendment 99 contains three typographical errors at Table 4.1-1. The typos are between Table 4.1-1 and Table 4.4-1 for the same parameters.

• The exponent on Table 4.1-1 item 8 should be "6" Table 4.1-1 and not "5" 39. Section 4.4.3.2.1

• There should be a less than sign before value of 2-100-39 3290 on item 24 of Table 4.1-1

• The greater than sign on item 6 of Table 4.1-1 should be deleted 2. At Section 4.4.3.2.1, just below "where:" Replace N . RTP F t.H with F t.H 40. Table 11.3-8 Revise Land Use Data 2-100-40 41. Section 7.1.2 Modified Section 7.1.2.1.9.

Added cross reference in 2-100-41 Section 7.2.1 Section 7.2.1.1.10 to Section 7.1.2.1.9 E1-18 ENCLOSUREI WBN Unit 2 FSAR A100"Summary Listing of AI00 FSAR Changes" Item Change Area Change Description Change Package No. II Number Correct spelling, page numbering and punctuation noted during the FSAR review For Table 1.3-3, added a note to the elbow-tab flow measurement discussion.

In Section 7.1.1.2, revised text to read: "Other safety-related, along with non safety-related, display instrumentation is discussed in Section 7.5." In Section 7.1.1.2, relocated the discussion of the BISI to section 7.5.2.2.For Table 7.1-1, note 12, clarified that the TRM calibration interval is determined by the requirements of Reg. Guide 1.133 Rev. 1 Added new section 7.5.1.8 to describe the Post Accident Monitoring System.For Section 7.5.2, added text to clarify that the Plant 42. Section 7.1.2 Computer System is non safety-related and is also 2-100-42Section 7.5.2 referred to as the ICS and plant process computer.For Section 7.5.2, removed "and/or touch screen" Clarified Sections 7.5.2.1 though 7.5.2.3.2 to describe some of the key functions performed by the Plant Computer System." For Section 7.5.2.2, changed "computer based system" to read "function of the Plant Computer System" For Section 7.5.2.3, changed "Nuclear Data Links" to read"Communication Data Links" For Section 7.5.2.3(1), Added "For Watts Bar the Central Emergency Control Center (CECC) is the EOF. " For Section 7.5.2.3(1), Added "Nuclear Data Link" For Section 7.1.2.1.9, Added information to incorporatethe requirements of TSTF-493 43. Section 7.1.2 Further revisions to 7.1.2 and 7.5.2 2-100-43 1 Section 7.5.21 E1-19 ENCLOSURE 1 WBN Unit 2 FSAR A100 "Summary Listing of A100 FSAR Changes" Item Change Area Change Description Change Package No. Number Correct spelling, page numbering and punctuation noted during the FSAR review For Table 1.3-3, added a note to the elbow-tab flow measurement discussion.

In Section 7.1.1.2, revised text to read: "Other safety-related, along with non safety-related, display instrumentation is discussed in Section 7.5." In Section 7.1.1.2, relocated the discussion of the BISI to section 7.5.2.2. For Table 7.1-1, note 12, clarified that the TRM calibration interval is determined by the requirements of Reg. Guide 1.133 Rev. 1 Added new section 7.5.1.8 to describe the Post Accident Monitoring System. For Section 7.5.2, added text to clarify that the Plant 42. Section 7.1.2 Computer System is non safety-related and is also 2-100-42 Section 7.5.2 referred to as the ICS and plant process computer.

For Section 7.5.2, removed "and/or touch screen" Clarified Sections 7.5.2.1 though 7.5.2.3.2 to describe some of the key functions performed by the Plant Computer System." For Section 7.5.2.2, changed "computer based system" to read "function of the Plant Computer System" For Section 7.5.2.3, changed "Nuclear Data Links" to read "Communication Data Links" For Section 7.5.2.3(1), Added "For Watts Bar the Central Emergency Control Center (CECC) is the EOF. " For Section 7.5.2.3(1), Added "Nuclear Data Link" For Section 7.1.2.1.9, Added information to incorporate the requirements of TSTF-493 43. Section 7.1.2 Further revisions to 7.1.2 and 7.5.2 2-100-43 Section 7.5.2 E1-19 ENCLOSURE 2 WBN Unit 2 FSAR A100"Summary of Redacted Pages" Chapter Page(S) Section No. Figure No. Basis For Redaction 1 1.2-15 1.2 1.2-1 Security Related, 1OCFR2.390(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, 1OCFR2.390(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, 1OCFR2.390(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) 2 2.2-8 2.2 2.2-2 Security Related, 10CFR2.390(d)(1) 2 2.4-89 2.4 2.4-2 Security Related, 10CFR2.390(d)(1) 2 2.4-159 2.4 2.4-24 Security Related, 10CFR2.390(d)(1) 2 2.4-162 2.4 2.4-27 Security Related, 1OCFR2.390(d)(1) 2 2.4-163 2.4 2.4-28 Security Related, 10CFR2.390(d)(1) 2 2.4-168 2.4 2.4-40a Security Related, 1 OCFR2.390(d)(1)

Sheet 1 2.4-40a 2 2.4-169 2.4 Sheet 2 Security Related, 10CFR2.390(d)(1) 2 2.4-171 2.4 2.4-40b Security Related, 1OCFR2.390(d)(1) 2 2.4-172 2.4 2.4-40c Security Related, 10CFR2.390(d)(1) 2 2.4-173 2.4 2.4-40c Security Related, 1 OCFR2.390(d)(1) 2 2.4-173 2.4 2.4-40d Security Related, 10CFR2.390(d)(1)

Sheet 1 2 2.4-178 2.4 2.4-40f Security Related, 1 OCFR2.390(d)(1)

Sheet 1 2 2.4-181 2.4 2.4-40g Security Related, 10CFR2.390(d)(1)

Sheet 1 2 2.4-206 2.4 2.4-76 Security Related, 10CFR2.390(d)(1) 2 2.4-209 2.4 2.4-79 Security Related, 10CFR2.390(d)(1) 2 2.4-212 2.4 2.4-82 Security Related, 10CFR2.390(d)(1) 2 2.4-213 2.4 2.4-83 Security Related, 10CFR2.390(d)(1) 2 2.4-218 2.4 2.4-88 Security Related, 10CFR2.390(d)(1) 2 2.4-219 2.4 2.4-89 Security Related, 10CFR2.390(d)(1) 2 2.4-220 2.4 2.4-90 Security Related, 10CFR2.390(d)(1) 2 2.5-471 2.5 2.5-185 Security Related, 10CFR2.390(d)(1) 2 2.5-472 2.5 2.5-185a Security Related, 1OCFR2.390(d)(1) 2 2.5-513 2.5 2.5-225 Security Related, 1OCFR2.390(d)(1) 2 2.5-514 2.5 2.5-226 Security Related, 1OCFR2.390(d)(1) 2 2.5-515 2.5 2.5-226a Security Related, 1-CFR2.390(d)(1) 2 2.5-575 2.5 2.5-273 Security Related, 100FR2.390(d)(1)

E2-1 Chapter 1 1.2-15 1 1.2-16 1 1.2-17 1 1.2-18 1 1.2-19 1 1.2-20 1 1.2-21 1 1.2-22 1 1.2-23 1 1.2-24 1 1.2-25 1 1.2-26 1 1.2-27 1 1.2-28 1 1.2-29 2 2.2-7 2 2.2-8 2 2.4-89 2 2.4-159 2 2.4-162 2 2.4-163 2 2.4-168 2 2.4-169 2 2.4-171 2 2.4-172 2 2.4-173 2 2.4-178 2 2.4-181 2 2.4-206 2 2.4-209 2 2.4-212 2 2.4-213 2 2.4-218 2 2.4-219 2 2.4-220 2 2.5-471 2 2.5-472 2 2.5-513 2 2.5-514 2 2.5-515 2 2.5-575 ENCLOSURE 2 WBN Unit 2 FSAR A100 "Summary of Redacted Pages" Section No. Figure No. Basis For Redaction 1.2 1.2-1 Security Related, 1 OCFR2.390(d)(1) 1.2 1.2-2 Security Related, 10CFR2.390(d)(1) 1.2 1.2-3 Security Related, 10CFR2.390(d)(1) 1.2 1.2-4 Security Related, 1 OCFR2.390(d)(1) 1.2 1.2-5 Security Related, 1 OCFR2.390(d)(1) 1.2 1.2-6 Security Related, 10CFR2.390(d)(1) 1.2 1.2-7 Security Related, 10CFR2.390(d)(1) 1.2 1.2-8 Security Related, 1 OCFR2.390(d)(1) 1.2 1.2-9 Security Related, 10CFR2.390(d)(1) 1.2 1.2-10 Security Related, 10CFR2.390(d)(1) 1.2 1.2-11 Security Related, 10CFR2.390(d)(1) 1.2 1.2-12 Security Related, 10CFR2.390(d)(1) 1.2 1.2-13 Security Related, 10CFR2.390(d)(1) 1.2 1.2-14 Security Related, 10CFR2.390(d)(1) 1.2 1.2-15 Security Related, 1 OCFR2.390(d)(1) 2.2 2.2-1 Security Related, 1 OCFR2.390(d)(1) 2.2 2.2-2 Security Related, 10CFR2.390(d)(1) 2.4 2.4-2 Security Related, 10CFR2.390(d)(1) 2.4 2.4-24 Security Related, 10CFR2.390(d)(1) 2.4 2.4-27 Security Related, 1 OCFR2.390(d)(1) 2.4 2.4-28 Security Related, 1 OCFR2.390(d)(1) 2.4 2.4-40a Security Related, 1 OCFR2.390(d)(1)

Sheet 1 2.4 2.4-40a Security Related, 1 OCFR2.390(d)(1)

Sheet 2 2.4 2.4-40b Security Related, 10CFR2.390(d)(1) 2.4 2.4-40c Security Related, 10CFR2.390(d)(1) 2.4 2.4-40d Security Related, 10CFR2.390(d)(1)

Sheet 1 2.4 2.4-40f Security Related, 10CFR2.390(d)(1)

Sheet 1 2.4 2.4-40 9 Security Related, 10CFR2.390(d)(1)

Sheet 1 2.4 2.4-76 Security Related, 1 OCFR2.390(d)(1) 2.4 2.4-79 Security Related, 1 OCFR2.390(d)(1) 2.4 2.4-82 Security Related, 10CFR2.390(d)(1) 2.4 2.4-83 Security Related, 10CFR2.390(d)(1) 2.4 2.4-88 Security Related, 10CFR2.390(d)(1) 2.4 2.4-89 Security Related, 10CFR2.390(d)(1) 2.4 2.4-90 Security Related, 10CFR2.390(d)(1) 2.5 2.5-185 Security Related, 1 OCFR2.390(d)(1) 2.5 2.5-185a Security Related, 10CFR2.390(d)(1) 2.5 2.5-225 Security Related, 1 OCFR2.390(d)(1) 2.5 2.5-226 Security Related, 1 OCFR2.390(d)(1) . 2.5 2.5-226a Security Related, 10CFR2.390(d)(1) 2.5 2.5-273 Security Related, 10CFR2.390(d)(1)

E2-1 ENCLOSURE2 WBN Unit 2 FSAR AIOO"Summary of Redacted Pages" Chapter Page(S) ISection No. Figure No. Basis For Redaction I 2 2.5-690 2.5 2.5-358 Security Related, 1OCFR2.390(d)(1) 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, 1OCFR2.390(d)(1) 3 3.6-76 3.6 3.6-24 Security Related, 1OCFR2.390(d)(1) 3 3.7-217 3.7 3.7-39 Security Related, 10CFR2.390(d)(1) 3 3.7-218 3.7 3.7-40 Security Related, 10CFR2.390(d)(1) 3 3.7-219 3.7 3.7-41 Security Related, 1OCFR2.390(d)(1) 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) 3 3.8.4-95 3.8.4 3.8.4-3 Security Related, 10CFR2.390(d)(1) 3 3.8.4-96 3.8.4 3.8.4-4 Security Related, 10CFR2.390(d)(1) 3 3.8.4-97 3.8.4 3.8.4-5 Security Related, 10CFR2.390(d)(1) 3 3.8.4-98 3.8.4 3.8.4-6 Security Related, 1OCFR2.390(d)(1) 3 3.8.4-101 3.8.4 3.8.4-9 Security Related, 10CFR2.390(d)(1) 3 3.8.4-109 3.8.4 3.8.4-17 Security Related, 10CFR2.390(d)(1) 3 3.8.4-110 3.8.4 3.8.4-18 Security Related, 10CFR2.390(d)(1) 3 3.8.4-111 3.8.4 3.8.4-19 Security Related, 1OCFR2.390(d)(1) 3 3.8.4-112 3.8.4 3.8.4-20 Security Related, 10CFR2.390(d)(1) 3 3.8.4-116 3.8.4 3.8.4-24 Security Related, 10CFR2.390(d)(1) 3 3.8.4-120 3.8.4 3.8.4-28 Security Related, 10CFR2.390(d)(1) 3 3.8.4-127 3.8.4 3.8.4-35 Security Related, 10CFR2.390(d)(1) 3 3.8.4-128 3.8.4 3.8.4-36 Security Related, 10CFR2.390(d)(1) 3 3.8.4-129 3.8.4 3.8.4-36a Security Related, 1OCFR2.390(d)(1) 3 3.8.4-132 3.8.4 3.8.4-37 Security Related, 1OCFR2.390(d)(1) 3 3.8.4-149 3.8.4 3.8.4-50 Security Related, 1OCFR2.390(d)(1) 3 3.8.4-150 3.8.4 3.8.4-51 Security Related, 10CFR2.390(d)(1) 3 3.8.6-19 3.8.6 3.8.6-7 Security Related, 10CFR2.390(d)(1) 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)(1) 6 6.2.3-77 6.2.3 6.2.3-5 Security Related, 10CFR2.390(d)(1) 6 6.2.3-78 6.2.3 6.2.3-6 Security Related, 10CFR2.390(d)(1) 6 6.2.3-79 6.2.3 6.2.3-7 Security Related, 10CFR2.390(d)(1) 6 6.2.3-80 6.2.3 6.2.3-8 Security Related, 10CFR2.390(d)(1) 6 6.2.3-81 6.2.3 6.2.3-9 Security Related, 10CFR2.390(d)(1) 6 6.2.3-82 6.2.3 6.2.3-10 Security Related, 10CFR2.390(d)(1) 6 6.2.3-92 6.2.3 6.2.3-18 Security Related, 10CFR2.390(d)(1) 6 6.2.3-93 6.2.3 6.2.3-19 Security Related, 10CFR2.390(d)(1) 8 8.1-21 8.1 8.1-1 Security Related, 1OCFR2.390(d)(1) 8 8.2-14 8.2 Text only Security Related, 1OCFR2.390(d)(1)

E2-2 Chapter 2 2.5-690 2 2.5-934 3 3.5-53 3 3.5-54 3 3.6-73 3 3.6-74 3 3.6-75 3 3.6-76 3 3.7-217 3 3.7-218 3 3.7-219 3 3.7-222 3 3.8.3-60 3 3.8.3-61 3 3.8.4-94 3 3.8.4-95 3 3.8.4-96 3 3.8.4-97 3 3.8.4-98 3 3.8.4-101 3 3.8.4-109 3 3.8.4-110 3 3.8.4-111 3 3.8.4-112 3 3.8.4-116 3 3.8.4-120 3 3.8.4-127 3 3.8.4-128 3 3.8.4-129 3 3.8A .. 132 3 3.8.4-149 3 3.8.4-150 3 3.8.6-19 6 6.2.2-24 6 6.2.3-76 6 6.2.3-77 6 6.2.3-78 6 6.2.3-79 6 6.2.3-80 6 6.2.3-81 6 6.2.3-82 6 6.2.3-92 6 6.2.3-93 8 8.1-21 8 8.2-14 ENCLOSURE 2 WBN Unit 2 FSAR A100 "Summary of Redacted Pages" Section No. Figure No. Basis For Redaction 2.5 2.5-358 Security Related, 1 OCFR2.390(d)(1) 2.5 2.5-592 Security Related, 10CFR2.390(d)(1) 3.5 3.5-3 Security Related, 10CFR2.390(d)(1) 3.5 3.5-4 Security Related, 1 OCFR2.390(d)(1) 3.6 3.6-21 Security Related, 1 OCFR2.390(d)(1) 3.6 3.6-22 Security Related, 10CFR2.390(d)(1) 3.6 3.6-23 Security Related, 10CFR2.390(d)(1) 3.6 3.6-24 Security Related, 10CFR2.390(d)(1) 3.7 3.7-39 Security Related, 1 OCFR2.390(d)(1) 3.7 3.7-40 Security Related, 1 OCFR2.390(d)(1) 3.7 3.7-41 Security Related, 10CFR2.390(d)(1) 3.7 3.7-44 Security Related, 10CFR2.390(d)(1) 3.8.3 3.8.3-6 Security Related, 10CFR2.390(d)(1) 3.8.3 3.8.3-7 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-2 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-3 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-4 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-5 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-6 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-9 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-17 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-18 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-19 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-20 Security Related, 1 OCFR2. 390( d)( 1 ) 3.8.4 3.8.4-24 Security Related, 10CFR2.390(d)(1) 3.8A 3.8.4-28 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-35 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-36 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-36a Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-37 Security Related, 10CFR2.390(d)(1) 3.8.4 3.8.4-50 Security Related, 1 OCFR2.390(d)(1) 3.8.4 3.8.4-51 Security Related, 10CFR2.390(d)(1) 3.8.6 3.8.6-7 Security Related, 10CFR2.390(d)(1) 6.2.2 6.2.2-4 Security Related, 1 OCFR2. 390( d)( 1) 6.2.3 6.2.3-4 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-5 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-6 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-7 Security Related, 1 OCFR2.390(d)(1) 6.2.3 6.2.3-8 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-9 Security Related,1 OCFR2.390(d)(1) 6.2.3 6.2.3-10 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-18 Security Related, 10CFR2.390(d)(1) 6.2.3 6.2.3-19 Security Related, 10CFR2.390(d)(1) 8.1 8.1-1 Security Related, 1 OCFR2.390(d)(1) 8.2 Text only Security Related, 1 OCFR2.390(d)(1)

E2-2 ENCLOSURE2 WBN Unit 2 FSAR AIOO"Summary of Redacted Pages" Chapter Page(s, Section No. Figure No. BasisForRedaction 8 8.2-15 8.2 Text only Security Related, 10CFR2.390(d)(1) 8 8.2-30 8.2 8.2-3 Security Related, 10CFR2.390(d)(1) 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, 1OCFR2.390(d)(1) 8 8.3-97 8.3 8.3-1 Security Related, 10CFR2.390(d)(1) 8 8.3-99 8.3 8.3-2 Security Related, 10CFR2.390(d)(1) 8 8.3-100 8.3 8.3-3 Security Related, 1OCFR2.390(d)(1) 8 8.3-102 8.3 8.3-4b Security Related, 10CFR2.390(d)(1) 8 8.3-205 8.3 8.3-46 Security Related, 10CFR2.390(d)(1) 8 8.3-218 8.3 8.3-59 Security Related, 1OCFR2.390(d)(1) 9 9.2-208 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) 9 9.4-281 9.4 9.4-23 Security Related, 10CFR2.390(d)(1) 9 9.4-282 9.4 9.4-24 Security Related, 1OCFR2.390(d)(1) 12 12.3-39 12.3 12.3-1 Security Related, 1 OCFR2.390(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, 1OCFR2.390(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, 1OCFR2.390(d)(1) 12 12.3-45 12.3 12.3-7 Security Related, 1 OCFR2.390(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, 1OCFR2.390(d)(1) 12 12.3-50 12.3 12.3-12 Security Related, 1OCFR2.390(d)(1) 12 12.3-51 12.3 12.3-13 Security Related, 1OCFR2.390(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, 1OCFR2.390(d)(1) 12 12.3-55 12.3 12.3-17 Security Related, 10CFR2.390(d)(1) 12 12.4-5 12.4 12.4-1 Security Related, 10CFR2.390(d)(1)

E2-3 Chapter 8 8.2-15 8 8.2-30 8 8.2-31 8 8.2-44 8 8.3-97 8 8.3-99 8 8.3-100 8 8.3-102 8 8.3-205 8 8.3-218 9 9.2-208 9 9.4-276 9 9.4-280 9 9.4-281 9 9.4-282 12 12.3-39 12 12.3-40 12 12.3-41 12 12.3-42 12 12.3-43 12 12.3-44 12 12.3-45 12 12.3-46 12 12.3-47 12 12.3-48 12 12.3-49 12 12.3-50 12 12.3-51 12 12.3-52 12 12.3-53 12 12.3-54 12 12.3-55 12 12.4-5 ENCLOSURE 2 WBN Unit 2 FSAR A100 "Summary of Redacted Pages" Section No. Figure No. Basis For Redaction 8.2 Text only Security Related, 1 OCFR2.390(d)(1) 8.2 8.2-3 Security Related, 10CFR2.390(d)(1) 8.2 8.2-4 Security Related, 1 OCFR2.390(d)(1) 8.2 8.2-11 Security Related, 1 OCFR2.390(d)(1) 8.3 8.3-1 Security Related, 10CFR2.390(d)(1) 8.3 8.3-2 Security Related, 10CFR2.390(d)(1) 8.3 8.3-3 Security Related, 10CFR2.390(d)(1) 8.3 8.3-4b Security Related, 10CFR2.390(d)(1) 8.3 8.3-46 Security Related, 1 OCFR2.390(d)(1) 8.3 8.3-59 Security Related, 1 OCFR2.390(d)(1) 9.2 9.2-40 Security Related, 10CFR2.390(d)(1) 9.4 9.4-21 Security Related, 10CFR2.390(d)(1) 9.4 9.4-22c Security Related, 10CFR2.390(d)(1) 9.4 9.4-23 Security Related, 1 OCFR2.390(d)(1) 9.4 9.4-24 Security Related, 10CFR2.390(d)(1) 12.3 12.3-1 Security Related, 10CFR2.390(d)(1) 12.3 12.3-2 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-3 Security Related, 10CFR2.390(d)(1) 12.3 12.3-4 Security Related, 10CFR2.390(d)(1) 12.3 12.3-5 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-6 Security Related, 10CFR2.390(d)(1) 12.3 12.3-7 Security Related, 10CFR2.390(d)(1) 12.3 12.3-8 Security Related, 10CFR2.390(d)(1) 12.3 12.3-9 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-10 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-11 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-12 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-13 Security Related, 10CFR2.390(d)(1) 12.3 12.3-14 Security Related, 10CFR2.390(d)(1) 12.3 12.3-15 Security Related, 10CFR2.390(d)(1) 12.3 12.3-16 Security Related, 1 OCFR2.390(d)(1) 12.3 12.3-17 Security Related, 10CFR2.390(d)(1) 12.4 12.4-1 Security Related, 10CFR2.390(d)(1)

E2-3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes TVA WBN-2_FSARFiles 001WTVAWBFSAR TOC.pdf 366,173 002WTVA WB FSAR LRP.pdf 96,986 003 TVA WB FSAR Section 1.pdf 4,642,334 004WTVAWBFSAR Section 2 A.pdf 10,171,101 005WTVAWBFSARSection 2 B Part 1 of 2.pdf 41,119,426 005WTVAWBFSARSection 2 B Part 2 of_2.pdf 12,384,340 006WTVA WB FSAR Section_2_C.pdf 2,107,687 007WTVA WB FSAR Section 2 D.pdf 31,323,905 008WTVAWBFSARSection 2_E.pdf 47,312,484 009WTVA WB FSAR Section 3 A.pdf 2,626,339 010WTVAWBFSAR Section 3 B.pdf 7,063,345 011 WTVAWBFSARSection 3 C.pdf 30,016,872 012WTVAWBFSARSection_3_D.pdf 6,017,930 013 TVAWBFSAR Section 4.pdf 12,558,754 014_TVAWBFSARSection_5.pdf 9,915,991 015_TVAWBFSAR Section 6 A.pdf 20,327,763 016 TVA WB FSAR Section 6 B.pdf 8,348,374 017WTVA WB FSAR Section_7.pdf 9,420,373 018WTVAWBFSARSection_8.pdf 29,723,822 019WTVA WB FSAR Section 9 A.pdf 24,762,572 020 TVA WB FSAR Section_9_B.pdf 16,484,969 021 TVA WB FSAR Section 10.pdf 14,162,890 022_-VAWB FSARSection-1 .pdf 3,924,117 023WTVAWBFSARSectionI 2.pdf 5,974,153 024 TVA WBFSARSection 13.pdf 3,238,509 025WTVAWBFSARSection_14.pdf 1,168,143 Page 1 of 3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes TVA WBN-2 FSAR Files 001_ TVA_WB_FSAR_

TOC.pdf 366,173 002 TVA WB FSAR LRP.pdf 96,986 003 TVA WB FSAR Section 1.pdf 4,642,334 004 TVA WB FSAR Section 2 A.pdf 10,171,101 005 TVA WB FSAR Section 2 B Part 1 of 2.pdf 41,119,426 005 TVA WB FSAR Section 2 B Part 2 of 2.pdf 12,384,340 006 TVA WB FSAR Section 2 C.pdf 2,107,687 007 TVA WB FSAR Section 2 D.pdf 31,323,905 008 TVA WB FSAR Section 2 E.pdf 47,312,484 009 TVA WB FSAR Section 3 A.pdf 2,626,339 010 TVA WB FSAR Section 3 B.pdf 7,063,345 011 TVA WB FSAR Section 3 C.pdf 30,016,872 012 TVA WB FSAR Section 3 D.pdf 6,017,930 013 TVA WB FSAR Section 4.pdf 12,558,754 014 TVA WB FSAR Section 5.pdf 9,915,991 015 TVA WB FSAR Section 6 A.pdf 20,327,763 016 TVA WB FSAR Section 6 B.pdf 8,348,374 017 TVA WBFSAR Section 7.pdf 9,420,373 018 TVA WB FSAR Section 8.pdf 29,723,822 019 TVA WB FSAR Section 9 A.pdf 24,762,572 020 TVA WB FSAR Section 9 B.pdf 16,484,969 021 TVA WB FSAR Section 10.pdf 14,162,890 022 TVA WB FSAR Section 11.pdf 3,924,117 023 TVA WB FSAR Section 12.pdf . 5,974,153 024 TVA WB FSAR Section 13.pdf 3,238,509 025 TVA WB FSAR Section 14.pdf 1,168,143 Page 1 of 3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes 026 TVA WB FSARSection_

15.pdf 35,478,686 027 TVA WB FSAR Section_16.pdf 148,224 028 TVA WB FSARSection_17.pdf 144,827 Total 391,031,089 TVAWBN-2_Oversized_FSARFigures 001 TVA WB FSAR Figure 2.5 3.pdf 1,757,743 002-TVA WBFSAR Figure 2.5 11.pdf 1,689,538 003 TVA WB FSAR Figure 2.5 71.pdf 2,263,087 004 TVA WB FSAR Figure 2.5 222.pdf 909,429 005_TVA WB FSAR Figure 2.5 281 1.pdf 2,155,627 006 TVA WB FSAR Figure 2.5 281 2.pdf 2,117,562 007_TVAWBFSAR Figure 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_TVAWBFSARFigure 2.5 549 4.pdf 2,809,599 011_TVA WBFSAR Figure 2.5 550.pdf 1,803,985 012_TVAWBFSARFigure 2.5 551.pdf 1,996,869 013_TVAWBFSARFigure 2.5 554 1.pdf 3,081,060 014_TVA WBFSAR Figure 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_TVA WBFSAR Figure 2.5 571_1.pdf 844,484 018_TVA WB FSAR Figure 2.5 571_2.pdf 3,128,329 019_TVA WBFSAR Figure 2.5 571_3.pdf 3,284,555 020_TVAWBFSARFigure 2.5 571 4.pdf 2,142,316 021_TVA WB FSAR Figure 2.5 572.pdf 2,196,945 Page 2 of 3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes 026 TVA WB FSAR Section 15.pdf 35,478,686 027 TVA WB FSAR Section 16.pdf 148,224 028 TVA WB FSAR Section 17.pdf 144,827 Total 391,031,089 TVA_WBN-2 Oversized FSAR Figures 001 TVA WB FSAR Figure 2.5* 3.pdf 1,757,743 002 TVA WB FSAR Figure 2.5 11.pdf 1,689,538 003 TVA WB FSAR Figure 2.5 71.pdf 2,263,087 004 TVA WB FSAR Figure 2.5 222.pdf 909,429 005 TVA WB_FSAR_Figure_2.5 281 1.pdf 2,155,627 006 TVA WB_FSAR Figure 2.5 281 2.pdf 2,117,562 007 TVA WB FSAR Figure 2.5 549 1.pdf -3,600,807 008 TVA WB_FSAR Figure 2.5 549 2.pdf *3,989,180 009 TVA* WB FSAR Figure 2.5 549 3.pdf 2,863,719 010 TVA WB FSAR Figure 2.5 549 4.pdf 2,809,599 011 TVA WB FSAR Figure 2.5 550.pdf 1,803,985 012 TVA WB FSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB FSAR Figure 2.5 554 1.pdf 3,081,060 014 TVA WB FSAR Figure 2.5 554 2.pdf 1,996,707 015 TVA WB FSAR Figure 2.5 555.pdf 1,993,312 016 TVA WB FSAR Figure 2.5 556.pdf 2,998,087 017 TVA WB FSAR Figure 2.5 571 1.pdf 844,484 018 TVA WB_FSAR_Figure_2.5_571_2.pdf 3,128,329 019 TVA WB FSAR Figure 2.5 571 3.pdf 3,284,555 020 TVA WB FSAR Figure 2.5 571 4.pdf 2,142,316 021 TVA WB FSAR Figure 2.5 572.pdf 2,196,945 Page 2 of 3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes 022_TVAWBFSAR Figure 2.5 573.pdf 2,013,286 023-TVAWBFSAR Figure 2.5 576 1.pdf 3,238,525 024_-VAWBFSAR Figure 2.5 576 2.pdf 2,151,750 025_FVAWBFSAR Figure 2.5 577.pdf 2,207,622 026_-VAWBFSAR Figure 2.5 578.pdf 2,080,032 027_-VA WB FSAR Figure 2.5 579.pdf 2,308,985 028_-VAWBFSAR Figure 2.5 583.pdf 2,487,346 029_TVAWB FSAR Figure 2.5 588.pdf 2,528,515 030WTVAWBFSAR Figure 2.5 589.pdf 2,480,438 031_TVAWBFSAR Figure 2.5 594.pdf 13,054,127 032WTVAWBFSAR Figure 2.5 595.pdf 2,323,267 033_TVA WBFSAR Figure 2.5 596.pdf 5,732,107 034WTVAWBFSAR Figure 2.5 597.pdf 1,287,336 035WTVAWBFSAR Figure 2.5 602.pdf 5,549,537 036WTVAWBFSAR Figure 2.5 603.pdf 4,830,835 037WTVAWBFSAR Figure 2.5 604.pdf 6,392,279 038WTVAWBFSARFigure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA WBN-2_OversizedFSARTable 001 WVAWBFSARTable_6.2.4-1 .pdf 1,211,706 Total 1,211,706 Page 3 of 3 ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 -List of Files on Security-Related OSM File Name File Size -Bytes 022 TVA WB FSAR Figure 2.5 573.pdf 2,013,286 023 TVA WB FSAR Figure 2.5 576 1.pdf 3,238,525 024 TVA WB FSAR Figure 2.5 576 2.pdf 2,151,750 025_ TVA_WB_FSAR_Figure_2.5_577.pdf 2,207,622 026 TVA WB FSAR Figure 2.5 578.pdf 2,080,032 027 TVA WB FSAR Figure 2.5 579.pdf 2,308,985 028_ TV A_WB_FSAR_Figure_2.5_583.pdf 2,487,346 029 TVA WB FSAR Figure 2.5 588.pdf 2,528,515 030 TVA WB FSAR Figure 2.5 589.pdf 2,480,438 031_TVA_WB_FSARJigure_2.5_594.pdf 13,054,127 032 TVA WB FSAR Figure 2.5 595.pdf 2,323,267 033 TVA WB FSAR Figure 2.5 596.pdf 5,732,107 034 TVA WB FSAR Figure 2.5 597.pdf 1,287,336 035 TVA WB FSAR Figure 2.5 602.pdf 5,549,537 036 TVA WB FSAR Figure 2.5 603.pdf 4,830,835 037 TVA WB FSAR Figure 2.5 604.pdf 6,392,279 038_TVA_WB_FSAR Figure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA WBN-2 Oversized FSAR Table 001 TVA WB FSAR Table 6.2.4-1.pdf 1,211,706 Total 1,211,706 Page 3 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM File Name File Size -Bytes TVA WBN-2_FSARFiles 001 TVAWBFSARTOC.pdf 366,173 002_TVAWBFSARLEP.pdf 96,986 003WTVAWBFSARSection_

1.pdf 835,757 004 TVA WB FSAR Section 2_A.pdf 9,834,570 005WTVAWBFSARSection 2 B Part l of_2.pdf 32,435,095, 005 TVA_WBFSARSection 2 B Part 2 of_2.pdf 9,344,623 006WTVAWBFSAR Section 2 C.pdf 2,107,687 007WTVAWBFSARSection 2_D.pdf 31,323,905 008 TVA WB FSAR Section 2_E.pdf 45,933,134 009WTVAWBFSARSection_3_A.pdf 2,334,907 010WTVAWBFSARSection_3_B.pdf 6,576,229 011 WTVAWBFSARSection_3_C.pdf 25,184,333 012_TVAWBFSAR Section_3_D.pdf 5, 749,252 013 TVA WB FSAR Section 4.pdf 12,558,754 014_TVA WB FSAR Section 5.pdf 9,915,991 015_-VAWBFSARSection_6_A.pdf 17,447,269 016WTVA WB FSAR Section 6_B.pdf 8,348,374 017WTVA_WBFSARSection_7.pdf 9,420,373 018 TVA WB FSAR Section 8.pdf 26,799,159 019WTVA WBFSARSection 9 A.pdf 24, 762,572 020 WVA WB FSAR Section 9_B.pdf 15,270,336 021 WTVAWBFSARSectionI 0.pdf 14,162,890 022_-VAWBFSARSection_

1 .pdf 3,924,117 023 TVA WBFSARSection 12.pdf 1,706,267 024 TVA WB FSAR Section 13.pdf 3,238,509 025 WTVAWBFSAR Section 14.pdf 1,168,143 026_TVA_WB FSARSection 1 5.pdf 35,478,686 Note: Byte amounts in italics are redacted files.Page 1 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM File Name File Size -Bytes TVA WBN-2 FSAR Files 001 TVA WB FSAR TOC.pdf 366,173 002 TVA WB FSAR LEP.pdf 96,986 003 TVA WB FSAR Section 1.pdf 835,757 004 TVA WB FSAR Section 2 A.pdf 9,834,570 005 TVA WB FSAR Section 2 B Part 1 of 2.pdf 32,435,095.

005 TVA WB FSAR Section 2 B Part 2 of 2.pdf . 9,344,623 006 TVA WB FSAR Section 2 C.pdf 2,107,687 007 TVA WB FSAR Section 2 D.pdf 31,323,905

.008 TVA WB FSAR Section 2 E.pdf 45,933,134 009 TVA WB FSAR Section 3 A.pdf 2,334,907 010 TVA WB FSAR Section 3 B.pdf 6,576,229 011 TVA WB FSAR Section 3 C.pdf 25,184,333 012 TVA WB FSAR Section.3 D.pdf 5,749,252 013 TVA WB FSAR Section 4.pdf 12,558,754 014 TVA WB FSAR Section 5.pdf 9,915,991 015 TVA WB FSAR Section 6 A.pdf 17,447,269 016 TVA WB FSAR Section 6 B.pdf 8,348,374 017 TVA WB FSAR Section 7.pdf 9,420,373 018 TVA WB FSAR Section 8.pdf 26,799,159 019 TVA WB FSAR Section 9 A.pdf 24,762,572 020 TVA WB FSAR Section 9 B.pdf 15,270,336 021 TVA WB FSAR Section 10.pdf 14,162,890 022 TVA WB FSAR Section 11.pdf 3,924,117 023 TVA WB FSAR Section 12.pdf 1,706,267 024 TVA WB FSAR Section 13.pdf 3,238,509 025 TVA WB FSAR Section 14.pdf 1,168,143 026 TVA WB FSAR Section 15.pdf 35,478,686 Note: Byte amounts in italics are redacted files. Page 1 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM File Name File Size -Bytes 027_-I-AWBFSARSectionI 6.pdf 148,224 028-TVA WB FSAR Section 17.pdf 144,827 Total 356,617,142 TVAWBN-2 Oversized_FSARFigures 001WTVA WBFSAR Figure 2.5 3.pdf 1,757,743 002WTVAWBFSARFigure 2.51 1.pdf 1,689,538 003WTVAWBFSAR Figure 2.5 71.pdf 2,263,087 004WTVAWBFSAR Figure 2.5 222.pdf 909,429 005WTVA WBFSAR Figure 2.5 281 1.pdf 2,155,627 006 TVA WBFSAR Figure 2.5 281_2.pdf 2,117,562 007_TVAWBFSARFigure_2.5 549_1.pdf 3,600,807 008_TVAWBFSAR Figure 2.5 549_2.pdf 3,989,180 009WTVAWBFSAR Figure 2.5 549 3.pdf 2,863,719 010WTVAWBFSARFigure 2.5 549 4.pdf 2,809,599 011_TVA_WB_FSAR Figure 2.5 550.pdf 1,803,985 012_TVAWBFSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB-FSAR Figure 2.5 554 1.pdf 3,081,060 014WTVA WBFSAR Figure 2.5 554 2.pdf 1,996,707 015WTVAWBFSAR Figure 2.5 555.pdf 1,993,312 016WTVAWBFSAR Figure 2.5 556.pdf 2,998,087 017_TVA WBFSAR Figure 2.5 571_1.pdf 844,484 018 TVA WBFSAR Figure 2.5 57 1 2.pdf 3,128,329 019WTVAWBFSAR Figure 2.5 571_3.pdf 3,284,555 020WTVA WBFSAR Figure 2.5 571 4.pdf 2,142,316 021 TVA WBFSAR Figure 2.5 572.pdf 2,196,945 022WTVAWBFSARFigure 2.5 573.pdf 2,013,286 023_TVAWBFSARFigure 2.5 576_1.pdf 3,238,525 Note: Byte amounts in italics are redacted files.Page 2 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM FileName File Size -Bytes 027 TVA WB FSAR Section 16.pdf 148,224 028 TVA WB FSAR Section 17.pdf 144,827 Total 356,617,142 TVA WBN-2 Oversized FSAR Figures 001 TVA WB FSAR Figure 2.5 3.pdf 1,757,743 002 TVA WB FSAR Figure 2.5 11.pdf 1,689,538 003 TVA WB FSAR Figure 2.5 71.pdf 2,263,087 004 TVA WB FSAR Figure 2.5 222.pdf 909,429 005 TVA WB FSAR Figure 2.5 281 1.pdf 2,155,627 006 TVA WB FSAR Figure 2.5 281 2.pdf 2,117,562 007 TVA WB FSAR Figure 2.5 549 1.pdf 3,600,807 008 TVA WB FSAR Figure 2.5 549 2.pdf 3,989,180 009 TVA WB FSAR Figure 2.5 549 3.pdf 2,863,719 010 TVA WB FSAR Figure 2.5 549 4.pdf 2,809,599 011 TVA WB FSAR Figure 2.5 550.pdf 1,803,985 012 TVA WB FSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB FSAR Figure 2.5 554 1.pdf 3,081,060 014 TVA WB FSAR Figure 2.5 554 2.pdf 1,996,707 015_TVA_WB_FSAR_Figure_2.5_555.pdf 1,993,312 016 TVA WB FSAR Figure 2.5 556.pdf 2,998,087 017 TVA WB FSAR Figure 2.5 571 1.pdf 844,484 018 TVA WB FSAR Figure 2.5 571 2.pdf 3,128,329 019 TVA WB FSAR Figure 2.5 571 3.pdf 3,284,555 020 TVA WB FSAR Figure 2.5 571 4.pdf 2,142,316 021 TVA WB FSAR Figure 2.5 572.pdf 2,196,945 022 TVA WB FSAR Figure 2.5 573.pdf 2,013,286 023 TVA WB FSAR Figure 2.5 576 1.pdf 3,238,525 Note: Byte amounts in italics are redacted files. Page 2 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM File Name File Size -Bytes 024_TVAWBFSAR Figure 2.5 576 2.pdf.

2,151,750 025 TVA WBFSAR Figure 2.5 577.pdf 2,207,622 026_TVA WBFSAR Figure 2.5 578.pdf 2,080,032 027 TVA WBFSAR Figure 2.5 579.pdf 2,308,985 028 TVA WB FSAR Figure 2.5 583.pdf 2,487,346 029_TVAWB FSAR Figure 2.5 588.pdf 2,528,515 030_TVAWBFSAR Figure 2.5 589.pdf 2,480,438 031 TVA WB FSAR Figure 2.5 594.pdf 13,054,127 032_TVA WB_FSAR Figure 2.5 595.pdf 2,323,267 033_TVAWBFSAR Figure 2.5 596.pdf 5,732,107 034_TVA WB FSAR Figure 2.5 597.pdf 1,287,336 035_TVAWBFSAR Figure 2.5 602.pdf 5,549,537 036_TVA WB FSAR Figure 2.5_603.pdf 4,830,835 037_TVA WB FSAR Figure 2.5 604.pdf 6,392,279 038_TVA WBFSAR Figure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA WBN-2_OversizedFSARTable 001 TVA WB FSARTable_6.2.4-1.pdf 1,211,706 Total 1,211,706Note: Byte amounts in italics are redacted files.Page 3 of 3 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 100 List of Files on Publicly Available OSM File Name File Size -Bytes 024 TVA WB FSAR Figure 2.5 576 2.pdf. 2,151,750 025 TVA WB FSAR Figure 2.5 577.pdf 2,207,622 026 TVA WB FSAR Figure 2.5 578.pdf 2,080,032 027_ TVA_WB_FSAR_Figure_2.5_579.pdf 2,308,985 028_TVA WB FSAR_Figure_2.5 583.pdf 2,487,346 029 TVA WB FSAR Figure 2.5 588.pdf 2,528,515 030 TVA WB FSAR Figure 2.5 589.pdf . 2,480,438 031_ TVA WB_FSAR_Figure_2.5 594.pdf 13,054,127 032 TVA WB FSAR Figure 2.5 595.pdf 2,323,267 033 TVA WB FSAR Figure 2.5 596.pdf 5,732,107 034 TVA WB FSAR Figure 2.5 597.pdf 1,287,336 035_ TVA WB FSAR_Figure_2.5 602.pdf 5,549,537 036 TVA WB FSAR Figure 2.5 603.pdf 4,830,835 037 TVA WB FSAR Figure 2.5 604.pdf 6,392,279 038 TVA WB FSAR Figure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA_WBN-2_0versized_FSAR_Table 001 TVA WB FSAR Table 6.2.4-1.pdf 1,211,706 Total 1,211,706 Note: Byte amounts in italics are redacted files. Page 3 of 3 ENCLOSURE 5 WBN Unit 2 FSAR A100"List of Commitments"1. A revision to the WBN Unit 2 Technical Specifications will be provided via separate letter to provide consistency with the setpoint methodology changes provided in A100 and Technical Specification Tracking Form 493.2. TVA will submit a combined Unit 1 and Unit 2 FSAR with the first update of the Unit 1 UFSAR after Unit 2 is licensed.E5-1 ENCLOSURE 5 WBN Unit 2 FSAR A 100 "List of Commitments" 1. A revision to the WBN Unit 2 Technical Specifications will be provided via separate letter to provide consistency with the setpoint methodology changes provided in A100 and Technical Specification Tracking Form 493. 2. TVA will submit a combined Unit 1 and Unit 2 FSAR with the first update of the Unit 1 UFSAR after Unit 2 is licensed.

E5-1