ML14051A680

From kanterella
Jump to navigation Jump to search
Final Safety Analysis Report, Amendment 111
ML14051A680
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 02/13/2014
From: Hruby R
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14051A680 (14)


Text

Attachment 1 to be withheld from Public Disclosure Under 10 CFR 2.390. When separated from this Enclosure, this letter is decontrolled.

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 February 13, 2014 10 CFR 50.4 10 CFR 50.34(b) 10 CFR 2.390(d)(1)

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

Subject:

WATTS BAR NUCLEAR PLANT (WBN) - UNIT 2 - FINAL SAFETY ANALYSIS REPORT (FSAR), AMENDMENT 111

Reference:

1. TVA letter to NRC dated August 14, 2013, "Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR), Amendment 110" This letter transmits WBN Unit 2 FSAR Amendment 111 (Al 11), which reflects changes made since the issuance of Amendment 110 on August 14, 2013 (Reference 1). contains a summary listing of FSAR sections and corresponding Unit 2 change package numbers associated with the Al 11 FSAR changes.

FSAR Al 11 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. 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).

There are no new commitments made in this letter. This letter does not close any "Generic Communications." If you have any questions, please contact Gordon Arent.

at (423) 365-2004.

=11, U.S. Nuclear Regulatory Commission Page 2 February 13, 2014 I declare under the penalty of perjury that the foregoing is true and correct. Executed on the 13th day of February, 2014.

Respectfully, Raymond A. Hruby, Jr.

General Manager, Technical Services Watts Bar Unit 2

Enclosures:

1. WBN Unit 2 FSAR Al 11, "Summary Listing of Al 11 FSAR Changes"
2. WBN Unit 2 FSAR Al 11, "Summary of Redacted Pages"
3. WBN Unit 2 FSAR Al 11, "List of files and file sizes on the security-related OSM (OSM #1)"
4. WBN Unit 2 FSAR Al 11, "List of files and file sizes on the publicly available OSM (OSM #2)"

Attachments:

1. OSM #1: WBN Unit 2 FSAR Amendment 111 - Security-Related Information - Withhold Under 10 CFR 2.390
2. OSM #2: WBN Unit 2 FSAR Amendment 111 - Publicly Available Version cc: See Page 3

U.S. Nuclear Regulatory Commission Page 3 February 13, 2014 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

I I

I I

ENCLOSURE 2 WBN Unit 2 FSAR All 1 "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, 10CFR2.390(d)(1) 1 1.2-16 1.2 1.2-2 Security Related, 10CFR2.390(d)(1) 1 1.2-17 1.2 1.2-3 Security Related, 10CFR2.390(d)(1) 1 1.2-18 1.2 1.2-4 Security Related, 10CFR2.390(d)(1) 1 1.2-19 1.2 1.2-5 Security Related, 10CFR2.390(d)(1) 1 1.2-20 1.2 1.2-6 Security Related, 10CFR2.390(d)(1) 1 1.2-21 1.2 1.2-7 Security Related, 10CFR2.390(d)(1) 1 1.2-22 1.2 1.2-8 Security Related, 10CFR2.390(d)(1) 1 1.2-23 1.2 1.2-9 Security Related, 10CFR2.390(d)(1) 1 1.2-24 1.2 1.2-10 Security Related, 10CFR2.390(d)(1) 1 1.2-25 1.2 1.2-11 Security Related, 10CFR2.390(d)(1) 1 1.2-26 1.2 1.2-12 Security Related, 10CFR2.390(d)(1) 1 1.2-27 1.2 1.2-13 Security Related, 10CFR2.390(d)(1) 1 1.2-28 1.2 1.2-14 Security Related, 10CFR2.390(d)(1) 1 1.2-29 1.2 1.2-15 Security Related, 10CFR2.390(d)(1) 2 2.2-7 2.2 2.2-1 Security Related, 10CFR2.390(d)(1) 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, 10CFR2.390(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

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

Sheet 1 2

2.4-178 2.4 2.4-40f Security Related, 10CFR2.390(d)(1)

Sheet 1 2

2.4-181 2.4 2.4-40g Security Related, 1 OCFR2.390(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, 10CFR2.390(d)(1) 2 2.5-513 2.5 2.5-225 Security Related, 10CFR2.390(d)(1) 2 2.5-514 2.5 2.5-226 Security Related, 10CFR2.390(d)(1) 2 2.5-515 2.5 2.5-226a Security Related, 10CFR2.390(d)(1) 2 2.5-575 2.5 2.5-273 Security Related, 10CFR2.390(d)(1) 2 2.5-690 2.5 2.5-358 Security Related, 10CFR2.390(d)(1)

E2-1

I I

ENCLOSURE 2 WBN Unit 2 FSAR Al 11 "Summary of Redacted Pages" Chapter Page(S) ISection No.

Figure No.1 Basis For Redaction I

2 2.5-934 2.5 2.5-592 Security Related, 10CFR2.390(d)(1) 3 3.5-53 3.5 3.5-3 Security Related, 10CFR2.390(d)(1) 3 3.5-54 3.5 3.5-4 Security Related, 10CFR2.390(d)(1) 3 3.6-73 3.6 3.6-21 Security Related, 10CFR2.390(d)(1) 3 3.6-74 3.6 3.6-22 Security Related, 10CFR2.390(d)(1) 3 3.6-75 3.6 3.6-23 Security Related, 10CFR2.390(d)(1) 3 3.6-76 3.6 3.6-24 Security Related, 10CFR2.390(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, 10CFR2.390(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, 10CFR2.390(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, 10CFR2.390(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, 10CFR2.390(d)(1) 3 3.8.4-132 3.8.4 3.8.4-37 Security Related, 10CFR2.390(d)(1) 3 3.8.4-149 3.8.4 3.8.4-50 Security Related, 10CFR2.390(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, 10CFR2.390(d)(1) 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)

E2-2

I I.

ENCLOSURE 2 WBN Unit 2 FSAR AlII "Summary of Redacted Pages" Chapter Page(S)

Section No.

Figure No.

Basis For Redaction I

8 8.2-31 8.2 8.2-4 Security Related, 10CFR2.390(d)(1) 8 8.2-44 8.2 8.2-11 Security Related, 10CFR2.390(d)(1) 8 8.3-97 8.3 8.3-1 Security Related, 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, 10CFR2.390(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, 10CFR2.390(d)(1) 9 9.2-211 9.2 9.2-40 Security Related, 10CFR2.390(d)(1) 9 9.4-276 9.4 9.4-21 Security Related, 10CFR2.390(d)(1) 9 9.4-280 9.4 9.4-22c Security Related, 10CFR2.390(d)(1) 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, 10CFR2.390(d)(1) 12 12.3-39 12.3 12.3-1 Security Related, 10CFR2.390(d)(1) 12 12.3-40 12.3 12.3-2 Security Related, 10CFR2.390(d)(1) 12 12.3-41 12.3 12.3-3 Security Related, 10CFR2.390(d)(1) 12 12.3-42 12.3 12.3-4 Security Related, 10CFR2.390(d)(1) 12 12.3-43 12.3 12.3-5 Security Related, 10CFR2.390(d)(1) 12 12.3-44 12.3 12.3-6 Security Related, 10CFR2.390(d)(1) 12 12.3-45 12.3 12.3-7 Security Related, 10CFR2.390(d)(1) 12 12.3-46 12.3 12.3-8 Security Related, 10CFR2.390(d)(1) 12 12.3-47 12.3 12.3-9 Security Related, 10CFR2.390(d)(1) 12 12.3-48 12.3 12.3-10 Security Related, 10CFR2.390(d)(1) 12 12.3-49 12.3 12.3-11 Security Related, 10CFR2.390(d)(1) 12 12.3-50 12.3 12.3-12 Security Related, 10CFR2.390(d)(1) 12 12.3-51 12.3 12.3-13 Security Related, 10CFR2.390(d)(1) 12 12.3-52 12.3 12.3-14 Security Related, 10CFR2.390(d)(1) 12 12.3-53 12.3 12.3-15 Security Related, 10CFR2.390(d)(1) 12 12.3-54 12.3 12.3-16 Security Related, 10CFR2.390(d)(1) 12 12.3-55 12.3 12.3-17 Security Related, 10CFR2.390(d)(1) 12 12.4-7 12.4 12.4-1 Security Related, 10CFR2.390(d)(1)

E2-3

I I

ENCLOSURE 3 WBN Unit 2 FSAR AlII "List Of Files And File Sizes On The Security-Related OSM (OSM #1)"

E3-1

I" 'L a"

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 - List of Files on Security-Related OSM File Name File Size - Bytes TVAWBN-2_FSARFiles 001 TVA W B_FSAR TOC.pdf 361,949 002 TVA WB FSAR LRP.pdf 95,224 003 TVA WB FSARSection_ 1.pdf 4,635,785 004 TVA WB FSAR Section 2 A.pdf 19,882,901 005 TVA WB FSAR Section 2 B Part 1 of 3.pdf 18,601,305 005_TVA WB FSAR Section 2 B Part 2 of 3.pdf 41,436,625 005 TVA WB FSAR Section 2 B Part 3 of 3.pdf 47,978,359 006 TVA Wa FSAR Section 2 C.pdf 2,102,923 007 TVA WB FSAR Section 2 D. pdf 31,328,368 008_TVAWBFSARSection_2_E.pdf 47,314,766 009 TVA WB FSAR Section_3 A.pdf 2,713,688 010 TVA WB FSAR Section 3 B.pdf 7,958,134 011 TVA WB FSAR Section 3 C.pdf 30,016,659 012 TVA WB FSAR Section_3 D.pdf 11,759,618 013 TVA WB FSAR Section 4.pdf 25,727,044 014 TVA Wa FSARSection_5.pdf 9,879,350 015 TVA WB FSAR Section 6 A.pdf 25,764,452 016 TVA WB FSAR Section 6 B.pdf 10,443,203 017 TVA WB FSAR Section 7.pdf 14,431,337 018 TVA Wa FSAR Section_8.pdf 29,717,097 019 TVA WB FSAR Section 9 A.pdf 24,517,802 020 TVA WB FSAR Section 9 B.pdf 16,492,802 021 TVA WBaFSAR Section 10.pdf 14,145,753 022 TVA WB FSAR Section 11.pdf 3,977,570 023 TVA WB FSAR Section 12.pdf 5,990,994 024 TVA WB FSAR Sectionl 3.pdf 3,237,097 Page 1 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 - List of Files on Security-Related OSM File Name File Size - Bytes 025 TVA WB FSAR Section 14.pdf 1,169,799 026 TVA WB FSAR Section_15A.pdf 28,462,215 026 TVA WB FSAR Section 15B.pdf 36,336,771 027 TVA WB FSAR Section 16.pdf 157,676 028 TVA WB FSAR Section 17.pdf 156,608 Total 516,793,874 TVAWBN-2_Oversized_FSARFigures 001 TVA WBFSAR 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 FSARFigure 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 3,989,180 009 TVA WBFSAR Figure 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_TVAWBFSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB FSAR Figure 2.5 554_1.pdf 3,081,060 014 TVA WBFSAR 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_TVAWBFSAR Figure 2.5 571_1.pdf 844,484 018 TVAWB FSAR_Figure 2.5 571_2.pdf 3,128,329 019 TVA WBFSAR Figure 2.5 571 3.pdf 3,284,555 Page 2 of 3

I I

I ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 - List of Files on Security-Related OSM File Name File Size - Bytes 020_TVAWBFSAR Figure 2.5 571 4.pdf 2,142,316 021 TVA WB FSAR Figure 2.5 572.pdf 2,196,945 022_TVA WBFSAR Figure 2.5 573.pdf 2,013,286 023_TVAWBFSARFigure 2.5 576_1.pdf 3,238,525 024 TVA WBFSAR Figure 2.5 576 2.pdf 2,151,750 025_TVAWBFSARFigure 2.5 577.pdf 2,207,622 026 TVA WB FSAR Figure 2.5 578.pdf 2,080,032 0273TVAWBFSARFigure 2.5 579.pdf 2,308,985 0283TVA WBFSARFigure 2.5 583.pdf 2,487,346 029 TVA WBFSAR Figure 2.5 588.pdf 2,528,515 030 TVA WBFSAR Figure 2.5 589.pdf 2,480,438 0314TVA WB FSAR Figure 2.5 594.pdf 13,054,127 032_TVAWB BFSAR_Figure 2.5_595.pdf 2,323,267 033 TVAWBFSARFigure 2.5_596.pdf 5,732,107 034_TVAWBFSAR_Figure 2.5_597.pdf 1,287,336 035 TVAWBFSAR Figure 2.5 602.pdf 5,549,537 036 TVA WB FSARFigure 2.5 603.pdf 4,830,835 037 TVA WB FSARFigure 2.5_604.pdf 6,392,279 038 TVA_WB_FSARFigure 2.5 605.pdf 20,823,108 Total 131,112,035 TVAWBN-2_OversizedFSARTable 001 TVA WB FSAR Table 6.2.4-1.pdf 919,663 Total 919,663 Page 3 of 3

I 1

0 ENCLOSURE 4 WBN Unit 2 FSAR Al 11 "List Of Files And File Sizes On The Publicly Available OSM (OSM #2)"

E4-1

ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 List of Files on Publicly Available OSM File Name File Size - Bytes TVAWBN-2_FSARFiles 001 _TVA WB FSARTOC.pdf 361,949 002_TVA_WB_FSARLRP.pdf 95,224 003WTVA WB FSAR Section 1.pdf 829,202 004 TVA WB FSAR Section 2_A.pdf 19,546,361 005WTVA WB FSARSection 2 B Part 1 of_3.pdf 17,517,245 005WTVAWBFSARSection 2 B Part 2 of_3.pdf 32,273,255 005 TVA WB FSAR Section 2 B Part 3 of 3.pdf 41,720,248 006_TVA WB FSAR Section_2_C.pdf 2,102,923 007 TVA WB FSAR Section2 _D.pdf 31,328,368 008WTVA WB FSAR Section_2_E.pdf 45,935,352 009 TVA WB FSAR Section_3A.pdf 2,422,240 010 TVA WB FSAR Section3_B.pdf 6,556,369 011 TVA WB FSAR Section 3_C.pdf 25,184,132 012 TVA WB FSAR Section 3_D.pdf 11,490,944 013 TVA WB FSAR Section 4.pdf 25,727,004 014 TVA WB FSAR Section_5.pdf 9,879,350 015 TVA WB FSAR Section_6A.pdf 22,883,939 016 TVA WB FSAR Section 6_B.pdf 10,443,203 017 TVA WB_FSARSection_7.pdf 14,431,337 018 TVA WB FSAR Section 8.pdf 26,756,924 019 TVA_WB FSARSection_9_A.pdf 24,256,789 020 TVA WB FSAR Section 9_B.pdf 15,278,325 021 TVA WB FSAR Section 10.pdf 14,145,753 022 TVA WB_FSARSection_ 11.pdf 3,977,570 023WTVA WB FSAR Section 12.pdf 1,722,983 024 TVA WB FSAR Section 13.pdf 3,237,097 Note: Byte amounts in italics are redacted files.

Page 1 of 3

1 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 List of Files on Publicly Available OSM File Name File Size - Bytes 025 TVA WB FSAR Section 14.pdf 1,169,799 026 TVA WB FSAR Section 15A.pdf 28,462,215 026 TVA WB FSAR Section 15B.pdf 36,336,771 027 TVA WB FSAR Section 16.pdf 157,676 028 TVA WB FSAR Section 17.pdf 156,608 Total 476,387,155 TVA_WBN-2_Oversized_FSARFigures 001 TVA WB_FSAR Figure_2.5_3.pdf 1,757,743 002_TVAWBFSAR Figure 2.5 11.pdf 1,689,538 003_TVAWBFSAR Figure 2.5 71.pdf 2,263,087 004_TVAWBFSAR Figure 2.5 222.pdf 909,429 005_TVA WB FSAR Figure 2.5 281 1.pdf 2,155,627 006_TVAWBFSAR Figure 2.5 281 2.pdf 2,117,562 007_TVA WB FSARFigure 2.5_549_1.pdf 3,600,807 008_TVA WB FSAR Figure 2.5 549 2.pdf 3,989,180 009_TVA WBFSARFigure 2.5 549 3.pdf 2,863,719 010_TVA WB FSARFigure 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_TVAWBFSAR Figure 2.5 554 1.pdf 3,081,060 014_TVAWBFSAR 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_TVAWBFSAR 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 Note: Byte amounts in italics are redacted files.

Page 2 of 3

1ý 4 07 ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 111 List of Files on Publicly Available OSM File Name File Size - Bytes 020_TVAWBFSARFigure 2.5 571 4.pdf 2,142,316 021_TVAWBFSAR Figure 2.5 572.pdf 2,196,945 022_TVA WB FSAR Figure 2.5 573.pdf 2,013,286 023_TVA WBFSARFigure 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 WBFSAR 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_TVAWBFSAR Figure 2.5 597.pdf 1,287,336 035_TVA WB FSAR Figure 2.5 602.pdf 5,549,537 036 TVA WBFSARFigure 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 TVAWBN-2_OversizedFSARTable 001 TVA WB FSAR Table 6.2.4-1.pdf 919,663 Totall 919,663 Note: Byte amounts in italics are redacted files.

Page 3 of 3

ENCLOSUREI WBN Unit 2 FSAR A 111 "Summary Listing of Alll FSAR Changes" Item Change Change NoI Area Change Description Package Number

.Table On FSAR Table 3.9-17, Sheet 1 of 9, change valve actuation and

1.

3.9-17 type for valve FCV-62-77 from "Motor" and "Gate" to "Air" and 2-111-01 "Globe" respectively.

1.

In FSAR Section 7.7.1.8, on Page 7.7-18 (A110), in the next to last paragraph perform the following:

a. Delete "an" in the first line.
b. Replace "sensing circuit" with "logic" in the second line of paragraph.
c. Replace "This circuit senses" with "The DCS calculates" in the second sentence.
2.

In FSAR Section 7.7.1.8.1, on Page 7.7-18 (Al10), replace "controller" with "logic within the DCS," in the first sentence of the first paragraph.

3.

In the title of Section 7.7.1.8.2 on Page 7.7-18 (Al 10), replace "Plant" with "Reactor."

2.

Section

4. In Section 7.7.1.8.2, on Page 7.7-18 (Al10), perform the 2-111-02

7.7 following

a.

Replace "plant" with "reactor" in two places within the first sentence of the first paragraph.

b.

At the end of the first sentence of the first paragraph, add the sentence, "(The Reactor Trip controller is sometimes referred to as the "Plant Trip" controller).

5.

In Section 7.7.1.8.2, on Page 7.7-19 (Al10), replace "plant" with "reactor" in the first and second paragraphs at the top of the page.

6.

In Section 7.7.2.6, on Page 7.7-29 (Al10), replace "plant" with "reactor" in the first sentence of the second paragraph.

7.

For Figure 7.7-8 on Page 7.7-40, replace "Plant" with "Reactor" in four places.

El-i

ENCLOSUREI WBN Unit 2 FSAR Alll "Summary Listing of AII1 FSAR Changes" Change Item Change Change Description Package No, Area Number

1.

In Section 14.2.2, Page 14.2-3, change the following title from "TVA Senior Vice President, Nuclear Construction (NC)" to Senior Vice President, Watts Bar Operations and Section Construction."

14.22-111-03 14.2

2. In section 14.2.2.5.1, Page 14.2-8, combine "Unit 1 Operations and Unit 2 Operations" into a single "Operations" representative.
4.

Section In FSAR Section 15.5.5, Page 15.5-22 (Al 10), delete the phrase 2-111-04 15.5 "Reference 38 in" Section 15.4" 5.

Sections 2.1 3.8 6.3 9.2 15.2 15.4

1.

On Page 2.1-2, capitalize "River" in the last line of the first paragraph of Section 2.1.2.3.

2.

On Page 3.8.4-12, correct typo by replacing "anks" with "tanks" in the first sentence of the second paragraph.

3.

On Page 3.12-1 (Al 10), correct typo by replacing "Licecing" with "Licensing" in the heading for Section 3.12.1.

4.

On Page 6.3.9 (Al 10), in the third paragraph change "RHRI" to "RHR"

5.

On Page 9.2-124 (Al 10), change "CCS" to "CSS" in Item No.

2 of Note 2.

6.

On Page 15.2-10 (Al 10), change "paralled" to "parallel" in the second sentence of the second paragraph.

7.

On Page 15.2-32 (Al 10), change "that" to "than" in the third line of Item l(a).

8.

On Page 15.2-35 (A110), change "in" to "is" in the third sentence of the fourth full paragraph.

9.

On Page 15.2-37 (Al10), replace period with comma between the word, "temperatures" and the word, "and" in Item No. 1 at the top of the page.

10. On Page 15.4-40 (Al 10), replace "or" with "for": in the last sentence of the second paragraph.
11. On Page 15.2-41, (Al 10), replace "shutdown" with "standby" in the third sentence of Item (1) Case A.

2-111-05 El-2

ENCLOSURE1 WBN Unit 2 FSAR AllI "Summary Listing of All 1 FSAR Changes" Change Item Change Change Description Package No.

Area Number The following specific changes are to be made to the FSAR

1. Revise FSAR Sections 6.2.3.1.1 and 6.2.3.1.3 to remove the FHA as a design basis for the Secondary Containment and ABGTS as follows:
a. On Page 6.2.3-1 (Al 10), in the first sentence of the first paragraph of Section 6.2.3.1.1, delete the phrase, "or a fuel handling accident (FHA)," at the end of the sentence.
b. On Page 6.2.3-2 (A110), in Item 3 of Section 6.2.3.1.3, add a second sentence after the first sentence as follows:

"ABGTS is not required to mitigate the consequences of a fuel handling accident."

2. On Page 6.2.3-5 (Al 10), revise FSAR Section 6.2.3.2.1 by deleting the following from Item No. 3,"Auxiliary Building Secondary Containment Enclosure (ABSCE):
a. "During fuel handling operations in this configuration, a high Sections radiation signal from spent fuel pool radiation monitors will 6.2.3 result in a Containment Ventilation Isolation (CVI) in addition
6.

6.2.4 to an Auxiliary Building isolation and ABGTS start. Similarly, 2-111-06 6.5 a CVI signal, including a CVI signal generated by a high 9.4 radiation signal from the containment purge air exhaust 15.5 radiation monitors, will initiate an Auxiliary Building isolation and start of ABGTS. Likewise, a"

b. Capitalize "A" for the start of the next sentence.
c. Later in the same paragraph at the top of Page 6.2.3-6, insert the following after the sentence that ends with while the purge air ventilation system is operating":

"During fuel handling operations in this configuration, a high radiation signal from spent fuel pool radiation monitors will result in a Containment Ventilation Isolation (CVI) in addition to an Auxiliary Building isolation and ABGTS start. Similarly, a CVI signal, including a CVI signal generated by a high radiation signal from the containment purge air exhaust radiation monitors, will initiate an Auxiliary Building isolation and start of ABGTS. These are not required functions for the ABGTS and the Reactor Building Purge System filters or for Purge System isolation as no credit for these features is in mitigating a fuel handling accident."

El-3

ENCLOSURE1 WBN Unit 2 FSAR AII1 "Summary Listing of AlII FSAR Changes" Change Item Change Change Description Package No.

Area Number

d. Later in the same paragraph at the top of Page 6.2.3-6, delete the following sentence:

"Under special administrative controls, one of the airlock doors at each location will be closed and the purge air ventilation systems will be shutdown and isolated in a timely manner subsequent to a fuel handling accident to ensure ABSCE boundary integrity."

3. In Section 6.2.3.3.3, on Page 6.2.3-21 (Al10), delete the phrase, ", or a high radiation signal (See Section 6.2.3.2.3)"

from Item No 3.

4. In Section 6.2.3.3.3, on Page 6.2.3-21 (Al 10), delete the phrases, "or a high radiation," and ", except for the fuel Sections handling area exhaust dampers which must close within 9.3 6.2.3 seconds" from Item No. 8.
6.

6.2.4

5. On Page 6.2.4-14 (A110), in FSAR Section 6.2.4.3 delete the 2-111-06 (cont.)

6.5 sentence from Item (e) that reads: "Administrative controls will 9.4 15.4 ensure timely closure of the valves subsequent to a fuel 15.5 handling accident."

6. On Pages 6.5-1 (Al 10) and 6.5-2 (Al 10), delete Section 6.5.1.1.3 and renumber 6.5.1.1.4 as 6.5.1.1.3.
7. On Page 6.5-4 (A110), delete Section 6.5.1.2.3 and renumber 6.5.1.2.4 as 6.5.1.2.3.
8. On Pages 6.5-19 (A110) and 6.5-20 (A110), delete contents of Table 6.5-3 and insert, "Table 6.5-3, Deleted in Amendment 111."
9. On Page 9.4-11 (Al 10), insert a new sentence in the first paragraph of Section 9.4.2.3 between the sentence ending with "9.4-10" and the sentence beginning with "To accomplish..."

that reads as follows: "No credit is taken in the dose or accident analyses for these functions."

E1-4

ENCLOSUREI WBN Unit 2 FSAR AI1I "Summary Listing of A111 FSAR Changes" Item Change Change No.

Area Change Description Package Number

10. On Page 9.4-11 (Al 10), modify the last sentence in the first paragraph of Section 9.4.2.3, from "To accomplish its safety function following a fuel handling accident, the fuel handling area ventilation system must accomplish the following functions:" to "The fuel handling area ventilation system will accomplish the following functions:"
11. On Page 9.4-37 (Al 10), in the third paragraph of Section 9.4.6.1, delete the following sentence that reads: "However, the filtration units are required to provide a safety-related filtration path following a fuel handling accident until all containment isolation valves are closed."
12. On Page 9.4-37 (Al10), in Section 9.4.6.1, insert a new paragraph between the third and fourth paragraphs that reads as follows: "In the case of a fuel handling accident the Sections filtration units provide a filtration path following a fuel handling 6.2.3 accident until all containment isolation valves are closed.
6.

6.2.4 However, neither the filtration nor the isolation functions are 2-111-06 (cont.)

6.5 credited in the Fuel Handling Dose Analysis. Thus, they are 9.4 not safety functions for this accident."

15.5

13. On Page 9.4-37 (Al 10), in the existing fourth paragraph (prior to the Item 12 change) of Section 9.4.6.1, delete the phrase, "during Mode 6 or" from the next to last line of the paragraph.
14. On Page 9.4-37 (Al 10), in the existing fourth paragraph (prior to the Item 12 change) of Section 9.4.6.1, delete the last sentence of the paragraph that reads: "This system is not required for fuel handling accident mitigation and is not available for that purpose since it is essentially isolated by containment isolation valves during fuel loading or handling activities (Mode 6)."
15. On Page 9.4-38 (Al 10), in the second paragraph of Section 9.4.6.1, delete the last sentence that reads: "However, the filtration units are required to provide a safety-related filtration path following a fuel handling accident."

El-5

ENCLOSURE1 WBN Unit 2 FSAR AlII "Summary Listing of AllI FSAR Changes" Change Item Change Change Description Package No.

Area Number

16. In Section 9.4.6.1, on Page 9.4-39 (All0), delete the fourth full paragraph that reads: "The RBPVS air cleanup equipment assures that activity released inside containment from a refueling accident and prior to containment isolation, is processed through both HEPA filters and carbon adsorbers before release to the atmosphere. Fuel handling operations inside the primary containment are constrained by the operability requirement for the RBPVS air cleanup units contained in the plant technical specifications."
17. In Section 9.4.6.2, on Page 9.4-41 (Al 10), modify the first and second sentences of the third full paragraph from "The purge function of the RBPVS is not a safety-related function.

However, the filtration units are required to provide a safety-related filtration path following a fuel handling accident," to "The purge function of the RBPVS is not a safety-related Sections function and the filtration units are not required to provide a 6.2.3 safety-related filtration path following a fuel handling

6.

6.2.4 accident."

2-111-06 (cont.)

6.5

18. In Section 9.4.6.3, on Page 9.4-41 (Al 10), in the first 9.4 paragraph, delete the sentence that reads: "The purge air 15.5 filtration units and associated exhaust ductwork provide a safety-related filtration path following a fuel-handling accident."
19. In Section 9.4.6.3, on Page 9.4-42 (All0), in the partial paragraph at the top of the page, delete the sentence that reads: "In addition, the containment ventilation system is not allowed to be used during Mode 6."
20. In Section 9.4.6.3, on Page 9.4-42 (Al 10), insert the word "isolation" between the words, "accident" and "mode" into the sentence of Item No. 3.
21. In Section 9.4.6.3, on Page 9.4-42 (Al 10), delete the sentence below Item No. 5 that reads: "Containment vent system is not allowed to be used during Mode 6."

El-6

ENCLOSURE1 WBN Unit 2 FSAR Al 11 "Summary Listing of All 1 FSAR Changes" Item hangeChange Item Change Change Description Package No.

Area INumber

22. In Section 15.5.6, on Pages 15.5-22 (All0) and 15.5-23 (Al 10), modify the first paragraph of this section from "The analysis of the fuel handling accident considers three cases. The first case is for a Fuel Handling Accident inside containment with the containment closed and the Reactor Building Purge System operating. This analysis is discussed in Section 15.5.6.1 and is based on Regulatory Guide 1.25[1 1] and NUREG 5009[24]. The second case is for an accident in the spent fuel pool area located in the Auxiliary Building. This case is discussed in Section 15.5.6.2 and is evaluated using the Alternate Source Term based on Regulatory Guide 1.183[18], "Alternate Source Terms." The third case considered is an open containment case for an accident inside containment where there is open Sections communication between the containment and the Auxiliary 6.2.3 Building. This evaluation is discussed in Section 15.5.6.2 and
6.

6.2.4 is based on Regulatory Guide 1.183."

2-111-06 (cont.)

6.5 9.4 to 15.5 "The analysis of the fuel handling accident considers two cases. The first case is for an accident in the spent fuel pool area located in the Auxiliary Building. This case is evaluated using the Alternate Source Term (AST) based on Regulatory Guide 1.183[18], "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." The second case considered is an open containment case for an accident inside containment where there is open communication between the containment and the Auxiliary Building. This evaluation is also based on the AST and Regulatory Guide 1.183. An FHA could occur with the containment closed and the reactor building purge operating. This scenario is bounded by Case 2. The parameters used for this analysis are listed in Table 15.5-20.a.

El-7

ENCLOSURE1 WBN Unit 2 FSAR AlII "Summary Listing of A111 FSAR Changes" Item Change

~Change N.

Aeane Change Description Package No.

Area Number

23. In Section 15.5.6, on Pages 15.5-23 (Al10) and 15.5-24 (A110), delete Section 15.5.6.1.
24. In Section 15.5.6, on Page 15.5-24 (All0), delete heading and first paragraph of Section 15.5.6.2. The remaining portions of 15.5.6.2 becomes part of Section 15.5.6.
25. In existing Section 15.5.6.2, modify the phrase prior to the list from "The bases for evaluations are:" to read as follows:

"The bases for evaluations consistent with Regulatory Guide 1.183 are:"

26. On page 15.5-24 (Al 10), delete the phrase, "In the Regulatory Guide 1.183 analysis," in Items 1, 2, 4, 6, 7, and 8, and capitalize the first letter of the first word to begin the sentence.

Sections 6.2.3

27. On Page 15.5-24 (Al 10), insert a new Item 9 which reads:
6.

6.2.4 "The release path for the containment scenario is changed to 2-111-06 (cont.)

6.5 include 12.7 seconds of unfiltered release through the Shield 9.4 Building vent, with the remainder of the unfiltered release 15.5 through the Auxiliary Building vent."

28. On Page 15.5-24 (All0), renumber the remaining items of list based on the insertion of a new No. 9 in Item 26 above.
29. On Page 15.5.25 (Al 10), delete the section no "15.5.6.3" but leave the heading, "Fuel Handling Accident Results."
30. On Page 15.5-25 (Al 10), delete the first four paragraphs of 15.5.6.3. (Please note that the remaining portions become part of Section 15.5.6.)
31. On Page 15.5-25 (Al 10), delete the last paragraph at the bottom of page.
32. On Page 15.5-26 (Al 10), delete the bullets at the top of page.

El-8

ENCLOSURE1 WBN Unit 2 FSAR AlII "Summary Listing of A111 FSAR Changes" Item Change Change Not Area Change Description Package Number

33. On Page 15.5-26 (Al 10), in the first paragraph below the former bulletized items (deleted by Item 32), delete the remaining verbiage of the paragraph starting with the sentence as follows: "In addition, any release from the shield building stack would go through the purge system HEPA and Charcoal filter assemblies prior to release. Currently, when the purge lines isolate on high radiation, the auxiliary building also isolates and ABGTS is actuated. The release point for ABGTS is the shield building stacks and the releases are filtered through HEPA and Charcoal assemblies. Thus, AST analysis for the FHA in the Auxiliary Building that considers no filtration is conservative and acceptable as the basis for the containment evaluation."

Sections 6.2.3

34. On Page 15.5-26 (Al 10), delete the next to last paragraph
6.

6.2.4 prior to heading "15.5.7 Environmental Consequences of a 2-111-06 (cont.)

6.5 Postulated Rod Ejection Accident."

9.4 15.5

35. On Page 15.5-26 (Al 10), replace the phrase, "For the RG 1.183 cases, the" with "The".
36. On Page 15.5-50 (Al 10), delete contents of Table 15.5-20 and insert, "Table 15.5-20, Deleted in Amendment 111."
37. On Page 15.5-54 (Al10), for Table 15.5-20, delete asterisk after "(rem)" and note below the top table and for the bottom table, replace heading "Doses from Fuel Handling Accident Regulatory Guide 1.25 Analyses" and current values with new heading "Doses from Fuel Handling Accident Regulatory Guide 1.183 Analyses" and insert new values for TEDE.

E1-9

ENCLOSURE1 WBN Unit 2 FSAR Al 11 "Summary Listing of Al11 FSAR Changes" Change Item Change Change Description Package No AreaNumber For Section 14.2.2.6.1, on Page 14.2-8, Delete "Quality Assurance" off the list of Test Review Group (TRG).

Insert a new sentence below the TRG list between the

7.

Section sentence that ends with "systems and components," and 2-111-07 14.2 the sentence that begins "TRG members," that reads as follows:

"Site Quality Assurance will conduct activities in accordance with Chapter 17 of the FSAR."

1. In exception (e) of FSAR Section 6.2.4.3, delete the words

"(Mode 7)" from the first sentence.

2. In exception (e) of FSAR Section 6.2.4.3, delete the fifth sentence that indicates the configuration is being installed to permit ice blowing operations to occur concurrently with fuel Section handling activities inside containment.
8.

2-111-08 6.2.4

3. In exception (e) of FSAR Section 6.2.4.3, revise the sixth sentence of exception (e), to indicate that administrative controls will ensure timely closure of the valves, if necessary, subsequent to a LOCA in the other unit.

Please note that Item Nos. 2 and 3 reinstates and modifies a sentence deleted by Item No. 5 of Change Package 2-111-06.

El-10

4 ENCLOSURE I WBN Unit 2 FSAR Alll "Summary Listing of AllI FSAR Changes" Item Change Change NoI Area Change Description Package Number In FSAR Section 15.2.14.1 on Page 15.2-41 (All0), revise the 9

Section third sentence Case A to indicate that for a spurious safety

9.

15.2 injection occurrence, an operator will stop the safety injection 2-111-09 and maintain the plant in a "hot standby" condition rather than "hot shutdown."

For Table 14.2-2, make the following changes,

1. On Sheet 1 of 39 on Page 14.2-127 (Al10), replace the "&"

between the words "Measurement" and "Stationary" with the word, "and."

2. On Sheet 5 of 39 on Page 14.2-131 (Al 10), replace the phrase "30%, 50%, 75%, 100% power," with "the 30%, 50%,

75%, and 100% power test plateaus."

3. On Sheet 8 of 39 on Page 14.2-134 (Al10), shift the word, "OBJECTIVE," to the left hand margin and add bolding and underlining to make subheading.
4. On Sheet 14 of 39 on Page 14.2-140 (Al 10), in the second sentence under the test method heading, replace the Table phrase, "At ascending power levels of," with "At the
10.

14.2-2 ascending power test plateaus of..."

2-111-10

5. On Sheet 16 of 39 on Page 14.2-142 (Al 10), perform the following changes:

a)

In the second sentence under the test method heading, replace the phrase, "At ascending power levels" with "At the ascending power test plateaus..."

b)

In the next to last sentence under the test method heading, replace the phrase "90% and 100% power" with the phrase, "the 90% and 100% power test plateaus,"

c)

In the last sentence under the test method heading, replace the phrase, "100% power," with the phrase, "the 100% power test plateau,"

El-11

ENCLOSUREI WBN Unit 2 FSAR Al 11 "Summary Listing of All 1 FSAR Changes" Change Item Change Change Description Package No._

Area Number

6. On Sheet 20 of 39, on Page 14.2-146, (A110), perform the following changes:

a) In the third sentence under the test method heading, replace the phrase, "30% and 50% power levels," with the phrase, "then again during "30% and 50% power test plateaus."

b) In the fourth sentence, delete the word, "chamber" so that the phrase reads, "turbine impulse pressure."

c) In the fifth sentence, replace the phrase "75% power,"

with "the 75% power test plateau,"

7. On Sheet 21 of 39, in the first sentence under the test method heading on Page 14.2-147 (Al 10), replace the
10.

Table phrase, "of 30%, 50%, 75%, and 100%" with "during the (Cont.)

14.2-2 30%, 50%, 75% and 100% power test plateaus."

8. On Sheet 26 of 39 on Page 14.2-152 (All0), add "Test Summary," to the title and remove extra space in the last sentence under the Test Method heading.
9. On Sheet 29 of 39 on Page 14.2-155 (Al 10), perform the following changes:

a) In the second sentence of Item number 2 of the Acceptance Criteria, replace the word, "Application," with "Selected application,"

b) In the third sentence of Item number 2, replace the phrase, "100% power," with the phrase, "the 100%

power test plateau," and delete the phrase, "based on precision instrumentation."

E1-12

ENCLOSURE1 WBN Unit 2 FSAR Al 1I "Summary Listing of AlII FSAR Changes" Item Change Change No.

Area Change Description Package Number

10. On Sheet 30 of 39, on Page 14.2-156 (Al 10), insert the phrase, "power test plateaus" after "100%" in the last sentence under Test Method heading.
11. On Sheet 37 of 39, on Page 14.2-163 (Al 10), replace the
10.

Table phrase, "100% power" with "the 100% power test plateau" in (Cont.)

14.2-2 the last sentence under Test Method heading.

2-111-10

12. On Sheet 38 of 39, on Page 14.2-164 (Al 10), replace the phrase, "0%, 30%, 50%, 75%, 100% power" with the phrase, "the initial criticality and low power ( <5%) physics testing, 30%, 50%, 75%, and 100% power test plateaus" in the first sentence under the Test Method heading.

For Table 14.2-2, make the following changes:

1. On Sheet 34 of 39, on Page 14.2-160 (Al10), under the Test Method heading, replace the sentence that reads:

"Recorders are connected to monitor plant parameters (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, Table feedwater pump speed, and feedwater pressure) during the 11.14.2-2 transient."

2-111-11 with the following sentence:

"Applicable plant parameter data will be obtained (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, feedwater pump speed, feedwater pressure, generator breaker position, and turbine speed) during the transient."

El-13

ENCLOSUREI WBN Unit 2 FSAR AlII "Summary Listing of Al 11 FSAR Changes" Item Change Change Noe Area Change Description Package Number

2. On Sheet 35 of 39, on Page 14.2-161 (A110), under the Test Method heading, replace the sentence that reads:

"Recorders are connected to monitor plant parameters (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, feedwater pump speed, and feedwater pressure) during the transient."

with the following sentence:

"Applicable plant parameter data will be obtained (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, feedwater pump speed, feedwater pressure, generator Table breaker position, and turbine speed ) during the transient."

11.

2-111-11 14.2-2

3. On Sheet 36 of 39, on Page 14.2-162 (Al 10), under the Test Method heading, replace the sentence that reads:

"Recorders are connected to monitor plant parameters (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, feedwater pump speed, feedwater pressure, generator breaker position, and turbine speed) during the transient."

with the following sentence:

"Applicable plant parameter data will be obtained (e.g.,

reactor power, RCS temperature and pressure, pressurizer level, feedwater and steam flows, steam generator levels, feedwater pump speed, feedwater pressure, generator breaker position, and turbine speed ) during the transient."

El-14

ENCLOSUREI WBN Unit 2 FSAR Al 11 "Summary Listing of AlII FSAR Changes" Change Item Change Change Description Package No.

Area Number

1. In the first sentence of the third paragraph of FSAR Section 1.1.1, change the NSSS power level from 3,425 MWt to 3,427 MWt.
2. In the first sentence of the fourth paragraph of FSAR Section 1.2.2.2, change the NSSS power level from 3,425 MWt to 3,427 MWt.
3. In the second sentence of the fourth paragraph of FSAR Section 1.2.2.2, change the peak power from 13.1 kW/ft to Secio 13.6 kW/ft.

1.1.1 1.2.2.2

4. On FSAR Table 4.1-1, page 1 of 3, change the reactor core 2-111-12
12.

Tables heat output for Watts Bar from 11,641.7 106 BTU/hr to 11,639 4.1-1 106 BTU/hr.

4.4-1 15.1-1

5. On FSAR Table 4.4-1, page 1 of 2, change the reactor core heat output for Watts Bar from 11,641.7 106 BTU/hr to 11,639 106 BTU/hr.
6. On FSAR Table 15.1-1, change the guaranteed nuclear steam supply system thermal power output from 3,425 MWt to 3,427 MWt.
7. On FSAR Table 15.1-1, change the thermal power generated by the reactor coolant pumps from 14 MWt to 16 MWt.

For Table 14.2-2, make the following changes

1.

For Sheet 4 of 39 (Page 14.2-130), delete the last sentence of Test Method, that reads, "Finally, a periodic sampling and lineup verification is performed during core loading to preclude having an inadvertent boron dilution event."

2.

For Sheet 10 of 39 (Page 14.2-136), delete the last part of the last sentence of the Test Method, that reads, "...without

13.

Table unduly increasing the count rate on any source channel 2-111-13 14.2-2 above the established baseline rate."

3.

For Sheet 22 of 39 (Page 14.2-148),

a. Replace "20%" with "25%" in Item No. 2 of the Prerequisites.
b. Replace the word, "by" with the word, "to" in the fifth line of Test Method.

El-15

ENCLOSURE1 WBN Unit 2 FSAR Al 11 "Summary Listing of Al II FSAR Changes" Item Change Change No.

Area Change Description Package Number

1.

On FSAR Table 14.2-1, Sheet 23 of 89, Page 14.2-60 (Al 10), delete Item No. 2 under the "Test Method" for the "Accumulators" regarding the requirement to verify the ability of the accumulator isolation valves to open automatically on a safety injection signal against a

.Table differential pressure equal to the accumulator at maximum

14.

14.2-1 operating pressure and the RCS depressurized and 2-111-14 renumber Items 3 through 5.

2.

On FSAR Table 14.2-1, Sheet 24 of 89, Page 14.2-61 (Al 10), delete Item No. 6 under the "Acceptance Criteria" related to the opening of the accumulator discharge isolation valves under maximum differential conditions.

15.

Section 2.4

1.

On Page 2.4-18 (Al 10), replace the PMF elevation in the first sentence of Section 2.4.3.5 from "738.8" with "739.2."

2.

On Page 2.4-19 (Al 10), delete the word, "critical" from the phrase, "critical west face of the Intake Pumping Station" in the next to the last sentence of the second paragraph.

3.

On Page 2.4-20 (Al 10), delete the word, "critical" from the phrase, "for the critical west face" in the fourth sentence of the second paragraph.

4.

On Page 2.4-20 (Al 10), delete the word, "critical" from the phrase, "The runup on the critical west wall," in the fourth sentence of the third paragraph.

5.

On Page 2.4-20 (Al 10), replace value "741.7" with "741.4" in the fifth sentence of the fourth paragraph.

6.

On Page 2.4-20 (Al 10), insert the phrase, "and the runup on the critical south face wall is 2.4 ft and reaches elevation 741.7 ft," after the Item No. 5 elevation change above.

7.

On Page 2.4-20 (Al 10), replace the phrase, "south and east faces allow," with "east face allows" in the seventh sentence of the fourth paragraph.

8.

On Page 2.4-20 (Al 10), delete ", south," from the eighth sentence of the fourth paragraph.

9.

Figure 2.4-11 (Sheet 2 of 13) - Discharge Rating Curve, Watts Bar Dam 2-111-15 El-16

ENCLOSURE1 WBN Unit 2 FSAR A 111 "Summary Listing of Al II FSAR Changes" Item Change Change No.

Area Change Description Package Number 15 (Cont.)

Section 2.4

10.

Figure 2.4-11 (Sheet 3 of 13) - Discharge Rating Curve, Ft Loudoun Dam

11.

Figure 2.4-11 (Sheet 4 of 13) - Discharge Rating Curve, Tellico Dam

12.

Figure 2.4 PMF Discharge Hydrograph at Watts Bar Nuclear Plant

13.

Figure 2.4 PMF Elevation Hydrograph at Watts Bar Nuclear Plant

14.

Figure 2.4-40g - Sheet 2, Yard Grading, Drainage, and Surfacing

15.

Figure 2.4 Delete and replace with the words, "Figure 2.4-64 is not used"

16.

Figure 2.4-106 - Mechanical - Flow Diagram Fuel Pool Cooling and Cleaning System

17.

Figure 2.4-107 - Powerhouse Units 1 & 2 Flow Diagram -

Residual Heat Removal System

18.

Figure 2.4-115 - OBE Failure of Norris and Tellico Dams with 1/2 PMF Event Failure Wave at Watts Bar Nuclear Plant

19.

For Figure 3.7-11, revise the Possible Maximum Flood (PMF) value from "737.5" to "739.2" and add the word,

"(Still)" to the caption after flood but before the value.

2-111-15 In FSAR Section 15.2.8.2 on Page 15.2-29 (All0), replace Assumption 9 at the top of the page with the following:

"For the LONF and LOOP events, an initial pressurizer pressure Section of 2320 psia and an initial average RCS temperature of 582.20F

16.

15.2 were assumed. LONF and LOOP cases run with both positive 2-111-16 and negative initial average RCS temperature uncertainty (+/-60F) and pressurizer pressure uncertainty (-50/+70 psi) have indicated that the case with a negative temperature uncertainty and positive pressurizer pressure uncertainty is conservative in terms of maximum pressurizer water volume."

E1-17

a ENCLOSURE I WBN Unit 2 FSAR AlII "Summary Listing of All 1 FSAR Changes" Change Item Change Change Description Package No.

Area Number

1.

In FSAR Table 15.5-14 on Page 15.5-44 (All10), change the isolation Time under "General Control Room Parameters" from 40 seconds to 74 seconds.

Tables

17.

15.5-14

2.

In FSAR Table 15.5-19 on Page 15.5-49, (Al10), revise 2-111-17 15.5-19 the gamma, beta and thyroid doses for the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> EAB, 30 Day LPZ and the Control Room for both the Pre-Accident Initiated Spike Case and the Accident Initiated Iodine Spike Case.

In FSAR Table 15.5-2 on Page 15.5-30 (Al 10), revise the

18.

Table gamma, beta and thyroid doses for the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> EAB, 30 Day 2-111-18 15.5-2 LPZ, and the Control Room for both the Conservative Analysis and the Realistic Analysis.

In FSAR Table 15.5-17 on Page 15.5-47 (Al 10), revise the

19.

Table gamma, beta and thyroid doses for the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> EAB, 30 Day 2-111-19 15.5-17 LPZ, and the Control Room for both the Pre-Accident Initiated Spike Case and the Accident Initiated Spike Case.

Table In FSAR Table 15.5-5 on Page 15.5-33 (A110), revise the

20.

15.5-5 gamma, beta and thyroid doses for the Control Room for both 2-111-20 the Regulatory Guide 1.24 Analysis and the Realistic Analysis.

In FSAR Section 7.7.1.12 on Page 7.7-23 (A110), change the

21.

7.7 word "impulse" to "inlet" in the fourth sentence of the second 2-111-21 paragraph.

Replace Table 3.2-7 in its entirety with an updated version

22.

Table based on Table 3.1-8 from Design Criteria WB-DC-40-36, "The 2-111-22 3.2-7 Classification of Piping, Pumps, Valves, and Vessels -(Unit 1 /

Unit 2)"

On Page 17.2-1 (Al 10), insert the following sentence at the end of the first paragraph of Section 17.2-1:

23.

Section 17.2 "The term Q-List refers to a report available in the Master Equipment List (MEL) that indicates component safety classifications."

1. On Page 4.3-41 (Al 10), move "Addendum 1, May 1996 and Addendum 2, March 2001" to after the word, "(Proprietary)"

in Reference No. 11. In addition, insert, "; Addendum 4-A, Sections September 2012," to after the Addendum 1 and Addendum 2 Sections that were moved above.

4.3 2-111-24

24.
2. On Page 7.7-31 (Al 10), insert ", Addendum 4-A, September 15.3 2012," to after "April 2002" in Reference 18.
3. On Page 15.3-14 (Al 10), insert ", Addendum 4-A, September 2012," to after "April 2002" in Reference 17.

El-18

I I I ENCLOSURE I WBN Unit 2 FSAR AlII "Summary Listing of A111 FSAR Changes" Change Item No.

Change Area Change Description Package Number

1.

On the List of Tables for FSAR Section 6, add Table 6.3-12.

2.

On the List of Tables for FSAR Section 9, change the title for Table 9.2-3 to identify the table as "Deleted by Amendment 111."

3.

In FSAR Section 6.2.2.2, revise the last sentence of the paragraph under the subsection entitled "Net Positive Suction Head (NPSH)" to indicate no credit is taken for the height of water above the RHR Strainer Assembly.

Also add a sentence to the end of the paragraph to refer to Table 6.3-12 for available NPSH parameters.

25 Table 6.3-12 Table 9.2-3 Sections 6.2.2.2 6.3.2.14 9.2.7.1 4.

In FSAR Section 6.3.2.14, revise 'the first paragraph by inserting a sentence referring to Table 6.3-12 for a complete listing of available NPSH for ECCS pumps.

2-111-25

5.

In FSAR Section 6.3.2.14, revise third sentence of Item (1) to indicate no credit is taken for water level above the RHR sump strainer assembly.

6.

In FSAR Section 6.3.2.14, revise the last sentence of Item (2) to refer to Table 6.3-12 instead of 9.2-3.

7.

Add new FSAR Table 6.3-12.

8.

in FSAR Section 9.2.7.1, change the references to Table 9.2-3 which is being deleted to new Table 6.3-12, in two locations,

9.

In FSAR Section 9.2.7.1, change the word "screens," in three locations, to "strainer assemblies."

El-19

ENCLOSURE1 WBN Unit 2 FSAR AlII "Summary Listing of Al 11 FSAR Changes" Change Item No.

Change Area Change Description Package Number

10. In FSAR Section 9.2.7.1, revise assumption 4 regarding Table 6.3-12 sump level.

Table 9.2-3

11. In FSAR Section 9.2.7.1, delete the note regarding the
25.

Sections minimum sump level and the total head loss through the 2-111-25 (Cont.)

6.2.2.2 6.3.2.14strainer.

6.3.2.14 9.2.7.1

12. Replace FSAR Table 9.2-3 with page that indicates the table has been moved to Table 6.3-12.

In FSAR Section 15.2.7.2 on Page 15.2-25 (Al 10), insert the following into Assumption (1)(b) between the first and second sentences as shown below:

"It should be noted that additional sensitivity studies have been performed that show that a slight reduction in the initial RCS average temperature, to a value consistent with the steady state full power RCS average temperature without allowances for calibration and instrument uncertainties, can result in approximately a 3 psi decrease in the margin to the Section RCS pressure safety analysis limit. The decrease in margin is

26.

15.2 due to a change in the time at which the main steam safety 2-111-26 valves open, which is caused by a slightly lower initial steam generator pressure due to the lower RCS average temperature. The current analysis demonstrates that there is 96.8 psi of margin to the safety analysis limit, thus a decrease of 3 psi would not challenge the analysis limit nor invalidate the conclusions presented herein with respect to the Loss of Load/Turbine Trip event. Additionally, the penalty does not significantly impact the governing characteristics of the pressure transient; as such, Figures 15.2-23, 15.2-24, 15.2-25, and 15.2-26 continue to represent the characteristics of the transient."

1. In FSAR Section 6.2.3.2.2 on Page 6.2.3-7 (Al 10), under the subsection entitled "Annulus Vacuum Control Subsystem," delete the last sentence of the second paragraph regarding the Unit 2 annulus control subsystem Section being isolated.
27.

2-111-27 6.2.3.2.2

2. In FSAR Section 6.2.3.2.2 on Page 6.2.3-8 (Al 10), under the subsection entitled "Air Cleanup Subsystem," delete the last sentence of the second paragraph regarding the EGTS ductwork which is connected to the Unit 2 annulus being isolated.

E1-20

I r I.

ENCLOSURE I WBN Unit 2 FSAR A 111 "Summary Listing of Al II FSAR Changes" Change Item No.

Change Change Description Package Area Number In FSAR Section 9.2.2.2 on Page 9.2-14 (Al 10), insert the following wording between the first and second paragraphs at the bottom of page:

"CCS Heat Exchanger C is subject to testing in accordance with Generic Letter 89-13, which requires cleaning and testing of the ERCW cooled CCS Heat Exchangers to verify the heat transfer capability. Since CCS Heat Exchanger C supports the operability of both CCS Trains 1 B and 2B, without a dual unit outage, cleaning CCS Heat Exchanger C requires a Unit 1 refueling outage and CCS Heat Exchanger

28.

Section A is needed to support CCS Train 2B operability.

2-111-28 9.2 Specifically, Unit 1 shall be in an outage with no RHR cooling required (full core offload) and CCS Heat Exchanger A (aligned to ERCW Train 1 B), CCS Pump 1 B-B, and CCS Pump C-S shall be aligned to CCS Train 2B. These components ensure that Unit 2 maintains two operable independent CCS trains, thereby; ensuring that Unit 2 is capable of responding to any design basis event. In this cleaning alignment, CCS can support two trains of Spent Fuel Pool Cooling utilizing Spent Fuel Pool Cooling Heat Exchangers A and B and Spent Fuel Pool Cooling Pump C-S."_

Section For Section 3.12.4.1 on Page 3.12-2 (Al 10), replace

29.

3.12 drawing number "44W411-7" with "2-44W411-7" in Item 2-111-29 No. 1 of Guideline 1.

El-21