ML12261A143

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OL - TVA Letter to NRC_2012-08-23_WBN U2 FSAR A109
ML12261A143
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 08/23/2012
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To:
Division of Operating Reactor Licensing
References
Download: ML12261A143 (37)
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Text

1 WBN2Public Resource From:

Boyd, Desiree L [dlboyd@tva.gov]

Sent:

Thursday, August 23, 2012 12:43 PM To:

Epperson, Dan; Wilson, George; Poole, Justin Cc:

Arent, Gordon; Hamill, Carol L; Boyd, Desiree L

Subject:

TVA letter to NRC_2012-08-23_WBN U2 FSAR A109 Attachments:

2012-08-23_WBN U2 FSAR A109_Final.pdf Please see attached TVA letter that was sent to the NRC today.

Thank You,

~*~*~*~*~*~*~*~*~*~*~

Désireé L. Boyd WBN Unit 2 Licensing dlboyd@tva.gov 423-365-8764

Hearing Identifier:

Watts_Bar_2_Operating_LA_Public Email Number:

731 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF317F18FB)

Subject:

TVA letter to NRC_2012-08-23_WBN U2 FSAR A109 Sent Date:

8/23/2012 12:43:22 PM Received Date:

8/23/2012 12:43:28 PM From:

Boyd, Desiree L Created By:

dlboyd@tva.gov Recipients:

"Arent, Gordon" <garent@tva.gov>

Tracking Status: None "Hamill, Carol L" <clhamill@tva.gov>

Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov>

Tracking Status: None "Epperson, Dan" <>

Tracking Status: None "Wilson, George" <George.Wilson@nrc.gov>

Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>

Tracking Status: None Post Office:

TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 279 8/23/2012 12:43:28 PM 2012-08-23_WBN U2 FSAR A109_Final.pdf 303437 Options Priority:

Standard Return Notification:

No Reply Requested:

Yes Sensitivity:

Normal Expiration Date:

Recipients Received:

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 August 23, 2012 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 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 109

References:

1. TVA letter to NRC dated March 5, 2012, Watts Bar Nuclear Plant (WBN)

- Unit 2 - Final Safety Analysis Report (FSAR), Amendment 108

2. TVA letter to NRC dated February 25, 2011, Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR) - Response to Chapters 11 and 12 Request for Additional Information
3. TVA letter to NRC dated June 3, 2010, Watts Bar Nuclear Plant (WBN) -

Unit 2 - Final Safety Analysis Report (FSAR) - Response to Preliminary Requests for Additional Information This letter transmits WBN Unit 2 FSAR Amendment 109 (A109), which reflects changes made since the issuance of Amendment 108 on March 5, 2012 (Reference 1).

contains a summary listing of FSAR sections and corresponding Unit 2 change package numbers associated with the A109 FSAR changes.

U.S. Nuclear Regulatory Commission Page 2 August 23, 2012 FSAR A109 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).

A109 addresses Supplemental Safety Evaluation Report (SSER), Appendix HH open items 115, 117, 138, and 139.

For Item No. 115, FSAR A109, Section 12.4 has been updated to reflect the design changes implemented to lower radiation levels as provided in TVAs letter dated June 3, 2010 (Reference 3).

For Item No. 117, FSAR A109, Section 12.3 has been updated to reflect the calculational basis for access to vital areas as provided in TVAs letter dated February 25, 2011 (Reference 2). The additional analyses cases were made using the Iodine spike source term in conformance with Commitment 9 made in Enclosure 4 of Reference 2. The results provided represent the limiting results and are well below the regulatory limits. The commitment is considered closed.

Item No. 138 regarding an updated Offsite Dose Calculation Manual (ODCM) to reflect annual average /Q and D/Q values has been addressed by Revision 20 of the current station ODCM. A copy of the current ODCM has been provided via CD to the NRR Project Manager for NRC review.

Item No. 139 regarding the results of the cost-benefit analysis required by 10 CFR Part 50, Appendix I, subsection II.D, has been addressed by revisions to Sections 11.2.9.2 and 11.3.10.2 within A109.

During a review of the SSER for Unit 2 FSAR Section 2.3, Meteorology, it was noted that the reference to Regulatory Guide (RG) 1.76, R1 had been previously made within FSAR Section 2.3.1.3, Severe Weather, on page 2.3-5. This statement is in error since the plant was designed to meet Revision 0 of this RG, not Revision 1. This condition has been entered into TVAs corrective action program as Service Request 599025.

U.S. Nuclear Regulatory Commission Page 4 August 23, 2012 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 4 August 23, 2012 bcc (Enclosures):

George Wilson U.S. Nuclear Regulatory Commission MS 8 B1A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Fred Brown, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-1 Item No.

Change Area Change Description Change Package Number

1.

Sections 11.2.9.2 11.3.10.2

1. For Section 11.2.9.2, perform the following:
a. Insert the following as the second paragraph of the section:

Based on the requirements of Section II.D of Appendix I of 10 CFR Part 50 with respect to meeting the as low as reasonably achievable criterion, the potential effectiveness of augmenting the liquid radwaste treatment management systems using items of reasonably demonstrated technology has determined that further effluent treatment will not affect reductions in the cumulative population dose reasonably expected with a 50 mile radius of the reactor at a cost of less than $1000 per man-rem or man-thyroid-rem.

b. Add as a Reference 2, the following letter:

(2) TVA letter to NRC date July 28, 2011, Results from Cost-Benefit Analysis of Radwaste System Enhancements

2. For Section 11.3.10.2, perform the following:
a. Insert the following as the second paragraph of the section:

Based on the requirements of Section II.D of Appendix I of 10 CFR Part 50 with respect to meeting the as low as reasonably achievable criterion, the potential effectiveness of augmenting the gaseous radwaste treatment management systems using items of reasonably demonstrated technology has determined that further effluent treatment will not affect reductions in the cumulative population dose reasonably expected with a 50 mile radius of the reactor at a cost of less than $1000 per man-rem or man-thyroid-rem.

b. Add as a Reference, the following letter:

TVA letter to NRC date July 28, 2011, Results from Cost-Benefit Analysis of Radwaste System Enhancements 2-109-01

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-2 Item No.

Change Area Change Description Change Package Number

2.

15.2.4.1 For Section 15.2.4.1,

1. A108-Page 15.2 Change Item 4 under Item e from Source range neutron flux - alarm on increase of 1.3 times in base count rate to Source range neutron flux - alarm of increase in base count rate above variable setpoint.
2. A108-Page 15.2 Change the next to last sentence of the last paragraph from The actual setpoint is maintained at 1.3 times background rather than at five times background as currently described in the FSAR. to The actual setpoint is maintained at approximately three times background rather than at one-half decade above background as currently described in the FSAR.

2-109-02

3.

Change Package No. 2-109-03 was not used.

4.

14.2

1.

In the first paragraph of Section 14.2.2, replace Unit 2 Vice President with "General Manager, Watts Bar Unit 2 Technical Services,"

2.

In the first paragraph of Section 14.2.2, replace Executive Vice President, Nuclear Generation Development and Construction (NGDC) with "Senior Vice President, Nuclear Construction (NC)."

3.

In the second paragraph of Section 14.2.2, delete test from the phrase Preoperational Startup Test Manager.

4.

In the third paragraph of Section 14.2.2, capitalize the word Unit.

5.

In the first paragraph of Section 14.2.2.1, insert (PSE) after phrase of Preoperational Startup Engineering.

6.

In the first paragraph of Section 14.2.2.1, replace the phrase, system test engineers, with Startup Test Engineers.

7.

In the second paragraph of Section 14.2.2.1, replace Unit 2 Vice President with "General Manager, Watts Bar Unit 2 Technical Services,"

8.

In the second paragraph of Section 14.2.2.1, replace Preoperational Startup organization with "PSE Organization."

9.

In the third paragraph of Section 14.2.2.1, replace the phrase, system test engineers, with Startup Test Engineers.

2-109-04

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-3 Item No.

Change Area Change Description Change Package Number

4.

(cont.)

14.2

10. In Item No. 10 of Section 14.2.2.1.1, replace the phrase, system test engineers, with Startup Test Engineers.
11. For Section 14.2.2.1.2, replace Section deleted by Amendment 84 with Startup Test Engineers.
12. Delete title 14.2.2.1.3 System Test Engineers.
13. In the first paragraph of new renumber Section 14.2.2.1.2 for Startup Test Engineers, replace the phrase, system test engineers, with Startup Test Engineers.
14. Insert the new Sections 14.2.2.1.3 and 14.2.2.1.4:

14.2.2.1.3 Unit 2 Operations During Preoperational Testing Phase The Operations Manager is responsible for proper operation of all equipment and ensuring that the conduct of test program does not place the plant in an unsafe condition. This manager will provide personnel from the operating organization as required supporting the conduct of testing activities.

The Unit Supervisor/Senior Reactor Operator (US/SRO) report to the Operations Manager and are responsible for the safe operation of the plant during assigned shifts. They also are responsible for the implementation of appropriate clearance procedures and have the authority to disallow or terminate testing due to conditions which could endanger personnel or equipment.

14.2.2.1.4 Unit 2 Quality Assurance Unit 2 Quality Assurance will conduct activities in accordance with Chapter 17 of the FSAR."

15. Insert into the first sentence of Section 14.2.2.2 between the word The and Plant the words, Nuclear Power Group (NPG)
16. Delete the second sentence of Section 14.2.2.2 which reads, With regard to the preoperational test program, the Unit 2 Vice President functionally reports to the Executive VP, NGDC and has responsibility for component acceptance and preoperational testing
17. In the second paragraph of Section 14.2.2.2, replace the Engineering with Manager.

2-109-04

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-4 Item No.

Change Area Change Description Change Package Number

4.

(cont.)

14.2

18. For Section 14.2.2.2.3, replace the Managers will be with Manager is in the first sentence of the section.

18a. Replace Shift Operations Supervisor with US/SRO in the second paragraph of Section 14.2.2.2.3.

19. Delete Section 14.2.2.2.4, Maintenance Manager (under VP, Unit 2).
20. For Section 14.2.2.3, replace Nuclear with Site Quality in the section title.
21. For Section 14.2.2.3, replace sentence which reads, A system of planned and periodic management audits will be conducted by WBN2 Project Nuclear Assurance (NA) with a sentence that reads, Site Quality Assurance will conduct activities in accordance with Chapter 17 of the FSAR.
22. Delete the word, Plant from Unit 1 Plant Operations and Unit 2 Plant Operations within the list contained in Section 14.2.2.5.1.
23. In the last paragraph of Section 14.2.2.5, replace Unit 2 Vice President with "General Manager, Watts Bar Unit 2 Technical Services,"
24. Delete the word, Plant from Plant Operations within the list contained in Section 14.2.2.6.1.
25. Delete the sentence that reads, The plant staff retains the responsibility for performing actual equipment operations and maintenance in section 14.2.4.3.
26. Replace Process Computer with: Integrated Computer System in Table 14.2-2 (Sheet 2 of 39).
27. Delete the phrase, analog RPI detector output voltage from the second sentence under the heading, Test Method, in Table 14.2-2 (Sheet 8 of 39).
28. Delete the phrase, pulse-to-analog converter chassis from the last sentence of the first paragraph of the Test Method section of Table 14.2-2 (Sheet 8 of 39).
29. Delete Item c) from the list of alarms of the Test Method section of Table 14.2-2 (Sheet 8 of 39).

2-109-04

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-5 Item No.

Change Area Change Description Change Package Number

4.

(cont.)

14.2

30. Replace the word, Test with Trouble in Item d) of the Test Method section of Table 14.2-2 (Sheet 8 of 39).
31. Re-label Item d) as c) in the list of alarms of the Test Method section of Table 14.2-2 (Sheet 8 of 39).
32. Re-label Item e) as d) in the list of alarms of the Test Method section of Table 14.2-2 (Sheet 8 of 39).
33. Replace the sentence in Item 2 of the Acceptance Criteria which reads, Each rod operates over its entire range of travel within the limits of RPI detector DC output voltage versus rod position calibration curve with one that reads as follows: Each RPI agrees within 12 steps of the group demand position for the full range of rod travel.
34. Replace the word, primary with the word, secondary in the second sentence under the heading of Test Method of Table 14.2-2 (Sheet 9 of 39).
33. Replace the phrase, hot. full-flow,conditions, with hot full flow conditions. from the fifth sentence of Test Method of Table 14.2-2 (Sheet 9 of 39).

2-109-04

5.

6.2.6-3, 6.2.6-4, Table 6.2.4-1

1.

On FSAR Table 6.2.4-1, Sheet 55 of 69, change the position of valves90-114 and 90-115 for penetration X-95C from open to closed during the ILRT.

2.

On FSAR Table 6.2.4-1, Sheet 57 of 69, change the position of valves43-202 and 43-434 for penetration X-99 from open to closed during the ILRT.

3.

On FSAR Table 6.2.4-1, Sheet 57 of 69, change the position of valves43-201 and 43-433 for penetration X-100 from open to closed during the ILRT.

4.

On FSAR Table 6.2.6-3, Page 3 of 6, delete the two references to Note 12 included, between penetrations X-24 and X-27A.

5.

On FSAR Table 6.2.6-4, add penetrations X-23, X-28, X-84A, X-86A, X-86B, X-86C, X-92C and X-96C with the corresponding description and status.

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-6 Item No.

Change Area Change Description Change Package Number

5.

(cont.)

6.2.6-3, 6.2.6-4, Table 6.2.4-1

6.

On FSAR Table 6.2.6-4, change the status for penetrations X-25B, X-92A, X-92B, X-97 and X-105 from "Vented" to "Vented (See Note 1)."

7.

On FSAR Table 6.2.6-4, change the status for penetrations X-26C, X-57B, X-60B and X-102 from "Vented" to "Normal Lineup."

8.

On FSAR Table 6.2.6-4, change the status for penetrations X-85A and X-106 from "See Note 3" to "Vented (See Note 1)."

9.

On FSAR Table 6.2.6-4, change the description for penetration X-120 from "Electrical Penetration" to "(see Note 4.)."

10. On FSAR Table 6.2.6-4, change penetration X-171F to penetration X-171E.
11. On FSAR Table 6.2.6-4, page 7 of 8, add penetrations X-20A and X-20B with the corresponding description and status.
12. On FSAR Table 6.2.6-4, page 8 of 8, change the description for penetration' "X-118" to "(See Note 4)."
13. Renumber the pages for FSAR Table 6.2.6-4.

2-109-05

6.

Table 6.2.4-1 On FSAR Table 6.2.4-1, Sheet 44 of 69 (A108), revise the sketch for penetration X-80 to remove the second test connection valve and label valve number 30-556.

2-109-06

7.

Table 7.5-2 In Table 7.5-2 on Page 7.5-21 (A108), change Item 22, Reactor Vessel Level, Type/Category from B1 C1 D2 to A1 B1 C1 D2 2-109-07

8.

11.2

1. Revise Section 11.2.6.5.1, Expected Normal Plant Operation, by changing the value for Steam Blowdown concentration from 3.65 E-5 uCi/cc to 8.446 E-6 uCi/cc (in three places - twice in second paragraph and once in the third paragraph).
2. Insert 20 between CFR and limits in the last sentence of the second paragraph of Section 11.2.6.5.2.
3. In Table 11.2-1, replace Item 3.0.j.1 which reads, 1) SGBD blowdown = 3E4 Ib/hr (86330.93 gal/day) @ 1 PCA (of-SSC) with 1)

SGB blowdown = 1.75E+5 #/hr =504,000 gal/day @ 1 PCA (of SSC)

4. Replace the following tables with supplied data from engineering calculation.

11.2-4 11.2-5 11.2-5a 11.2-5b 11.2-5d 2-109-08

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-7 Item No.

Change Area Change Description Change Package Number

9.

12.3 For Section 12.3.2.2 perform the following:

1. Replace Item 1 on pages 12.3-15 and 12.3-16 (A108) under the heading Shielding for Accident Conditions with the following:

(1) It must restrict the exposure at the site boundary from activity in the containment to a small fraction of 10 CFR 100 limits and (2) it must attenuate exposure rates at interior and other onsite locations from activity in the containment to levels which will allow required access. Continuous occupancy of the main control room and the Technical Support Center (TSC) is required during accident conditions. Infrequent access is required for the Operational Support Center (OSC), radio-chem lab, and other plant area's identified below during accident conditions. Analyses have been done to ensure the following post accident activities can be accomplished with dose to workers remaining below 5 rem gamma, 30 rem beta and 30 rem thyroid as required by NUREG-0737, II.B.2. Each mission is performed from two separate start and return locations: The OSC located on Service Building Elevation 713' and the TSC located on Control Building Elevation 755'. The TSC is located within the Main Control Room Habitability Zone.

(1) Continuous Main Control Room and Technical Support Center occupancy is required.

(2) Control or verification functions in the MG Set Room (Aux.

Building EI. 782') and/or 480 Shutdown Board Room (Aux.

Building EI. 757').

(3) Install CCS/ERCW spool piece near the CCS Surge Tank on Aux Building elevation 757'.

(4) Refill RWST following a LOCA from 1) The CVCS Hold up tank (valves on Aux. Building EI. 676' & 692' and 2) from the Spent Fuel Pool (valves on Aux. Building EI. 692' & 713').

(5) Since a single crew cannot remain in the Main Control Room for the duration of the accident, it must be possible to make the trip from the site boundary to the main control room sometime after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without receiving an excessive dose.

2-109-09

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-8 Item No.

Change Area Change Description Change Package Number

9.

(cont.)

12.3 (6) Sampling of gaseous effluents per the requirements of NUREG-0737at the Shield Building vent monitor location (Aux. Building EI 729').

(7) Sampling of the reactor coolant per NUREG-0737 requirements in the Hot Sample Room, Aux Building EI. 713'.

(8) Sampling of the containment atmosphere per NUREG-0737 requirements utilizing radiation monitors RE-90-106 & 112 located on Aux. Building EI 737'.

(9) Realignment of component cooling water to the spent fuel pool cooling system (valves on Aux Building floor EI. 737').

(10) Mission to the Intake Pumping Station to place ERCW backwash screens in service.

(11) Survey of the Auxiliary Building EI. 676', 692', 713', & 737' for leaks.

(12) Survey of the main steam lines and the steam generator blowdown in the Main Steam Valve Vault (Aux. building EI.729') and the Hot Sample Room (Aux. building EI.713')

during a steam generator tube rupture accident.

(13) Control and verification functions in the switchyard, Diesel Generator Building, and Turbine Building.

(14) Obtain a Steam generator blowdown sample from the Hot Sample Room on Aux. Building EI 713' (15) Mission to operate Control Air System (CAS), Auxiliary Control Air System (ACAS), ERCW, & CCS valves on Aux.

Building elevations 737', 729', 713' &692' and CAS breakers on Aux. Building elevations 757' &729' post LOCA.

2-109-09

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-9 Item No.

Change Area Change Description Change Package Number

9.

(cont.)

12.3

2. Replace the last paragraph starting on Page 12.3-16 (A108) and continuing to the top of Page 12.3-17 (A108) with the following paragraph:

The Main Control Room and the Technical Support Center (TSC) are shielded so that the integrated dose from external sources (activity inside the primary containment, in the passing cloud, and in surrounding rooms) obtained during occupancy following a loss-of-coolant accident would be a very small fraction of 5.0 rem gamma, 30 rem beta, and 30 rem thyroid dose. The major portion of the dose will then come from the airborne activity within the Main Control Room.

The dose from this airborne activity, which is more difficult to limit than that from the external sources, is discussed in Chapter 15.

Chapter 15 considers integrated exposures in the Main Control Room under accident conditions from all sources.

2-109-09

10.

5.2

1. Add new FSAR Section 5.2.2.3.1 heading entitled, Pressure Transient Analyses.
2. Renumber FSAR Section 5.2.2.4.2.1 as FSAR Section 5.2.2.3.1.1 and move below new FSAR Section 5.2.2.3.1.
3. Renumber FSAR Section 5.2.2.4.2.2 as FSAR Section 5.2.2.4.2.1.
4. Renumber FSAR Section 5.2.2.4.2.3 as FSAR Section 5.2.2.4.2.2.

2-109-10

11.

9.2 For Section 9.2.1.5.3, Flow Instrumentation, perform the following:

1. Delete the phrase and component cooling from the second sentence of this section.
2. Insert new sentence between the second and third sentences of this section which reads as follows: The ERCW flow rate through each component cooling heat exchanger is also available in the main control room.

2-109-11

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-10 Item No.

Change Area Change Description Change Package Number

12.

2.4

1. Revise the elevation value for the maximum flood elevation from 738.8 to 739.2
2. Revise the elevation values for the following locations:
a. Diesel Generator Building (from 741.2 to 741.6)
b. Intake Pumping Station (from 741.0 to 741.7)
c. Auxiliary, Control and Shield Buildings(from 740.6 to 741.0)
3. Revise the average daily streamflow value from 27,100 to 27,000 and the maximum dally discharge from 211,000 to 208,400 in the second paragraph from the top of Page 2.4-5 (A108).
4. Insert the word, tailwater between the words maximum and elevation of the last sentence of the first paragraph at the top of Page 2.4-6 (A108).
5. Revise the discharge value for the May 8, 1984 entry from 214,100 to 208,400 in the listing at the bottom of Page 2.4-6 (A108).
6. Revise the maximum PMF value from Elevation 738.8 to Elevation 739.2 in the fourth paragraph from the top of Page 2.4-7 (A108).
7. Revise the phrase for wind wave run up during the PMF at the Diesel Generator Building from Elevation 741.2 which is 0.8 feet, to Elevation 741.6 ft. which is 0.4 ft.
8. Revise the water levels for Auxiliary, Control, and Shield Building from 740.6 to 741.0 in the next to last sentence of the fourth paragraph from the top of Page 2.4-8 (A108).
9.

Revise the design basis flood level for Diesel Generator Building from 741.2 to 741.6 in the last sentence of the fourth paragraph from the top of Page 2.4-8 (A108).

10. Add footnote [35] to the document Hydrometeorological Report No. 56 at the end of the third paragraph under Section 2.4.2.3 on Page 2.4-8 (A108) 2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-11 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

11. Revise the second paragraph from the top of Page 2.4-12 (A108) to read as follows:

In both storms, the West Saddle Dike at Watts Bar Dam would be overtopped and breached. No other failure would occur. Maximum discharge at the plant is 1,003,363 cfs from Watts Bar Dam with an additional 97,990 cfs from Watts Creek and 243,782 cfs from Yellow Creek for the 21,400-square-mile storm. The resulting PMF elevation at the plant would be 739.2 ft excluding wind wave effects.

12. Revise the first paragraph of Section 2.4.3.1 on Page 2.4-12 (A108) to read as follows:

Probable maximum precipitation (PMP) for the watershed above Chickamauga and Watts Bar Dams for determining PMF has been defined for TVA by the Hydrometeorological Report No. 41.[4] This report defines depth-area-duration characteristics, seasonal variations, and antecedent storm potentials and incorporates orographic effects of the Tennessee River Valley. Due to the temperate climate of the watershed and relatively light snowfall, snowmelt is not a factor in generating maximum floods for the Tennessee River at the site.

2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-12 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

13. Revise the fifth paragraph from the top of Page 2.4-14 to read as follows:

Discharge rating curves are provided in Figure 2.4-11 (13 Sheets) for the reservoirs in the watershed at and above Chickamauga. The discharge rating curve for Chickamauga Dam is for the current lock configuration with all 18 spillway bays available. Above Watts Bar Nuclear Plant, temporary flood barriers have been installed at four reservoirs (Watts Bar, Fort Loudoun, Tellico and Cherokee Reservoirs) to increase the height of embankments and are included in the discharge rating curves for these four dams.

Increasing the height of embankments at these four dams prevents embankment overflow and failure of the embankment. The vendor supplied temporary flood barriers were shown to be stable for the most severe PMF headwater/tailwater conditions using vendor recommended base friction values. A single postulated Fort Loudoun Reservoir rim leak north of the Marina Saddle Dam which discharges into the Tennessee River at Tennessee River Mile (TRM) 602.3 was added as an additional discharge component to the Fort Loudoun Dam discharge rating curve. Seven Watts Bar Reservoir rim leaks were added as additional discharge components to the Watts Bar Dam discharge rating curve. Three of the rim leak locations discharge to Yellow Creek, entering the Tennessee River three miles downstream of Watts Bar Dam. The remaining four rim leak locations discharge to Watts Creek, which enters Chickamauga Reservoir just below Watts Bar Dam.

14. Replace the phrase, steady state HEC RAS flow with the phrase, steady-state SOCH, in the first sentence of the last paragraph on Page 2.4-15 (A108).
15. Replace the phrase, HEC RAS steady state model with the phrase, SOCH steady state model, in the first sentence of the last paragraph on Page 2.4-15 (A108).
16. Replace the PMF discharge value of 1,065,000 cfs with 1,088,625 cfs, in the first sentence of the first paragraph of Section 2.4.3.4.

2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-13 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

19. Replace the word, will, with is postulated to, in the second line of the first paragraph at the top of Page 2.4-18 (A108).
20. Insert the word, likely between the words, will, and be which are in the fifth line of the first paragraph at the top of Page 2.4-18 (A108).
21. Revise the second paragraph from the top of the Page 2.4-18 (A108) to read as follows:

Should the barge approach the spillway portion broadside, two and possibly three bridge bents may fail. For this condition the bridge would likely collapse on the barge and the barge would be grounded on the tops of the spillway piers. For this condition the barge would likely ground before striking the spillway gates because the gates are about 20 ft downstream from the leg of the upstream bridge bents.

22. Revise the paragraph under the heading, Lock Gates, on Page 2.4-18 (A108) to read as follows:

The lock gates at Fort Loudoun, Watts Bar, and Chickamauga were examined for possible failure with the conclusion that no potential for failure exists. The lock gate structural elements may experience localized yielding and may not function normally following the most severe headwater/tailwater conditions.

23. Replace the controlling PMF elevation value of 738.8 with 739.2, contained in the first sentence of the first paragraph of Section 2.4.3.5 on Page 2.4-18 (A108).
24. Revise the listed elevation values (Diesel Generator Building earth embankment runup, Intake Pumping Station, west wall, and Auxiliary, Control and Reactor Building walls) contained within the fourth paragraph on Page 2.4-20 (A108) as follows:

From To 741.2 741.6 741.0 741.7 740.6 741.0 2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-14 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

25. Revise the last paragraph under the heading, Embankment, on Page 2.4-23 to read as follows:

As discussed in Section 2.4.3, temporary flood barriers are installed on embankments at Cherokee, Watts Bar, Fort Loudoun and Tellico Reservoirs. However, the temporary flood barriers are not required to be stable following an OBE or SSE and are not assumed to increase the height of the embankments for these loading conditions.

26. Revise the Watts Bar Dam headwater value from 763.42 ft., 6.58 ft. below top of dam to 762.96 ft., 6.54 ft below top of dam in the third paragraph of Page 2.4-29.
27. Revise the Chickamauga headwater value that would be reached from 701.48 ft., 4.52 ft. below top of dam to 701.05 ft, 4.95 ft below top of dam, in the third paragraph of Page 2.4-29 (A108).
28. Revise the fourth paragraph on Page 2.4-29 (A108) from The peak discharge at the Watts Bar Nuclear Plant site produced by the OBE failure of Norris and Tellico dams coincident with the one-half PMF is 910,994 cfs. The peak elevation is 728.84 ft., 0.84 feet above 728 plant grade to read as follows:

The peak discharge at the Watts Bar Nuclear Plant site produced by the OBE failure of Norris and Tellico Dams coincident with the one-half PMF is 917,284 cfs. The peak elevation is 728.67 ft, 0.67 ft above 728.0 ft plant grade.

2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-15 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

29. Revise the last paragraph on Page 2.4-31 (A108) and continues onto Page 2.4-32 (A108) from As discussed in Section 2.4.3, sand baskets are installed on embankments at Fort Loudoun. The sand baskets are assumed to fail in the SSE and are thus not credited for increasing the height of the Fort Loudoun embankments. The flood for this postulated failure combination would overtop and breach the south embankment and marina saddle dam at Fort Loudoun. At Watts Bar Dam the headwater would reach Elevation 765.54, 4.46 feet below the top of the earth embankment of the main dam. However, the West Saddle Dike with top at elevation 757 would be overtopped and breached. The headwater at Chickamauga Dam would reach elevation 701.14, 4.86 ft. below top of dam. The embankments at Nickajack Dam would be overtopped but was conservatively postulated not to breach. to read as follows:

As discussed in Section 2.4.3, temporary flood barriers are installed on embankments at Fort Loudoun and Tellico Reservoirs.

The temporary flood barriers are assumed to fail in the SSE and are thus not credited for increasing the height of the Fort Loudoun or Tellico Reservoirs embankments. The flood for this postulated failure combination would overtop and breach the south embankment and Marina Saddle Dam at Fort Loudoun. At Watts Bar Dam, the headwater would reach elevation 765.54 ft, 4.46 ft below the top of the earth embankment of the main dam. However, the West Saddle Dike with top at elevation 757.0 ft would be overtopped and breached. The headwater at Chickamauga Dam would reach elevation 701.14 ft, 4.86 ft below top of dam. The embankments at Nickajack Dam would be overtopped but was conservatively postulated not to breach.

2-109-12

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-16 Item No.

Change Area Change Description Change Package Number

12.

(cont.)

2.4

30. Revise Design Basis Flood Values as follows:

Value from to Probable Maximum Flood (still reservoir) 738.8 739.2 ft.

DBF Runup on 4:1 Sloped Surfaces 741.2 741.6 ft.

DBF Runup on critical vertical wall of the Intake Pumping Station 741.0 741.7 ft.

DBF Surge level within flooded structures 739.3 739.7 ft.

31. Revise the time range from 1 to 4 days to 1 to 5 days in the last sentence of Section 2.4.14.1.3 on Page 2.6-46 (A108).
32. Revise one of the three critical event times from 28 to 27 in the second paragraph from top of Page 2.4-57 (A108).
33. Delete Reference 37 and renumber current Reference 38 as Reference 37 on Page 2.4-60 (A108)
34. Perform a number of editorial type changes throughout the section.

Some examples are provided below:

a. Insert/abbreviate the foot (ft.) after each elevation value throughout the section.
b. Insert/abbreviate the word dam(s) after each name of dam.
c. Replace the term Intake Pumping Structure, with the term Intake Pumping Station
d. Replace single number values with the word form (i.e. 1 with one, etc.).

2-109-12

13.

10.2.1 In FSAR Section 10.2.1, revise the third sentence of the second paragraph to identify the zonal back pressure for the valves wide open condition as 1.92/2.70/3.75 inches of Hg absolute.

2-109-13 14 12.4 Add the list of design changes that will be implemented for WBN Unit 2 before power operations to FSAR Section 12.4.

2-109-14

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-17 Item No.

Change Area Change Description Change Package Number

15.

Table 3.9-25

1. Delete the duplicate entry for valve FCV-32-81 on FSAR Table 3.9-25, Sheet 9 of 23.
2. Correct the listing of valve 2-CKV-32-323 on FSAR Table 3.9-25, Sheet 10 of 23.

2-109-15

16.

14.2

1.

In the first paragraph of Section 14.2.2, replace Unit 2 Vice President with "General Manager, Watts Bar Unit 2 Engineering and Construction"

2.

In the second paragraph of Section 14.2.2.1, replace Unit 2 Vice President with "Completions and Startup Manager,"

3.

In the last paragraph of Section 14.2.2.5, replace Unit 2 Vice President with "Completions and Startup Manager,"

4.

Re-title Item No. 6 to read, Performance rather than Instructions on Page 14.2-11 (A108)

5.

Replace the word, instruction with the word performance, in the first sentence in Item No. 6 on Page 14.2-11 (A108)

6.

Insert a period after the word, bypasses in the first sentence of Item No. 6 on Page 14.2-11 (A108). In addition, for the same sentence as described above, delete the remaining phrase, and restoration of the system to normal status following test.

7.

Insert new second sentence for Item no. 6 on Page 14.2-11 (A108) to read as follows:

Provisions will be made for recording all pertinent test data regarding system conditions and performance.

8.

Re-title Item No. 7 to read, Post Performance Activities rather than Data Collection/Test Results on Page 14.2-11 (A108) 2-109-16

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-18 Item No.

Change Area Change Description Change Package Number

16.

(cont.)

14.2

9.

Replace the existing text of Item No. 7 with the following text:

Post-Performance Activities include notification of field completion testing to the responsible Operations personnel, restoration of the plan/system normal status including removal of jumpers, special test instrumentation and restoration of instrument settings. Also, post test accuracy test checks on plant instrumentation and M&TE used to gather quantitative Acceptance Criteria data is performed.

10.

Add new Item No. 8 to be entitled, Records, and insert the following text:

Provisions are made to determine if the completed test package is a quality related or non-quality record.

2-109-16

17.

2.1 2.2 2.3

1. Delete the phrase, the Watts Bar Steam Plant, in the second sentence of the second paragraph of Section 2.1.1.1 on Page 2.1-1 (A108).
2. Replace the second sentence of the first paragraph of Section 2.2.1 on Page 2.2-1 (A108) from The only significant nearby industrial facility is the Watts Bar Steam Plant, to There are no significant industrial facilities near WBN.
3. Delete the phrase, Watts Bar Steam Plant and, from the second sentence of the third paragraph of Section 2.2.1 on Page 2.2-1

.(A108) 4 Delete the first paragraph of Section 2.2.2.1 on Page 2.2-1 (A108)

5. Delete the last sentence of the first paragraph of Section 2.2.2.2 on page 2.2-1.
6.

Delete the third paragraph from top of Page 2.3-5 (A108).

2-109-17

ENCLOSURE 1 WBN Unit 2 FSAR A109 Summary Listing of A109 FSAR Changes" E1-19 Item No.

Change Area Change Description Change Package Number

18.

Table 6.2.4-1

1.

On FSAR Table 6.2.4-1, Page 8 of 69, change the "N" in the "Pos Ind in MCR" column for valves 2-FCV-1-15 and 2-FCV-1-147 in penetration X-13A to a "Y."

2.

On FSAR Table 6.2.4-1, Page 11 of 69, change the "Y" in the "Pos Ind in MCR" column for relief valve 62-662 in penetration X-15 to an "N."

3.

On FSAR Table 6.2.4-1, Page 55 of 69, change the "O" in the "ILRT" column for valves90-114 and 90-115 in penetration X-95C to a "C."

4.

On FSAR Table 6.2.4-1, page 57 of 69, change the "O" in the "ILRT" column for valves43-202 and 43-434 in penetration X-99 to a "C.

5.

On FSAR Table 6.2.4-1, page 57 of 69, change the "O" in the "ILRT" column for valves43-201 and 43-433 in penetration X-100 to a "C."

2-109-18

19.

Table 7.5-2 15.2.4

1. For Table 7.5-2, Page 10 of 41, correct the spelling of Reactor in Item No. 76.
2. For Item 3 of Section 15.2.4.2.6, delete the word to between a and critical.

2-109-19

20.

14.2

1. Delete the phrase, (other load group completely deenergized) in Item No. 1 under the heading, Test Method on Page 14.2-63.
2. Delete the phrase, (other load group completely deenergized) in Item No. 1 under the heading, Acceptance Criteria on Page 14.2-
64.
3. On Page 2.4-115, insert a new Item No. 3 in the heading, Test Method, as follows:

"3. Perform isothermal cross-calibration of Reactor Coolant Loop Resistance Temperature Detectors and Thermocouples."

4. On Page 2.4-115, renumber Items 3 through 13 through 4 through
14.
5. For Item No. 4 under the heading RCS Heatup, on Page 2.4-167, replace Deleted, with "RCS Loop RTD and Thermocouple Cross Calibration.
6. For Item No. 9 under the heading Integrated Hot Functional Testing, on Page 2.4-168, replace Deleted, with "RCS Loop RTD and Thermocouple Cross Calibration.

2-109-20

ENCLOSURE 2 WBN Unit 2 FSAR A109 Summary of Redacted Pages Chapter Page(S)

Section No.

Figure No.

Basis For Redaction E2-1 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 Sheet 1 Security Related, 10CFR2.390(d)(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 Sheet 1 Security Related, 10CFR2.390(d)(1) 2 2.4-178 2.4 2.4-40f Sheet 1 Security Related, 10CFR2.390(d)(1) 2 2.4-181 2.4 2.4-40g Sheet 1 Security Related, 10CFR2.390(d)(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)

ENCLOSURE 2 WBN Unit 2 FSAR A109 Summary of Redacted Pages Chapter Page(S)

Section No.

Figure No.

Basis For Redaction E2-2 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)

ENCLOSURE 2 WBN Unit 2 FSAR A109 Summary of Redacted Pages Chapter Page(S)

Section No.

Figure No.

Basis For Redaction E2-3 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)

ENCLOSURE 3 WBN Unit 2 FSAR A109 List Of Files And File Sizes On The Security-Related OSM (OSM #1)

E3-1

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 109 - List of Files on Security-Related OSM File Name File Size - Bytes TVA_WBN-2_FSAR_Files 001_TVA_WB_FSAR_TOC.pdf 362,572 002_TVA_WB_FSAR_LRP.pdf 92,718 003_TVA_WB_FSAR_Section_1.pdf 4,646,447 004_TVA_WB_FSAR_Section_2_A.pdf 19,883,491 005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 44,211,640 005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 42,591,488 006_TVA_WB_FSAR_Section_2_C.pdf 2,106,765 007_TVA_WB_FSAR_Section_2_D.pdf 31,323,884 008_TVA_WB_FSAR_Section_2_E.pdf 47,312,507 009_TVA_WB_FSAR_Section_3_A.pdf 2,625,195 010_TVA_WB_FSAR_Section_3_B.pdf 7,062,998 011_TVA_WB_FSAR_Section_3_C.pdf 30,016,093 012_TVA_WB_FSAR_Section_3_D.pdf 11,764,974 013_TVA_WB_FSAR_Section_4.pdf 24,486,322 014_TVA_WB_FSAR_Section_5.pdf 9,920,972 015_TVA_WB_FSAR_Section_6_A.pdf 26,045,220 016_TVA_WB_FSAR_Section_6_B.pdf 9,335,707 017_TVA_WB_FSAR_Section_7.pdf 14,022,462 018_TVA_WB_FSAR_Section_8.pdf 29,729,338 019_TVA_WB_FSAR_Section_9_A.pdf 24,541,210 020_TVA_WB_FSAR_Section_9_B.pdf 16,493,418 021_TVA_WB_FSAR_Section_10.pdf 14,163,516 022_TVA_WB_FSAR_Section_11.pdf 4,072,904 023_TVA_WB_FSAR_Section_12.pdf 5,990,097 024_TVA_WB_FSAR_Section_13.pdf 3,238,697 025_TVA_WB_FSAR_Section_14.pdf 1,185,393 Page 1 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 109 - List of Files on Security-Related OSM File Name File Size - Bytes 026_TVA_WB_FSAR_Section_15.pdf 46,630,176 027_TVA_WB_FSAR_Section_16.pdf 148,062 028_TVA_WB_FSAR_Section_17.pdf 144,876 Total 474,149,142 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 Page 2 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 109 - 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_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_Oversized_FSAR_Table 001_TVA_WB_FSAR_Table_6.2.4-1.pdf 1,220,825 Total 1,220,825 Page 3 of 3

ENCLOSURE 4 WBN Unit 2 FSAR A109 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 109 List of Files on Publicly Available OSM File Name File Size - Bytes TVA_WBN-2_FSAR_Files 001_TVA_WB_FSAR_TOC.pdf 362,572 002_TVA_WB_FSAR_LRP.pdf 92,718 003_TVA_WB_FSAR_Section_1.pdf 839,789 004_TVA_WB_FSAR_Section_2_A.pdf 19,554,223 005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 33,946,265 005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 36,333,391 006_TVA_WB_FSAR_Section_2_C.pdf 2,106,765 007_TVA_WB_FSAR_Section_2_D.pdf 31,323,884 008_TVA_WB_FSAR_Section_2_E.pdf 45,933,118 009_TVA_WB_FSAR_Section_3_A.pdf 2,333,760 010_TVA_WB_FSAR_Section_3_B.pdf 5,661,228 011_TVA_WB_FSAR_Section_3_C.pdf 25,183,642 012_TVA_WB_FSAR_Section_3_D.pdf 11,496,271 013_TVA_WB_FSAR_Section_4.pdf 24,486,322 014_TVA_WB_FSAR_Section_5.pdf 9,920,972 015_TVA_WB_FSAR_Section_6_A.pdf 23,164,754 016_TVA_WB_FSAR_Section_6_B.pdf 9,335,707 017_TVA_WB_FSAR_Section_7.pdf 14,022,462 018_TVA_WB_FSAR_Section_8.pdf 26,768,931 019_TVA_WB_FSAR_Section_9_A.pdf 24,280,149 020_TVA_WB_FSAR_Section_9_B.pdf 15,278,899 021_TVA_WB_FSAR_Section_10.pdf 14,163,516 022_TVA_WB_FSAR_Section_11.pdf 4,072,904 023_TVA_WB_FSAR_Section_12.pdf 1,728,081 024_TVA_WB_FSAR_Section_13.pdf 3,238,697 025_TVA_WB_FSAR_Section_14.pdf 1,185,393 Note: Byte amounts in italics are redacted files.

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ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 109 List of Files on Publicly Available OSM File Name File Size - Bytes 026_TVA_WB_FSAR_Section_15.pdf 46,630,176 027_TVA_WB_FSAR_Section_16.pdf 148,062 028_TVA_WB_FSAR_Section_17.pdf 144,876 Total 433,737,527 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 Note: Byte amounts in italics are redacted files.

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ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 109 List of Files on Publicly Available 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_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_Oversized_FSAR_Table 001_TVA_WB_FSAR_Table_6.2.4-1.pdf 122,825 Total 122,825 Note: Byte amounts in italics are redacted files.

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