ML12083A136

Transmittal of Amendment 108 to Final Safety Analysis Report

ML12083A136
Person / Time
Site:	Watts Bar
Issue date:	03/05/2012
From:	Hruby R Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML12083A136 (54)

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 March 5, 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 108

References:

1. TVA letter to NRC dated November 17, 2011, "Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR), Amendment 107"

2. TVA letter to NRC dated January 12, 2012, "Watts Bar Nuclear Plant (WBN)

Unit 2 - Final Safety Analysis Report (FSAR) - Chapter 15.2.4 Inadvertent Boron Dilution This letter transmits WBN Unit 2 FSAR Amendment 108 (Al 08), which reflects changes made since the issuance of Amendment 107 on November 17, 2011 (Reference 1). contains a summary listing of FSAR sections and corresponding Unit 2 change package numbers associated with the Al 08 FSAR changes. Please note that the Section 4.3 changes resulted from fuel vendor's final design of the initial Unit 2 Cycle 1 core load. In addition, the densification factor statements contained in Subsection 4.3.2.2.1 were removed based upon previous NRC approval of Westinghouse WCAP 13589-A, "Assessment of Clad Flattening and Densification Power Spike Elimination in Westinghouse Nuclear Fuel," on January 30, 1995. These changes did not alter the conclusions previously submitted in Section 4.3. In addition, changes in Section 15.2 satisfy the commitment previously made regarding inadvertent boron dilution in Reference 2.

FSAR Al 08 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.

7by~c

U.S. Nuclear Regulatory Commission Page 2 March 5, 2012 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.

I declare under the penalty of perjury that the foregoing is true and correct to the best of my knowledge. Executed on the 5th day of March, 2012.

Respectfully, Raymond A. Hruby, Jr.

General Manager, Technical Services Watts Bar Unit 2

Enclosures:

1. WBN Unit 2 FSAR Al 08, "Summary Listing of Al 08 FSAR Changes"

2. WBN Unit 2 FSAR Al 08, "Summary of Redacted Pages"

3. WBN Unit 2 FSAR Al 08, "List of files and file sizes on the security-related OSM (OSM #1)"

4. WBN Unit 2 FSAR Al 08, "List of files and file sizes on the publicly available OSM (OSM #2)"

Attachments:

1. OSM #1: WBN Unit 2 FSAR Amendment 108 - Security-Related Information - Withhold Under 10 CFR 2.390

2. OSM #2: WBN Unit 2 FSAR Amendment 108 - Publicly Available Version cc: See Page 3

U.S. Nuclear Regulatory Commission Page 3 March 5, 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

ENCLOSUREI WBN Unit 2 FSAR Al07 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number Revise Watts Bar Unit 2 FSAR Section 8.1.5.3, Note 12 as follows:

"(12) Full compliance with IEEE Std. 450-1980 with the following exceptions:

1. A modified performance test based on section 5.4 of IEEE Std. 450-1995 may be performed in lieu of the performance or service test in accordance with the Technical Specification.

1.Section 8.1 2-1 08-01

2. Also, the criteria for acceptance of connection resistance measurements may be established by the manufacturer's recommended limit as indicated In IEEE Std. 450-1995, Section D.2.

3.

Additionally, a performance test will be performed at a 24 months frequency if the battery has reached 85% of the expected life with capacity - 100% as delineated in IEEE Std. 450-1995, Section 5.2.C."

For Section 6.7-13.2, 1:

Insert the "Personnel Access Door," between the words, "panel" and "frame" of the second sentence of the first paragraph. Insert "Equipment Access" between the words "The" and 'door," of the third sentence of the first paragraph.

2.

Replace the last sentence of the first paragraph and the second paragraph with the following paragraphs:

"It is noted in Unit 2 only, the hoist assembly is

2.

Section 6.7 abandoned in place and a chain hoist is used by 2-108-02 personnel when the equipment door is required to be opened.

All exposed surfaces are protected against corrosion by appropriate coating. In Unit 1, limit switches are provided to monitor movement of each door and to indicate position as a part of the door position monitoring system. In Unit 2, limit switches are provided to monitor personnel access door latch position and the equipment access door seal inflation with the personnel access door position monitoring system."

E1-1

ENCLOSURE 1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number For Section 6.7.15.2, under the heading, "Equipment Access Doors," add the subheading, "Unit 1." At the end of the second paragraph, insert the following paragraph:

"Unit 2 Each personnel access door is provided with two limit

2.

switches fitted in a single series circuit providing control Section 6.7 room indication of the personnel access doors. Each 2-108-02 (cont.)

equipment access door is provided with one single pole double throw or equivalent switch to indicate the door seal is inflated. The normally closed set of contacts for switches on the equipment access doors, latched and inflated seals, are connected in series to a monitor light

("Access Door Closed"). The normally open set of contacts are connected in parallel to a monitor light (Access Door Open"). Refer to Figure 6.7-41."

1. On FSAR Table 3.9-26, Sheet 3 of 6, delete drawings 47W859-3 and 47W859-4 from the system column for Containment Spray.

2.

On FSAR Table 3.9-26, Sheet 4 of 6, add drawing

3.

Table 3.9-26 47W859-3 to the system column for Component 2-108-03 Cooling Water.

3. On FSAR Table 3.9-26, Sheet 4 of 6, delete drawing 472812-1 from the system column for Component Cooling Water.

For Section 6.2.3.3.2, Emergency Gas Treatment System

4.

Section 6.2.3.3.2 (EGTS) - Inactive Air Cleanup Unit Cooling Capabilities, 2-108-04 Paragraph 2, revise the cooling air flow rate from "90 cfm" to "112 cfm."

Changes in atmospheric dispersion (X/Q) data to reflect 1991 to 2010 data result in a change in offsite LOCA radiation dose during purging and results in revision of FSAR section 6.5.3.1 & Table 6.5-7. The X/Qs have been

5.

Section 6.5.3.1 changed to meet Unit 2 licensing requirements. TVA 2-108-05 Table 6.5-7 Calculation, T1-632, R7 has been revised to reflect the X/Q changes which resulted in a change to the offsite radiation doses for a LOCA during containment purging.

Revisions to the text for FSAR section 6.5.3.1 and to Table 6.5-7 are to reflect changes in calculation.

E1-2

ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number Change the last bullet in Section 15.5.6.3 from "No filtration of the release from the spent fuel pool to the

6.

Section 15.5.6.3 environment by the ABGTS is assumed" to "No filtration of 2-108-06 the release from the Containment or the spent fuel pool to the environment by the Containment Purge filters or the ABGTS is assumed".

1. On FSAR Table 6.2.4-1, page 2 of 69, add locked closed globe valve 30-555 to the listing for containment penetration X-4. Also, identify valve 30-555 is subject to Appendix J Test Type A and C testing.

2. On FSAR Table 6.2.4-1, page 2 of 69, add locked closed globe valve 30-554 to the listing for containment penetration X-5. Also, identify valve 30-554 is subject to Appendix J Test Type A and C testing.

3. On FSAR Table 6.2.4-1, page 3 of 69, add locked closed globe valve 30-558 to the listing for containment penetration X-6. Also, identify valve 30556 is subject to Appendix J Test Type A and C testing.

7.

Table 6.2.4-1

4. On FSAR Table 6.2.4-1, page 3 of 69, add locked 2-108-07 closed globe valve 30-557 to the listing for containment penetration X-7. Also, identify valve 30-557 is subject to Appendix J Test Type A and C testing.

5. On FSAR Table 6.2.4-1, page 5 of 69, add locked closed globe valve 30-563 to the listing for containment penetration X-9A. Also, identify valve 30-563 is subject to Appendix J Test Type A and C testing.

6. On FSAR Table 6.2.4-1, page 5 of 69, add locked closed globe valve 30-562 to the listing for containment penetration X-98. Also, identify valve 30-562 is subject to Appendix J Test Type A and C testing.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

7. On FSAR Table 6.2.4-1, page 6 of 69, add locked closed globe valve 30-561 to the listing for containment penetration X-1OA. Also, identify valve 30-561 is subject to Appendix J Test Type A and C testing.

8. On FSAR Table 6.2.4-1, page 6 of 69, add locked closed globe valve 30-560 to the listing for containment penetration X-1OB. Also, identify valve 30-560 is subject to Appendix J Test Type A and C testing.

9. On FSAR Table 6.2.4-1, page 6 of 69, add locked closed globe valve 30-559 to the listing for containment penetration X-1 1. Also, identify valve 30-559 is subject to Appendix J Test Type A and C testing.

10. On FSAR Table 6.2.4-1, page 44 of 69, add locked closed globe valve 30-556 to the listing for Table 6.2.4-1 containment penetration X-80. Also, identify valve 30-(cont.)

Table 6.2.6-2 556 is subject to Appendix J Test Type A and C 2-108-07 testing.

11. On FSAR Table 6.2.6-2, add valve 30-555 to the listing for containment penetration X-4, valve 30-554 to the listing for containment penetration X-5, valve 30-558 to the listing for containment penetration X-6, valve 30-557 to the listing for containment penetration X-7, valve 30-563 to the listing for containment penetration X-9A, valve 30-562 to the listing for containment penetration X-98, valve 30-561 to the listing for containment penetration X-10A, valve 30-560 to the listing for containment penetration X-1OB, valve 30-559 to the listing for containment penetration X-1 1 and valve 30-556 to the listing for containment penetration X-80.

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

13. On FSAR Table 6.2.4-1, Sheet 65 of 69, add the abbreviation for a valve with a manual actuator (M).

El -4

ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

1. Delete the asterisked note on FSAR Table 9.3-8, page 4 of 4. Also remove the asterisks from the components listed in FSAR Table 9.3-8.

2.

Remove local panel 2-L-366 from FSAR Table 9.3-8, page 2 of 4. Also add local panel 2-L-351 B to FSAR Table 9.3-8, page 2 of 4, as receiving Auxiliary Control Air System (ACAS) Train A control air.

3. Remove panels O-L-535 and 0-L-536 from FSAR Table 9.3-8, page 3 of 4.

4.

Add damper 0-FCO-31-12 to FSAR Table 9.3-8, page 3 of 4, as a normally open - fail open damper supplied with ACAS Train A control air. Also add damper 0-FCO-31 -11 to FSAR Table 9.3-8, page 3 of 4, as a normally open - fail open damper supplied with ACAS Train B control air.

5.

Add damper 0-FCO-31-82 to FSAR Table 9.3-8, page 3 of 4, as a modulating - fail closed damper supplied with ACAS Train A control air. Also add damper 0-FCO-31-91 to FSAR Table 9.3-8, page 3 of 4, as a

8.

Table 9.3-8 modulating - fail closed damper supplied with ACAS 2-108-08 Train B control air.

6. Add controllers 0-MC-31-176 and 0-MC-31-231 to FSAR Table 9.3-8, page 3 of 4, as HVAC equipment that is supplied with ACAS Train A control air. Also add controllers 0-MC-31-201 and 0-MC-31-261 to FSAR Table 9.3-8, page 3 of 4, as HVAC equipment that is supplied with ACAS Train B control air.

7. Add moisture control valves 0-MCV-31-176, 0-MCV-31-231 and 0-MCV-31-232 to FSAR Table 9.3-8, page 3 of 4, as modulating - fail open valves supplied with ACAS Train A control air. Also add moisture control valves 0-MCV-31-201, 0-MCV-31-261 and 0-MCV 262 to FSAR Table 9.3-8, page 3 of 4, as modulating -

fail open valves supplied with ACAS Train B control air. Additionally, add a note to FSAR Table 9.3-8, page 4 of 4, for these moisture control valves to indicate they do not directly receive control air from ACAS but instead receive an input signal for position control from controllers 0-MC-31-176, 0-MC-31201, 0-MC-31-231 and 0-MC-31-261 which are supplied with control air from ACAS.

E1-5

ENCLOSURE 1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

8.

Remove valve 2-FCV-65-60 and add valve 2-FCV 50 to FSAR Table 9.3-8, page 2 of 4.

9.

On FSAR Table 9.3-8, page 2 of 4, change the OP Mode - Failure Mode for valves 2-FCV-65-4 and 2-FCV-65-5 from NA to normally open - fail closed, and for valves 2-FCV-65-7 and 2-FCV-65-9 from NA to normally closed - fail closed.

10. On FSAR Table 9.3-8, page 2 of 4, change the OP Mode - Failure Mode for dampers 1-PCO-65-80, 1-PCO-65-82 and 2-PCO-65-82 from NA to normally closed - fail open. Also, add damper 2-PCO-65-80 to FSAR Table 9.3-8, page 2 of 4, as a normally closed -

fail open damper that receives ACAS Train A control air.

8. 8.Table 9.3-8 2-108-08 (cont.)

11. On FSAR Table 9.3-8, page 2 of 4, change the OP Mode - Failure Mode for dampers 1-PCO-65-89 and 2-PCO-65-89 from normally closed - fail closed to normally open - fail closed. Also, add dampers 1-PCO-65-88 and 2-PCO-65-88 to FSAR Table 9.3-8, page 2 of 4, as normally open - fail closed dampers that receive ACAS Train A control air.

12. Add a note to FSAR Table 9.3-8, page 4 of 4, to indicate dampers 1-PCO-65-80 and 2-PCO-65-80 are mechanically linked to dampers 1-PCO-65-88 and 2-PCO-65-88, respectively. Also, indicate in this note that dampers 1-PCO-65-82 and 2-PCO-65-82 are mechanically linked to dampers 1-PCO-65-89 and 2-PCO-65-89, respectively.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

13. Add valves 1-FCV-90-107, 1 -FCV-90-111, 1 -FCV 113 and 1-FCV-90-117 to FSAR Table 9.3-8, page 3 of 4, as valves supplied with ACAS Train A control air.

Also, add valves 1-FCV-90-108, 1-FCV-90-109, 1-FCV-90-110, 1-FCV-90-114, 1-FCV-90-115 and 1-

8.

FCV-90-116 to FSAR Table 9.3-8, page 3 of 4, as (cont.)

Table 9.3-8 valves supplied with ACAS Train B control air.

2-108-08

14. Add local panels 2-L-218A to FSAR Table 9.3-8, page 1 of 4, as a local panel supplied with ACAS Train A control air. Also, add local panel 2-L-929 to FSAR Table 9.3-8, page 1 of 4, as a local panel supplied with ACAS Train B control air.

1. Change "Regulatory Guide 1.168, Revision 1, February 2004" to read "Regulatory Guide 1.168, Revision 0, September 1997

9.

Table 7.1-1

2. Change "IEEE Std. 1012-1998" to read "IEEE Std.

2-108-09 1012-1986"

3. Change "IEEE Std. 1028-1997"to read "IEEE Std. 1028-1988"

1. Replace Section 15.2.4.1 with the following:

"Reactivity can be added to the core by feeding primary grade water into the RCS via the reactor makeup portion of the CVCS. Boron dilution is a manual operation under strict administrative controls with procedures calling for a limit on the rate and duration of dilution. The primary causes of an

10.

Section 15.2.4 inadvertent boron dilution event are the opening of the 2-108-10 Table 15.2-1 primary water control valve and failure of the blend system either by controller or mechanical failure. The CVCS, including the-blend system is designed to limit, even under various postulated failure modes, the potential rate of dilution to a value which, after indication through alarms and instrumentation, provides the operator sufficient time to correct the situation in a safe and orderly manner.

E11-7

ENCLOSURE 1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number Inadvertent dilution from reactor water make-up can be readily terminated by closing the control valve. All expected sources of dilution may be terminated by closing isolation valves FCV-62-128 and FCV-62-144.

In order for makeup water to be added to the RCS at pressure, at least one charging pump must be running in addition to a primary makeup water pump. The rate of addition of unborated makeup water to the RCS when it is not at pressure is limited by the capacity of the primary water makeup pumps. Normally, only one primary water supply pump is operating while the other is on standby. With the RCS at pressure, the maximum delivery rate is limited by the control valve.

The boric acid from the boric acid tank is blended with primary grade water in the blender and the composition is determined by the preset flow rates of Section 15.2.4 boric acid and primary grade water on the control

10.

Table 15.2-1 board. In order to dilute, two separate operations are 2-108-10 required:

(1) The operator must switch from the automatic makeup mode to the dilute or alternate dilute mode.

(2) The start handswitch must be actuated. Failure to carry out either of these actions prevents the initiation of dilution. During normal operation the operator may add borated water to the RCS by blending boric acid from the boric acid storage tanks with primary grade water. This requires the operator to determine the concentration of the addition and setting the blended flow rate and the boric acid flow rate. The makeup controller will then limit the sum of the boric acid flow rate and primary water flow rate to the blended flow rate.

E1-8

ENCLOSURE I WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number 10.

(cont.)

Section 15.2.4 Table 15.2-1 Primary water inadvertently added to the RCS via the charging system is a mass addition to the RCS. As primary water is added through the charging system, an equal amount of water is no longer being removed from the VCT. When this occurs, VCT level will increase. The system is designed to automatically divert water to the hold-up tank to prevent overfilling the VCT. A signal from redundant high VCT level switches result in a main control room alarm and lighting of an annunciator window. The alarm setpoint is the same level as when the divert valve starts to open. The divert valve will not fully open until VCT level reaches 93%. Thus letdown flow will not be diverted to the holdup tank prior to the alarm on high VCT level. The FSAR for Unit 1 and U2 have described the high flux at shut down alarm and stated that the alarm set point is maintained within 1/2 decade of the source flux level. Following reactor shutdown, when in the hot standby, hot shutdown, or subsequently the cold shutdown condition, and once below the P-6 interlock setpoint, and 104 counts per second, the high flux at shutdown alarm setting is automatically adjusted downward as the count rate reduces. The actual setpoint is maintained at 1.3 times background rather than at five times background as currently described in the FSAR. In addition to the high VCT level alarm set at 63% level, there is a high-high level alarm if the VCT level exceeds 93%.

2.

For Section 15.2.4.2.1, modify as follows:

a. Insert "s" after dilution in the first sentence.

b.

Insert the phrase, ""cold shutdown, hot shutdown, hot standby," between the words," refueling" and "startup" of the first sentence.

c.

Replace the word "is" with the word, "are" in the first sentence.

3.

After Section 15.2.4.2.2, insert new Sections 15.2.4.2.3, 15.2.4.2.4, 15.2.4.2.5 as follows:

"15.2.4.2.3 Dilution During Cold Shutdown In this mode, the plant is being taken from a long-term mode of operation (refueling) to a short term mode of operation (hot shutdown). Typically, the plant is 2-108-10 E11-9

ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number maintained in the cold shutdown mode when reduced RCS inventory is necessary or ambient temperatures are required. The water level can be dropped to the mid-plane of the hot leg for maintenance work that requires the steam generators to be drained.

Throughout the cycle, the plant may enter cold shutdown if reduced temperatures are required in containment or as the result of a Technical Specification action statement. The plant is maintained in cold shutdown at the beginning of the cycle for start-up testing of certain systems. Dilution with reduced inventory cannot occur due to administrative controls which isolate the RCS from the potential source of diluted water prior to terminating flow from the RCPs and initiating flow via the RHR system. Conditions used for the analysis are as follows:

(1) At operating temperature (between 68°F and 10 Section 15.2.4 2000 F) and pressure, dilution flow is limited by the (cont.)

Table 15.2-1 maximum delivery capacity of one primary water 2-108-10 pump, 150 gpm.

(2) A minimum RCS water volume of 8,451 ft3. This corresponds to the active RCS volume excluding the pressurizer and the reactor vessel upper head.

(3) The initial boron concentration is 1,302 ppm, which corresponds to a concentration that maintains the reactor subcritical by the required shutdown margin (1.0 %Ap), assuming all RCCAs inserted except for the most reactive RCCA.

(4) A conservative, maximum boron concentration at which the reactor will return to critical with all RCCAs inserted except for the most reactive RCCA, at the most reactive cycle burnup time without xenon, is 1,194 ppm. The 108 ppm change from the initial condition noted above is a conservative minimum value.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number (5) Operator notification occurs via a high VCT level alarm with a setpoint of 68.1% span (including uncertainties). The alarm time is a function of the minimum letdown flow rate, which is 75 gpm."

15.2.4.2.4 Dilution During Hot Shutdown In this mode, the plant is being taken from a short-term mode of operation (cold shutdown) to a long term mode of operation (hot standby). Typically, the plant is maintained in the hot shutdown mode to achieve plant heatup before entering hot standby. The plant is maintained in this mode at the beginning of cycle for startup testing of certain systems. Throughout the cycle, the plant will enter hot shutdown if reduced temperatures are required in containment or as a result of a Technical Specification action statement.

In hot shutdown, primary coolant forced flow is provided by at least one Reactor Coolant Pump (RCP). Conditions used for the analysis are as follows:

10 Section 15.2.4 (1) At operating temperature (200°F to 350 0F) and 2-108-10 pressure, dilution flow is limited by the maximum delivery capacity of one primary water pump, 150 gpm.

(2) A minimum RCS water volume of 8,451 ft3 This corresponds to the active RCS volume excluding the pressurizer and the reactor vessel upper head.

(3) The initial boron concentration is 1,348 ppm, which corresponds to a concentration that maintains the reactor subcritical by the required shutdown margin (1.6%Ap), assuming all RCCAs inserted except for the most reactive RCCA.

(4) A conservative, maximum boron concentration at which the reactor will return to critical with all RCCAs inserted except for the most reactive RCCA, at the most reactive cycle burnup time without xenon, is 1,165 ppm. The 183 ppm change from the initial condition noted above is a conservative minimum value.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number 10.

(cont.)

Section 15.2.4 Table 15.2-1 (5) Operator notification occurs via a high VCT level alarm with a setpoint of 68.1% span (including uncertainties). The alarm time is a function of the minimum letdown flow rate, which is 75 gpm.

15.2.4.2.5 Dilution During Hot Standby In this mode, the plant is being taken from one short-term mode of operation (hot shutdown) to another (startup). The plant is maintained in hot standby at the beginning of cycle for startup testing of certain systems and to achieve plant heatup before entering the startup mode and going critical. During operation of the cycle, the plant will enter this mode following a reactor trip or as the result of a Technical Specification action statement. During hot standby, all reactor pumps may not be in operation. In an effort to balance the heat loss through the RCS and the heat removal of the steam generators, one or more pumps may be shut off to decrease heat input into the system. The more limiting hot standby dilution scenario is with the control rods not withdrawn and the reactor shut down by boron to the Technical Specifications minimum requirement for this mode.

Conditions used for the analysis are as follows:

(1) At operating temperature (350°F to 557°F) and pressure, dilution flow is limited to 160 gpm by the high charging flow alarm (including uncertainties).

Any flow rate greater than this will result in an immediate alarm and ample operator action time.

(2) A minimum RCS water volume of 8,451 ft3. This corresponds to the active RCS volume excluding the pressurizer and the reactor vessel upper head.

(3) The initial boron concentration is 1,300 ppm, which corresponds to a concentration that maintains the reactor subcritical by the required shutdown margin (16%Ap), assuming all RCCAs inserted except for the most reactive RCCA.

2-108-10 E1-12

ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number (4) A conservative, maximum boron concentration at which the reactor will return to critical with all RCCAs inserted except for the most reactive RCCA, at the most reactive cycle burnup time without xenon, is 1,100 ppm. The 200 ppm change from the initial condition noted above is a conservative minimum value.

(5) Operator notification occurs via a high VCT level alarm with a setpoint of 68. 1% span (including uncertainties). The alarm time is a function of the minimum letdown flow rate, which is 75 gpm.

4. Renumber existing Section 15.2.4.2.3 as 15.2.4.2.6.

5.

For new Section 15.2.4.2.6 (formally 15.2.4.2.3),

replace the word, "assumed" with "used" in the last sentence of the first paragraph.

6.

For new Section 15.2.4.2.6, Item 1, modify to read as follows:

10.

Section 15.2.4 2-108-10 (cont.)

Table 15.2-1 "At operating temperature and pressure, dilution flow is limited to 235 gpm."

7.

For new Section 15.2.4.2.6, Item 3, modify to read as follows:

"The initial boron concentration is 1,600 ppm, which corresponds to a critical, hot zero power condition with the control rods at the rod insertion limits providing a shutdown margin of 1.6%."

8.

For new Section 15.2.4.2.6, Item 4, modify to read as follows:

"The critical boron concentration following reactor trip is 1,400 ppm, which is a conservative maximum value corresponding to a hot zero power condition with, all RCCAs inserted except for the most reactive RCCA at the most-reactive cycle burnup time without zenon.

The 200 ppm change from the initial condition noted above is a conservative minimum value."

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

9. Renumber existing Section 15.2.4.2.4 as 15.2.4.2.7.

10. For new Section 15.2.4.2.7 (formally 15.2.4.2.4),

replace the word, "assumed" with "used" in the last sentence of the first paragraph.

11. For new Section 15.2.4.2.7, Item 1, modify to read as follows:

"At operating temperature and pressure, dilution flow is limited to 235 gpm."

12 For new Section 15.2.4.2.7, Item 3, modify to read as follows:

"The initial boron concentration is 1,500 ppm, which corresponds to a hot full power condition with the control rods at the rod insertion limits providing a shutdown margin of 1.6%."

13. For new Section 15.2.4.2.7, Item 4, modify to read as follows:

"The critical boron concentration following reactor trip

10.

Section 15.2.4 is 1,250 ppm, which is a conservative maximum value (cont.)

Table 15.2-1 corresponding to a hot zero power condition with all 2-108-10 RCCAs inserted except for the most reactive RCCA at the most-reactive cycle burnup time without zenon.

The 250 ppm change from the initial condition noted above is a conservative minimum value."

14. Replace Section 15.2.4.3.3, with the following:

"In cold shutdown, hot shutdown and hot standby, the reactor operators are relied upon to detect and recover from an inadvertent boron dilution event.

Numerous alarms from the chemical and volume control system, the reactor makeup water system and the nuclear instrumentation system are available to provide assistance to the reactor operator in the detection of an inadvertent boron dilution event. In the analyses of the event initiated from these modes, the high Volume Control Tank (VCT) level alarm with an analysis setpoint of 68.1% span is modeled and provides the operator with timely indication that an event is occurring. The analyses have demonstrated that the reactor operators have at least 15 minutes in which to initiate actions to terminate the dilution and initiate boration of the RCS from the time of the alarm to loss of shutdown margin."

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

15. For Table 15.2-1, insert new items 1,2, and 3 as follows:

Dilution Dilution Begins 0

During High VCT Level 820

1.

Cold Alarm Sounds Shutdown -

Shutdown Margin is

-2186 RCS filled Lost Dilution Begins 0

Dilution High VCT Level 820

2.

During Hot Alarm Sounds Shutdown Shutdown Margin is

-3552 Lost Dilution Begins 0

Dilution High VCT Level 820 3

During Hot Alarm Sounds Standby Shutdown Margin is 3663 Lost

16. Renumber existing table items 1 and 2 as 4 and 5, respectively.

17. Revise new Item 5 (formally Item 2) as follows:

10.

(cont.)

Section 15.2.4 Table 15.2-1 2-108-10 5.

Dilution During Full Power Operation

a. Automatic Reactor Control Dilution Begins 0

Shutdown Margin is Lost

-2057 Dilution Be-qins 0

b. Manual Reactor Control Reactor trip setpoint reached for over 77.5 temperature AT Rods begin to fall into core Shutdown Margin is Lost (If dilution continues after trip)

-2057 El-15

ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

1. Replace, on Page 1.6-4 for the third item from the top of the page, an updated list of reports associated with the Power Distribution Monitoring System (PDMS) that will be used in WBN Unit 2 Operation with the following:

"Beard, C. L. and Morita, T. "BEACON: Core Monitoring and Operations Support System", WCAP-12472-P-A (Proprietary), August 1994, Addendum 1-A, January 2000, Addendum 2 -A, April 2002 and WCAP-12473-A (Non-proprietary), August 1994."

2.

On page 4.3-5, perform the following:,

a. Under Section 4.3.1.6 in..the third paragraph in the first sentence, change "the Technical Sections Specifications." to "the COLR."

1.6 43

b. Under Section 4.3.1.6 in the third paragraph in the

11.

4.4 third (last) sentence, change "as described in the 2-108-11 7..7 COLR" to "as specified in the Technical 14.2 Specifications."

15.3

3.

On Page 4.3-9, clarify the term FNu in terms of its use to support the Power Distribution Monitoring System (PDMS) used in WBN Unit 2 by deleting the words" with a full core flux map" and adding to the end "and as described in Reference [11] for the power distribution monitoring system."

4. On page 4.3-14, change the wording "full core map" to "power distribution measurement" in the fourth paragraph, second sentence.

5.

On page 4.3-20, in the fifth paragraph in the third sentence, change "(-681F)" to "(- 681F)." This is replacing the negative sign with an approximately sign.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

6. On page 4.3-28 perform the following:

a.

In the third paragraph and first sentence, change "in the spent fuel storage rack uses" to "in the new fuel racks uses"

b.

In the fourth paragraph and first sentence, change "the fresh fuel racks" to "the new fuel racks".

c.

In the fourth paragraph and second sentence, change "the fresh fuel rack" to "the new fuel rack".

d.

In the fifth paragraph and fourth sentence, change "the fresh fuel storage racks" to "the new fuel racks".

e.

In the fifth paragraph and fifth sentence, change "fresh fuel rack" to" new fuel rack".

Sections

7. Changes are being made to the second paragraph in 1.6 Section 4.4.2.4 on page 4.4-13. In the second 4.3 sentence the words "maps are taken" is being replace (cont.)

4.4 with the words" power distribution measurements are 2-108-11 7.7 obtained", The third sentence "Incore instrumentation 14.2 data is sent to the Power Distribution Monitoring 15.3 System (PDMS) once each minute and is compared to the calculated power distribution information," is being deleted and replaced with the following "Each of these measurements are reviewed for deviations from the expected power distribution,"

8.

In the second paragraph on page 4.4-14, the word "maps" is being replaced with the term "power distribution measurements,"

9. On page 4.4-31 under Section 4.4.4.2 in first paragraph, change "conservative" to "the" and add "that" between "factors" and "are" and add to end of sentence ", are bounding.

This change should then read "ensure that the peaking factors that are used in the core thermal and hydraulic analysis are bounding."

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

10. In section 7.7.1.9, on page 7.7-19, remove the space at the beginning of the paragraph. Then replace the term "core flux map" with the term "the incore power distribution measurement."

11. In section 7.7.1.9.2 on page 7.7-20, change the wording "flux mapping system" to "Power Distribution Monitoring System". Add to the end of the second paragraph, for the start of another paragraph the following words "The thimbles are closed at the leading ends and dry inside. Mechanical seals between the retractable thimbles and the conduits are provided at the seal table and serve as the pressure barrier between the reactor water pressure and the atmosphere. During reactor operation, the retractable thimbles are stationary. They are extracted downward from the core during refueling to avoid interference within the core. A space above the seal table is Sections provided for the retraction operation."

1.6

12. On page 7.7-20 add new Section 7.7.1.9.4 Power

11.

4.4 Distribution Monitoring System (PDMS) 2-108-11 (cont.)

4.47-081 (cn7 The PDMS can be used to obtain power distribution 14.2 measurements using the fixed IITAs. The PDMS 15.3 receives on-line values for fixed incore detector data, reactor power, RCS cold leg temperatures, and control bank positions, coupled with a three dimensional analytical model to yield a continuously measured three-dimensional power distribution.

On a once-per-minute basis, the Integrated Computer System transfers the values of computer points needed as input to the PDMS computer. The PDMS software is the Best Estimate Analyzer for Core Operations Nuclear (BEACON), which is described in References [18] and [19]. Detailed information on the core power distribution, including trends, may be obtained from the BEACON software. Although information is fed back to the Integrated Computer System in terms of computer point values, the PDMS does not drive any control room indications or annunciators.

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ENCLOSURE1I WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

13. On Page 7.7-29 under References for Reference 4, Change to read as follows:

4 "Westinghouse Incore Information Surveillance &

Engineering (WINCISE) System Technical Manual, Watts Bar Unit 2" NO-WBT-002 Rev. 1.

14. On Page 7.7-30, add reference 12, clarify two typos in 16 and 17 and add new reference 18.

Insert the following:

"12 System Description Document Number N3 4003, "Incore Instrumentation System."

16 Change "Westinghous" to "Westinghouse" 17 Change "CERPI Systm" to "CERPR System" Sections 1.6 Insert the following:

4.3 1o.

4.4 18 Beard, C.L. and Morita, T. "BEACON: Core 2-108-11 (cont.)

7.7 Monitoring and Operations Support System, 14.2 WCAP-12472-P-A (Proprietary), August 1994, 15.3 Addendum 1 - A, January 2000, Addendum 2 - A, April 2002 and WCAP-12473-A (Non-proprietary),

August 1994. "

15. On page 14.2-19, adding a new exception after item (k) and number as item (I):

(I) Appendix A, subparagraph 4.a WBN will not measure a boron reactivity coefficient using the Advanced Digital Reactivity Computer (ADRC) during low power physics testing. Overall core reactivity will be measured during low power physics testing.

16. On page 14.2-19, on this page and pages 14.2-20 thru 14.2-22, change the alphanumeric listings to reflect the addition of the exception.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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17. On page 14.2-32 under section 14.2.10.3, in the second paragraph, change "leaving the last withdrawn control bank inserted far enough in the core to provide effective control when criticality is achieved." to "until all shutdown and control banks are at the full ARO configuration.

18. On page 14.2-33, in the second paragraph, change "will be plotted" to "will be evaluated".

19. On page 14.2-33, in the fourth paragraph, delete the following statement "or by rod withdrawal following boron dilution."

20, On page 14.2-33 under section 14.2.10.4 in the last paragraph and the last sentence, change "isothermal temperature coefficient, differential boron Sections concentration reactivity worth, and critical boron 1.6 concentrations." to "isothermal temperature coefficient 11 4.3 and the critical ARO, hot zero power boron 4.4 concentration."

2-108-11 (cont.)

7.7 14.2

21. On page 14.2-129 under acceptance criteria, deleting 15.3 item 2.

2. If a statistical evaluation is used as a response check following an eight hour delay, the statistical reliability factor based on a ten count observation is between 0.53 and 1.48.

22 On page 14.2-129, under acceptance criteria, change item (3) number to (2).

23. On page 14.2-138, under prerequisites, change entire sentence to read:

"Containment pressurization tests are complete and Incore Instrumentation System is capable of having simulated signals injected at the seal table in order to generate a simulated power distribution measurement."

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

24. On page 14.2-138 under Test Method change the words" a flux map" to "a power distribution measurement" and change power level of "20% RTP" to "25% RTP".

Should read as "and the ability to generate a power distribution measurement is simulated by injecting signals into the Incore Instrumentation System detector cables at the seal table. After connecting the cables to the IITAs, and achieving at least 25% RTP, a power distribution measurement is produced using reactor core neutron power.

25. On page 14.2-138 under acceptance criteria, change the words "simulating and IITA" to "simulating an IITA, and change power level of "20% RTP" to "25% RTP" and change the words "a core flux map is computed....

to "a core power distribution measurement is obtained"

26. On page 14.2-148 under the prerequisites section, for Sections item (3), change "2 cps" to "0.5 cps".

1.6 4.3 Under test method section, in the first sentence, (cont.)

4.4 change the words "until approximately 100 pcm worth 2-108-11 7.7 remains inserted." To "until an All Rods Out (ARO) 14.2 configuration is reached. Under test method section, 15.3 for rest of this section replace with wording "RCS boron dilution is commenced at a rate of < 1000 pcm per hour with the RCS boron concentration being sampled at approximately 30 minute intervals. When the Inverse Count Rate Ratio (ICRR) is approximately 0.3, dilution rate is diminished by approximately one third of the original rate. Dilution is continued until the reactor is slightly critical or the maximum projected dilution volume has been added. Then dilution is terminated and the RCS is allowed to mix. If the reactor is slightly critical, then control bank D will be inserted to control and maintain the reactivity status of the reactor. If criticality is not achieved during mixing, RCS sampling will be used to determine the reactivity state point of the reactor and any additional dilution volume necessary to reach the projected dilution volume. Dilution will re-commence until the reactor is slightly critical or the dilution volume has been added, whichever happens first. During dilution, evaluations of ICRR versus dilution water additions are maintained.

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ENCLOSURE1I WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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27. On page 14.2-149 under test method section, replace the entire section with the following:

"Control bank D is withdrawn to achieve a positive reactivity increase. Flux level and plant conditions are monitored and noted when nuclear heating is observed. Typical indications of nuclear heating are a decrease in reactivity and an increase in RCS temperature. Control bank D is then inserted to achieve negative reactivity. At the point of adding nuclear heat, the zero power physics testing range is then determined and set by the reactivity computer as needed based on the appropriate testing to be Sections performed. Control bank D is then adjusted to reduce 1.6 nuclear flux within the necessary testing range."

4.3

11.

4.3 Under acceptance criteria change to read: "The zero 2-108-11 (cont.)

4.4 power physics testing range has been determined 14.2 such that the reactivity feedback from nuclear heating 15.3 does not compromise the measurements.

15.3

28. On page 14.2-150, under the prerequisites section for item (2), delete the words "along with an X-V recorder/plotter' Under Test method replace everything after the first sentence to read "Reactivity is monitored and reactivity parameters versus temperature changes are determined. The isothermal temperature coefficient value is determined. From this data, the value of the moderator temperature coefficient is then determined."

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ENCLOSURE 1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

29. On page 14.2-151, under the objective section, change the sentence to read:

"To verify the design integral rod worths of the control and shutdown banks and the design All Rods Out (ARO) critical boron concentration.

Under the test method section, replace with the following "The integral worth of all control and shutdown banks will be measured with the reactivity computer, using the Dynamic Rod Worth Measurement (DRWM) technique. The ARO critical boron endpoint will be determined from data obtained during rod worth measurements."

Sections 1.6 Under acceptance criteria section for item (2) delete 4.3 the "s" on end of the word concentrations. This 1o.

4.4 should read "critical boron concentration at hot zero" 2-108-11 (cont.)

7.7 14.2 Under acceptance criteria section for item (2) change 15.3 "are" to "is".

Under acceptance criteria section for item (3), delete this criterion.

30. On page 14.2-152, under the test method section, in the first sentence, change the words "by measuring the boron concentration near the all rods out, hot zero power xenon free critical condition and correcting reactivity by endpoint measurement techniques." to" by determining the ARO boron concentration at hot zero power, xenon free critical conditions. This measurement also confirms the reactivity measurement requirements of Technical Specifications are met."

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

31. On page 14.2-153, under prerequisites section for item (1) change to read "The reactor is critical with reactor power stable at the test plateau.

Under prerequisites section for item (2) change to read "The Power Distribution Monitoring System (PDMS) is operable and the Integrated Computer System (ICS) is available to gather power distribution measurement data.

Under test method section, change to read" Reactor power is stabilized at greater than or equal to 25%

Rated Thermal Power (RTP) and a power distribution Sections measurement is obtained using the PDMS. The 1.6 measurement is obtained with control rods controlling 4.3 Axial Flux Difference (AFD) within the target band.

1.

4.4 Power distribution measurement information is then 2-108-11 (cont.)

7.7 processed and calculations are performed. These 14.2 measurements are repeated as a minimum at 15.3 approximately 50%, 75% and 100% RTP.

Under acceptance criteria section change item (1) as follows:

Add "fuel" in front of loading, change "or" in front of enrichment to a " comma" and change "versus" to "placement of." This change should read "Hot channel factors are less than or equal to design safety limits which provide a check for potential errors in fuel loading, enrichment of fuel assemblies, placement of lumped poison elements, and to check for mispositioned or uncoupled control rods.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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32. On page 15.2-10, for a dropped RCCA or RCCA bank being detected, change item (2) as below and delete item (6).

(2) Asymmetric power distribution as seen on:

A. the Out of Core Neutron Detectors, B.

the Core Exit Thermocouples, C. the Power Distribution Monitoring System (PDMS);

Similarly, for misaligned RCCAs being detected, change item (1) as below and delete item (4).

Sections (1) Asymmetric power distribution as seen on:

1.6 11 4.3 A.

the Out of Core Neutron Detectors, (cont.)

4.4 B.

the Core Exit Thermocouples, 2-108-11 7.7 C. the Power Distribution Monitoring System 14.2 (PDMS);

15.3

33. On page 15.3-6, in the second paragraph and the third sentence change "Power Distribution Monitoring System" to "Power Distribution Monitoring System 11"."

In other words, the super script [17] correctly references the proper reference material over on page 15.3 -14.

34. On page 15.3-14, add a reference (17) to support the use of PDMS (17) Beard, C.L. and Morita, T.

"BEACON: Core Monitoring and Operations Support System ", WCAP-12472-P-A (Proprietary), August 1994, Addendum 1 - A, January 2000, Addendum 2 -

A, April 2002 and WCAP-12473-A (Non-proprietary),

August 1994.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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1.

On Page 2.3-15 (Al 07) correct typographical errors in first paragraph of Section 2.3.4.1 by replacing "Waits" with "Watts" in three places.

2.

On page 2.3-17 (A107), remove space between "61" and "b" in the second paragraph of Section 2.3.4.2.

3.

On page 2.3-17 (A107), replace "1992" date with "1991" date in the last line of the last paragraph just prior to table of information.

4. Combine information at the bottom of Page 2.3-17 Sections (A107) with the information at the top of Page 2.3-18 2.3 and correct data alignment issues within the table.

7.2 2-108-12 7.5

5.

For Table 7.2-2 (A107), Item P-7, delete the phrase, 12.3 "pressurizer low pressure, and pressurizer high level" 15.2 from the table.

6.

On Page 7.5-34 (Al 07), for Item 11 of Table 7.5-2, replace "1 0-4 to 10-9" with "10-9 to 10-4"

7.

On Page 12.3-5 (A107), replace "radiation protection,"

with "Radiation Protection."

8.

On Page 15.2-1 (A107), insert new Item 15 as follows:

"(15) Chemical and Volume Control System Malfunction During Power Operation".

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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1. On Page 2.4-1, change value in the fourth paragraph of Section 2.4 for the probable minimum flow past the site from "2000" cfs to "3,200" cfs.

2.

Under Section 2.4.1.2, revise value of 208,400 to 214,000 in the second sentence of the 14th paragraph.

3.

In the last sentence of the first paragraph of Section 2.4.2.1, replace the phrase, "under present day regulation reached Elevation 696.95 at the site on March 17, 1973, with the phrase, "elevation of the site under present day regulation would be approximately elevation 698 on a maximum tailwater elevation of 698.23 at Watts Bar dam located just upstream.

4. Insert the word, "wind," between the words "maximum" and "waves" in the second sentence of the fifth paragraph of Section 2.4.2.2.

5.

In the third sentence of the fifth paragraph of Section 2.4.2.3, replace the phrase, "site grading and drainage

13.

Section system for," with "yard site grading and drainage 2-108-13 2.4 system for flood studies for."

6.

In the first sentence of the 15th paragraph of Section 2.4.2.3, replace superscript for reference 4 to reference 35.

7 Insert word, "and" between "Fontana" and "Hiwassee" in the third paragraph of the second paragraph of Section 2.4.3.

8.

Delete the word, "storm" from the second sentence of the second paragraph of Section 2.4.3.1

9.

Insert phrase "in area." after "3,000 square miles" in the next to last sentence of the first paragraph of Section 2.4.3.1.

10. Delete "Hydrometeorological" from the last sentence of the fifth paragraph of Section 2.4.3.1.

11. Delete "orographically fixed" from the first sentence of the last paragraph of Section 2.4.3.1.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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12. In the last sentence of the third paragraph of Section 2.4.3.3, replace the phrase, "reservoirs were routed,"

with "routings were made."

13. In the second sentence of the fifth paragraph of Section 2.4.3.3, delete the phrase, "as of Amendment 98."

14. Delete the last two sentences of the fifth paragraph of Section 2.4.3.3, which read as follows: "Permanent improvements to raise the height of embankments of these four dams are being evaluated. Section 2.4.3 will be updated following completion of the installation of these improvements."

15. Replace the cross section number "33" with "25" in the fourth sentence of the sixth paragraph of Section 2.4.3.3.

16. Replace the phrase, "with cross section spacing of about 0.25 mile," within average cross-section spacing of about 0.18 miles" in the last sentence of the

13.

Section seventh paragraph of Section 2.4.3.3.

2-108-13 (cont.)

2.4

17. Replace the phrase, "unsteady flow," to "steady state HEC-RAS," in the first sentence of the 10th paragraph of Section 2.4.3.3.

18. Insert "Watts Bar" between "long" and "Reservoir" in the second sentence of the tenth paragraph of Section 2.4.3.3.

19. Replace the acronym, "SOCH," to "HEC-RAS steady state," in the second sentence of the 10th paragraph of Section 2.4.3.3.

20. Insert "Chickamauga" between "long" and "Reservoir" in the second sentence of the eleventh paragraph of Section 2.4.3.3.

21. Revise the value for sections from "57" to "53" in the second sentence of the tenth paragraph of Section 2.4.3.3.

22. Insert "or SOCH," between the acronym, "HEC-RAS,"

and the word, "models" into the last sentence of the 12th paragraph of Section 2.4.3.3.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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23. Insert the phrase, "up to the point the operating deck is flooded" into the fourth sentence of the 13th paragraph of Section 2.4.3.3.

24. Delete the phrase, 'upstream of Watts Bar Nuclear Plant," from the second sentence of the second paragraph of Section 2.4.3.4.

25. Delete the extra, "tailwater,' from the first sentence under the heading, "Concrete Section Analysis," of the Section 2.4.3.4.

26. Insert the following subsections after the "Spillway Gates" subsection contained within Section 2.4.3.4:

"Waterborne Objects Consideration has been given to the effect of waterborne objects striking the spillway gates and bents supporting the bridge across Watts Bar Dam at peak water level at the dam. The most severe potential for damage would be by a barge which has been torn loose from its moorings and floats into the dam.

13.

Section Should the barge approach the spillway portion of the 2-108-13 (cont.)

2.4 dam end on, one bridge bent could be failed by the barge and two spillway gates could be damaged and possibly swept away. The loss of one bridge bent will not collapse the bridge because the bridge girders are continuous members and the stress in the girders will be less than the ultimate stress for this condition of one support being lost. Should two gates be swept away, the nape of the water surface over the spillway weir would be such that the barge would be grounded on the tops of the concrete spillway piers and provide a partial obstruction to flow comparable to unfailed spillway gates. Hence the loss of two gates from this cause will have little effect on the peak flow and elevation. Should the barge approach the spillway portion broadside, two and possibly three bridge bents could be failed. For this condition the bridge would collapse on the barge and the barge would be grounded on the tops of the spillway piers. This would be probable because the approach velocity of the barge would be from 4 to 7 miles per hour and the bottom of the barge would be about 6 inches above the tops of the piers. For this condition the barge would be grounded before striking the spillway gates because the gates are about 20 feet downstream from the leg of the upstream bridge bents.

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ENCLOSUREI WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number Lock Gates The lock gates at Fort Loudoun, Watts Bar, and Chickamauga were examined for possible failure with the conclusion that no potential for failure exists because the gates are designed for a differential hydrostatic head greater than that which exists during the probable maximum flood."

27. Replace the phrase, "For the Watts Bar FSAR," in the first sentence of the fourth paragraph of Section 2.4.3.6 with the phrase, "For the Watts Bar plant site,"

28. Revise footnote reference from "38" to "37" in the second sentence of the fourth paragraph of Section 2.4.4.

29. Insert the phrase, "and other instrumentation has been added since." to the next to last sentence of the last paragraph of Section 2.4.4.

30. Insert the phrase, "for these loading conditions." after

13.

Section the word, "embankment," at the end of the last (cont.)

2.4 sentence of the paragraph prior to the subheading, "Flood Routing."

31. Insert the word, "postulated" between the words, "the" and "SSE" in the second sentence of the first paragraph of subsection, "Flood Routing."

32. Insert the word, "Dam" in two places after the phrase, "Watts Bar" in the first and second sentences of the fourth paragraph under the heading, "Multiple Failures," of Section 2.4.4.1.

33. Delete footnote "40" from the second sentence under the heading "Fontana Dam," of Section 2.4.4.1.

34. Replace the phrase, "football-shaped," with "flattened oval-shaped," in the first sentence of fifth paragraph under the heading, "Multiple Failures," of Section 2.4.4.1.

35. Replace the word, "each" with "reach" in the first sentence of the 10th paragraph under the heading of "Multiple Failures" of Section 2.4.4.1.

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36. Insert the phrase, "using the revised amplification factors," between the words "reevaluation" and "was' in the first sentence of the first paragraph under the heading, "Watts Bar Dam, of Section 2.4.4.1.

37. Replace the word, "postulated" with "assumed" in the first sentence of the fourth paragraph under the heading, "Fort Loudoun Dam," of Section 2.4.4.1

38. Replace the phrase, "SSE Dam failures" with "SSE dam failure combinations" in the first paragraph under the heading "Multiple Failures" after the "Cherokee" and "Douglas" headings of Section 2.4.4.1.

39. Delete the sentence that reads, "At least this most conservative assumption was used." from the third paragraph under the heading "Multiple Failures" after the "Cherokee" and "Douglas" headings of Section 2.4.4.1.

40. Correct the spelling of "respectively" in the next to last sentence of third paragraph under heading, "Multiple Failures," of Section 2.4.4.1.

13.

Section (cont.)

2.4

41. Replace Figure "2.4-76" with "Figure 2.4-90" in the last sentence of the tenth paragraph under heading, "Multiple Failures," of Section 2.4.4.1.

42. Delete the sentence that reads, "This is conservative."

from the tenth paragraph under the heading "Multiple Failures" after the "Cherokee" and "Douglas" headings of Section 2.4.4.1.

43. Delete the word, "Tellico" from the last sentence of the last paragraph of Section 2.4.4.1.

44. Replace the phrase, "where the dam was postulated to completely fail," with the phrase, "main river dams" in the third sentence of the first paragraph of Section 2.4.4.2.

45. Insert the phrase, "or SOCH" between the acronym, "HEC-RAS" and the word, "was" in the next to last sentence of the first paragraph of Section 2.4.4.2.

46. Add a space between "Plant" and 'Site" in the heading of Section 2.4.4.3.

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47. Replace maximum elevation value of "731.11" to "731.17" in the first sentence of the first paragraph of Section 2.4.4.3 and in the second sentence of the first paragraph of Section 2.4.14.10.

48. Add a space between "plant" and 'site" in the fifth paragraph of Section 2.4.7.

49. Replace the phrase, "TVA's Water Resources organization," with "TVA's River Operation (RO) organization" in the last sentence of the second paragraph of Section 2.4.10.

50. Correct typographical error by replacing "Wats Bar Nuclear Plant which show," with "Watts Bar Nuclear Plant shows" in the last paragraph of Section 2.4.11.

51. Insert the word, "Management" in between the words "Waste" and "Systems," in the first sentence of the first paragraph of Section 2.4.12.1.

13.

Section

52. Replace "Section 3.4, Sections 3.8.1 and 3.8.4" with 2-108-13 (cont.)

2.4 "Sections 3.4, 3.8.1 and 3.8.4," in the last sentence of the last paragraph of Section 2.4.14.

53. Replace "River Operations" with "RO" in the first sentence of the first paragraph of Section 2.4.14.8.1.

54. Insert the word, "system" between the words, "forecast" and "to" in the second sentence of the first paragraph of Section 2.4.14.8.2.

55. Relocate the phrase, "TVA hydro projects" in Item 3 of Section 2.4.14.9.2 to just after the number 21 and prior to list of TVA hydro projects beginning with "Watts Bar."

56. Replace the phrase, "(Sheet 1 B) and (Sheet 1C)" with

"(Sheets 1 B and 1C)"

57. Replace maximum elevation value of "731.11" to "731.17" in the first sentence of the first paragraph of Section 2.4.14.10.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

58. Revise the hour values from "36, 28, and 43" to "35, 28, and 44" in the first sentence of the second paragraph of Section 2.4.14.10.

59. Correct typographical error by replacing "fiber-options network," to "fiber-optics network.

60. Delete References 1, 2, 7 through 13, 22, and 31 through 33.

61. Addressed capitalizing building names or structures.

62. Added ".0" to certain elevations (several places)

63. Added "," separators to numbers great that 1000.

64. Added commas where needed.

13.

Section

65. Replace "and" with "or" in the last sentence of the third 2-108-13 (cont.)

2.4 paragraph of Section 2.4.14.9.3.

II. Table Changes

1. For Table 2.4-1, insert the number "40,000" into the Use (MGD) for Watts Bar Nuclear Plant. Revise ###

note to read as follows: Unit 2 is not in operation at this time. When operation maximum combined intake will be -115 million gallons per day."

IIl. Figure Changes

1. Delete Figure 2.4-61

2.

Delete Figure 2.4-62

3.

Delete Figure 2.4-63

4.

Delete Figure 2.4-69 E1-33

ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

1. For Section 4.3.1.3, Page 4.3-3; the calorimetric error discussed in this section was increased to 2.0% from 0.6%. The 0.6% value is an appropriate post-MUR uncertainty. Since the Watts Bar Unit 2 has not yet undergone the planned MUR, this number is to be consistent with the current licensing basis.

2.

For Section 4.3.1.4, Page 4.3-4, replace the phrase "45 inches per minute and" with "limited such that," in the second sentence under the heading "Discussion."

3.

For Section 4.3.1.6, Page 4.3-5; replace "Technical Specification" with "COLR" in the first sentence of the third paragraph of the section. In addition, replace the phrase, "as describe in the COLR," with the phrase, "as specified in the Technical Specifications,"

4.

For Section 4.3.2. 1, Page 4.3-6, add the following

.Section statement at the end of third paragraph: "The first

14.

4.3 cycle design of Watts Bar Unit 2 is not impacted by 2-108-14 these burnup-induced variances."

5.

For Section 4.3.2.2. 1, Page 4.3-8, move the last line that starts with "FQ to the beginning of Page 4.3-9.

Correct formatting issue involving "= Maximum kW/ft/Average kW/ft" at the top of the page.

6.

For Section 4.3.2.2.1, Page 4.3-9, insert last line from previous page 4.3-8 (Item 5 above). Delete the phrase, "with a full core flux map" and insert the following: "and as described in Reference [11] for the power distribution monitoring system." at the end of the line beginning with "F Nu =... "

7.

For Section 4.3.2.2.1 Pg. 4.3-9; the statements pertaining to "densification effects" are deleted, as is the correction factor, S(Z), as it is no longer used in the calculation FQ. The densification factor was also removed from the eauation for FQ.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

8.

For Section 4.3.2.2. 1, Page 4.3-9, Correct formatting issue involving "= Maximum kW/ft/Average kW/ft" at the bottom of page.

9.

For Section 4.3.2.2.2, Page 4.3-10, replace "one-eighth," with "one quarter" in the seventh line of the first paragraph,

10. For Section 4.3.2.2.5, Pg 4.3-12; delete line return to allow the phrase beginning with "axial power... to finish the sentence.

11. For Section 4.3.2.2.5, Pg. 4.3-14

a.

Delete the phrase, "allowed axial xenon distribution which, in turn, are used to calculate axial" from the first sentence of the first paragraph at the top of the page.

b.

Replace the second sentence of the first paragraph at the top of the page with the following: "For a RAOC analysis, however, a reconstruction model described in Reference [37]

14.

Section is used to create allowed axial xenon distributions 2-108-14 (cont.)

4.3 covering the wider Al power operating space allowed with RAOC operation. The xenon distributions are then used to create axial power distributions in both normal and Condition II accident conditions.

c.

In the first line of the third paragraph of this page, correct typographical error by replacing "H" with "x" indicating the multiplication symbol between "FQ(z)" and Power within the parentheses

12. For Section 4.3.2.2.5, Page, 4.3-14; the use of the term "full core map" was exchanged for "power distribution measurement". This change is consistent with the proposed changes presented in Reference 2.

13. For Section 4.3.2.2.5, Page 4.3-15, delete the phrase, "and densification effects" from the last sentence of the third paragraph of this page.

14. For Section 4.3.2.2.5, Page 4.3-17, in the first and second paragraphs, replace Category A, B, C. D with Category 1, 2, 3, 4 respectively.

+/- ______________________________________________________

.1. ______________

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

15. For Section 4.3.2.2.5, Page 4.3-17, "replace "valus" with "values" in the last bullet at the bottom of the page.

16. For Section 4.3.2.2.8, Page 4.3-18, replace "references' with "References" and "on line" with "online' in the first and second paragraph respectively.

17. For Section 4.3.2.3, Page 4.3-19, replace "FH" with the term "peaking factor"

18. For Section 4.3.2.3.2, Pg. 4.3-20; -68 0F (minus 681F) was changed to -681F (approximately 680F). This change is consistent with the proposed changes presented in Reference 2.

19. For Section 4.3.2.3.4, Page 4.3-21, delete "+or" from two lines.

20. For Section 4.3.2.4, Page 4.3-22, relocate the phrase "for analytic uncertainties {36}" to after 10% within the

14.

Section second sentence of the second paragraph of this (cont.)

4.3 section.

2-108-14 21, For Section 4.3.2.4, Page 4.3-22, insert the following statement at the end of the third paragraph of Section 4.3.2.4: "The shutdown margin calculation considers the reactivity addition from these individual components as the power defect from the current power level to the hot zero power condition."

22. For Section 4.3.2.4.2; Page 4.3-23, the temperature uncertainty was increased from 40F to 6°F in the last sentence of the first paragraph. This is consistent with the 50F uncertainty and the -1OF bias.

23. For Section 4.3.2.7, Pg. 4-28; all instances (5 places) of the term "fresh fuel rack(s)" have been changed to "new fuel rack(s)".

24. For Section 4.3-2.7, Page 4.3-29, add to "s" to the word, "calculation" to make it plural in the fourth sentence of the fourth paragraph under the heading "Spent Fuel Storage - Wet."

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

25. For Section 4.3-2.7, Page 4.3-30, bold the heading entitled, "Analytical Technique and Results"

26. For Section 4.3.2.7, Page 4.3-32, replace the word "spend":

to "spent" in the last sentence of the first paragraph of this page.

27. For Section 4.3.2.8.4, Page 4.3-34, replace "is" with "are" and capitalize "references" in the first sentence in the first

14.

Section paragraph of Item (1).

2-108-14 (cont.)

4.3

28. For Section4.3.3.3, Page 4.3-40, capitalize the word, "doppler" in the first item of list at the bottom of the page.

29. For Reference 2 on Page 4.3-41, replace "WCAP-7308-L-P" with "WCAP-7308-L-P-A"

30. For Table 4.3-1; Page 4.3-46, replace values "1.49" and "1.213" at the bottom of table with "1.39" and "1.186" respectively.

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ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

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31. For Table 4.3-2; Page 4.3-47 (Page 1 of 2), replace values in table as follows Value From To Total Heat Flux Hot Channel Factor FQ Nuclear Enthalpy Rise Hot Channel Factor, 1.55 1.65 FNA F NAH Upper Curve, Design

-10.2 to -6.7

-9.55 to -6.05 Limit

14.

Section Doppler-only Power,

-16.5 to -9.3

-12.2 to -8.1 2-108-14 (cont.)

4.3 Lower Cover Upper Curve, Best

-15.3 to -8.4

-10.3 to -7.5 Estimate Doppler Temperature

-2.1 to -1.4

-2.2 to -1.5 Coefficient Moderator Temperature 0.0 to -33.6 0.0 to -32.6 Coefficient, Best Estimate Boron Coefficient, Best

-12.2 to -8.5 7.

Estimate El-38

ENCLOSURE1 WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number 32 For Table 4.3-2; Page 4.3-48 (Page 2 of 2), replace values in table as follows:

Value From To Bank Worth, Bank D, 1417 1339 HZP, BOL Bank Worth, Bank C, 1187 1201 HZP, BOL Bank Worth, Bank B, 1573 1362 HZP, BOL Bank Worth, Bank A, 1156 1130 HZP, BOL Bank Worth, Bank D, 1404 1267 HZP, EOL Bank Worth, Bank C, 1204 1110 HZP, EOL Bank Worth, Bank B, 1314 1213 HZP, EOL Bank Worth, Bank A, 1128 1042 HZP, EOL Radial Factor (BOL to 1.38 to 1.23 1.37 to 1.20 EOL), Unrodded Radial Factor (BOL to 1.55 to 1.36 1.37 to 1.21 EOL), D Bank Zero Power, keff = 0.99, Cold, Rod Cluster 1407 1213 Control Assemblies Out Zero Power, keff = 0.99, Hot, Rod Cluster 1416 1130 Control Assemblies Out Zero Power, keff < 0.95, Cold, Rod Cluster 1136 972 Control Assemblies In Zero Power, keff = 1.00, Hot, Rod Cluster 1314 1033 Control Assemblies Out Full Power, No xenon, keff = 1.0, Hot, Rod 1186 875 Cluster Control Assemblies Out Full Power, Equilibrium Xenon, keff = 1.0, Hot 869 559 Rod Cluster Control Assemblies Out 14.

(cont.)

Section 4.3 2-108-14 E1-39

ENCLOSURE I WBN Unit 2 FSAR A107 "Summary Listing of A107 FSAR Changes" Change Item No.

Change Area Change Description Package Number

33. For Table 4.3-3; Page 4.3-49, replace table with updated information.

34. Replace Figures 4.3-4a, 4.3-4b and 4.3-5 with updated figures.

14.

Section n.)

Seti

35. Replace Figures 4.3-6 through 4.3-13 with updated figures.

2-108-14 (cont.)

4.3

36. Replace Figure 4.3-21 with updated figure.

37. Replace Figure 4.3-33 with updated figure.

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ENCLOSURE2 WBN Unit 2 FSAR A107 "Summary of Redacted Pages" Chapter Page(S)

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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, 10CFR2.390(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, 10CFR2.390(d)(1)

Sheet 1 2

2.4-206 2.4 2.4-76 Security Related, 10CFR2.390(d)(1) 2 2.4-209 2.4 2.4-79 Security Related, 10CFR2.390(d)(1) 2 2.4-212 2.4 2.4-82 Security Related, 10CFR2.390(d)(1) 2 2.4-213 2.4 2.4-83 Security Related, 10CFR2.390(d)(1) 2 2.4-218 2.4 2.4-88 Security Related, 10CFR2.390(d)(1) 2 2.4-219 2.4 2.4-89 Security Related, 10CFR2.390(d)(1) 2 2.4-220 2.4 2.4-90 Security Related, 10CFR2.390(d)(1) 2 2.5-471 2.5 2.5-185 Security Related, 10CFR2.390(d)(1) 2 2.5-472 2.5 2.5-185a Security Related, 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)

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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)

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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)

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ENCLOSURE 3 WBN Unit 2 FSAR A107 "List Of Files And File Sizes On The Security-Related OSM (OSM #1)"

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ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 108 - List of Files on Security-Related OSM File Name File Size - Bytes TVA WBN-2_FSARFiles 001 TVA WB_FSAR TOC.pdf 362,569 002_TVA WB FSAR LRP.pdf 96,901 003 TVA WB FSAR Section_l.pdf 4,646,853 004 TVA WB FSAR Section 2 A.pdf 19,859,628 005 TVA WB FSAR Section 2 B Part 1 of 2.pdf 44,209,852 005 TVA WB FSAR Section 2 B Part 2 of 2.pdf 42,591,716 006 TVA WB FSAR Section 2 C.pdf 2,104,421 007 TVA WB FSAR Section 2 D.pdf 31,323,894 008 TVA WB FSAR Section_2_E.pdf 47,312,569 009_TVAWBFSAR Section 3 A.pdf 2,624,981 010 TVA WB FSAR Section_3 B.pdf 7,062,835 011 TVA WB FSAR Section 3 C.pdf 30,015,701 012_TVA WB FSAR Section 3 D.pdf 11,764,767 013 TVA WB FSAR Section 4.pdf 21,326,732 014_TVAWBFSAR Section_5.pdf 8,570,453 015_TVA WB FSAR Section 6 A.pdf 26,046,178 016_TVA WB FSAR Section 6 B.pdf 9,366,373 017_TVAWB FSAR Section 7.pdf 14,022,918 018_TVAWBFSARSection_8.pdf 29,728,878 019 TVA WB FSAR Section 9 A.pdf 24,541,563 020_TVAWBFSARSection_9 B.pdf 16,493,361 021 TVA WB FSAR Section_ 10.pdf 14,164,296 022 TVA WB FSAR Section 11.pdf 3,964,288 023 TVA WB FSAR Section 12.pdf 5,993,869 024_TVA WB FSAR Section_ 13.pdf 3,239,838 025 TVA WB FSAR Section 14.pdf 1,170,580 Page 1 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 108 - List of Files on Security-Related OSM File Name File Size - Bytes 026 TVA WB FSAR Section_ 15.pdf 46,629,911 027_TVAWB BFSARSectionl 6.pdf 148,196 028 TVA WB FSAR Section_ 17.pdf 144,887 Total 469,529,008 TVA_WBN-2_OversizedFSAR_Figures 001_TVA WB FSAR Figure 2.5 3.pdf 1,757,743 002_TVA WBFSAR Figure 2.5 11.pdf 1,689,538 003_TVA WB FSAR Figure 2.5 71.pdf 2,263,087 004 TVA WB FSAR Figure 2.5 222.pdf 909,429 005_TVAWBFSAR Figure 2.5 281 1.pdf 2,155,627 006 TVA WBFSAR Figure 2.5 281 2.pdf 2,117,562 007_TVA WB FSAR Figure 2.5 549 1.pdf 3,600,807 008_TVA WBFSAR 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 WBFSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB FSARFigure 2.5 554 1.pdf 3,081,060 014_TVA WB FSAR Figure 2.5 554 2.pdf 1,996,707 015_TVAWBFSAR Figure 2.5 555.pdf 1,993,312 016_TVAWBFSAR Figure 2.5 556.pdf 2,998,087 017 TVA WB FSAR Figure 2.5 571 1.pdf 844,484 018_TVA WBFSAR Figure 2.5 571 2.pdf 3,128,329 019_TVA WB FSAR Figure 2.5 571 3.pdf 3,284,555 020_TVAWBFSAR Figure 2.5 571 4.pdf 2,142,316 021_TVAWBFSAR Figure 2.5 572.pdf 2,196,945 Page 2 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 108 - List of Files on Security-Related OSM File Name File Size - Bytes 022_TVAWBFSAR Figure 2.5 573.pdf 2,013,286 023_TVA WBFSAR Figure 2.5 576_1.pdf 3,238,525 024_TVA WB FSAR Figure 2.5 576 2.pdf 2,151,750 025_TVAWBFSARFigure 2.5 577.pdf 2,207,622 026_TVA WB FSARFigure 2.5 578.pdf 2,080,032 027_TVAWBFSAR Figure 2.5 579.pdf 2,308,985 028_TVA WBFSAR Figure 2.5 583.pdf 2,487,346 029_TVAWBFSAR Figure 2.5 588.pdf 2,528,515 030 TVA WB FSAR Figure 2.5 589.pdf 2,480,438 031_TVAWBFSAR Figure 2.5 594.pdf 13,054,127 032_TVAWBFSAR Figure 2.5 595.pdf 2,323,267 033_TVAWBFSAR 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 WB FSAR Figure 2.5 603.pdf 4,830,835 037_TVAWBFSAR Figure 2.5 604.pdf 6,392,279 038_TVAWBFSAR Figure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA_WBN-2_OversizedFSARTable 001 TVA WB FSAR Table 6.2.4-1.pdf 1,216,710 Total 1,216,710 Page 3 of 3

ENCLOSURE4 WBN Unit 2 FSAR A107 "List Of Files And File Sizes On The Publicly Available OSM (OSM #2)"

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ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 108 List of Files on Publicly Available OSM File Name File Size - Bytes TVAWBN-2_FSARFiles 001_TVAWBFSARTOC.pdf 362,569 002_TVAWB FSARLRP.pdf 96,901 003 TVA WB FSAR Section _.pdf 840,185 004_TVA WB FSAR Section_2_A.pdf 19,523,063 005WTVAWB FSAR Section 2 B Part lof_2.pdf 33,962,499 005 TVA WB FSAR Section 2 B Part 2 of_2.pdf 36,333,595 006 TVA WB FSAR Section 2 C.pdf 2,104,421 007 TVA WB FSAR Section 2_D.pdf 31,323,894 008 TVA WB FSARSection 2 E.pdf 45,933,113 009 TVA WB FSAR Section 3_A.pdf 2,333,546 010 TVA WB FSAR Section 3 B.pdf 5,661,088 011 TVA WB FSAR Section 3 C.pdf 25,183,205 012WTVAWBFSAR Section 3 D.pdf 11,496,042 013_TVA WB FSAR Section 4.pdf 21,326,732 014 TVA WB FSAR Section 5.pdf 8,570,453 015_TVA WB FSAR Section_6_A.pdf 23,165,699 016 TVA WB FSAR Section_6_B.pdf 9,366,373 017 TVA WB FSAR Section 7.pdf 14,022,918 018 TVA WBFSAR Section 8.pdf 26,768,692 019 TVA WB FSAR Section_9_A.pdf 24,280,513 020 TVA WB FSAR Section 9 B.pdf 15,278,836 021 TVA WB FSAR Section 10.pdf 14,164,296 022_TVA WB FSAR Sectionl 1.pdf 3,964,288 023 TVA WB FSARSection 12.pdf 1,725,677 024_TVA WB FSAR Section 13.pdf 3,239,838 025_TVA WB FSAR Section_ 14.pdf 1,170,580 Note: Byte amounts in italics are redacted files.

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ENCLOSURE 4 TVA Watts Bar.Nuclear Plant Unit 2 FSAR Amendment 108 List of Files on Publicly Available OSM File Name File Size - Bytes 026_TVAWBFSAR Section 15.pdf 46,629,911 027_TVA WB FSAR Section 16.pdf 148,196 028_TVAWBFSARSection-l 7.pdf 144,887 Total 429,122,010 TVAWBN-2_OversizedFSARFigures 001 TVAWBFSAR Figure 2.5 3.pdf 1,757,743 002_TVA WB FSAR Figure 2.5 11.pdf 1,689,538 003 TVA WBFSAR Figure 2.5 71.pdf 2,263,087 004_TVAWBFSAR Figure 2.5 222.pdf 909,429 005_TVAWBFSAR Figure 2.5 281_1.pdf 2,155,627 006_TVAWBFSAR Figure 2.5 281_2.pdf 2,117,562 007_TVAWBFSAR Figure 2.5 549 1.pdf 3,600,807 008_TVA WBFSAR Figure 2.5 549 2.pdf 3,989,180 009_TVAWBFSAR Figure 2.5 549 3.pdf 2,863,719 010_TVAWBFSAR Figure 2.5 549 4.pdf 2,809,599 011_TVAWBFSAR 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_TVAWBFSAR Figure 2.5 555.pdf 1,993,312 016_TVAWBFSAR Figure 2.5 556.pdf 2,998,087 017_TVAWBFSAR Figure 2.5 571 1.pdf 844,484 018_TVAWBFSAR Figure 2.5 571_2.pdf 3,128,329 019_TVAWBFSAR Figure 2.5 571_3.pdf 3,284,555 020_TVA WB FSAR Figure 2.5 571 4.pdf 2,142,316 021_TVAWBFSAR 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 108 List of Files on Publicly Available OSM File Name File Size - Bytes 022_TVAWBFSAR Figure 2.5 573.pdf 2,013,286 023_TVAWBFSAR Figure 2.5 576_1.pdf 3,238,525 024 TVA WB FSAR Figure 2.5 576_2.pdf 2,151,750 025_TVAWB FSAR Figure 2.5 577.pdf 2,207,622 026_TVA WB FSAR Figure 2.5 578.pdf 2,080,032 027_TVAWBFSAR Figure 2.5 579.pdf 2,308,985 028_TVAWBFSAR Figure 2.5 583.pdf 2,487,346 029_TVA WBFSAR Figure 2.5 588.pdf 2,528,515 030 TVA WB FSAR Figure 2.5 589.pdf 2,480,438 031_TVAWBFSAR 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 WBFSAR 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_OversizedFSARTable 001 TVA WB FSAR Table 6.2.4-1.pdf 1,216,710 Total_

Note: Byte amounts in italics are redacted files.

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