ML11257A209

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2011/08/12 Watts Bar 2 OL - TVA Lette to NRC_08-12-2011_WBN U2 FSAR A105
ML11257A209
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Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 08/12/2011
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Division of Operating Reactor Licensing
References
Download: ML11257A209 (30)
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Text

1 WBN2Public Resource From: Boyd, Desiree L [dlboyd@tva.gov]

Sent: Friday, August 12, 2011 10:29 AM To: Epperson, Dan; Poole, Justin; Raghavan, Rags; Milano, Patrick; Campbell, Stephen Cc: Crouch, William D; Hamill, Carol L; Boyd, Desiree L

Subject:

TVA lette to NRC_08-12-2011_WBN U2 FSAR A105 Attachments:

08-12-2011_WBN U2 FSAR A105_Final.pdfPlease see attached TVA letter that was sent to the NRC today.

Thank You,

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

Désireé L. Boyd WBN 2 Licensing Support Sun Technical Services dlboyd@tva.gov 423-365-8764

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 501 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF21D86489)

Subject:

TVA lette to NRC_08-12-2011_WBN U2 FSAR A105 Sent Date: 8/12/2011 10:28:37 AM Received Date: 8/12/2011 10:28:54 AM From: Boyd, Desiree L Created By: dlboyd@tva.gov Recipients: "Crouch, William D" <wdcrouch@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" <Dan.Epperson@nrc.gov> Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>

Tracking Status: None "Raghavan, Rags" <Rags.Raghavan@nrc.gov> Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov> Tracking Status: None "Campbell, Stephen" <Stephen.Campbell@nrc.gov>

Tracking Status: None Post Office: TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 317 8/12/2011 10:28:54 AM 08-12-2011_WBN U2 FSAR A105_Final.pdf 281162 Options Priority: Standard Return Notification: No Reply Requested: No 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 12, 2011 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 105

References:

1. TVA letter to NRC dated June 3, 2011, Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report Amendment 104
2. TVA letter to NRC dated October 11, 2007, Watts Bar Nuclear Plant (WBN) - Unit 2 - Exemptions, Reliefs, Deviations and Exceptions (ML072910331)
3. NRC Supplemental Safety Evaluation Report (SSER) 5 dated November 1, 1990 (ML073520360)
4. TVA letter to NRC dated February 13, 1985, Exemption Request (ML073511898)

This letter transmits WBN Unit 2 FSAR Amendment 105 (A105), which reflects changes made since the issuance of Amendment 104 on June 3, 2011 (Reference 1).

contains a summary listing of FSAR sections and corresponding Unit 2 change package numbers associated with the A105 FSAR changes. Most of these changes were the result of resolutions to NRC Requests for Additional Information.

FSAR A105 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).

U.S. Nuclear Regulatory Commission Page 3 August 12, 2011

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 12, 2011

bcc (Enclosures):

Stephen Campbell

U.S. Nuclear Regulatory Commission

MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738

Charles Casto, 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 A105 Summary Listing of A105 FSAR Changes" E1-1 Item No. Change Area Change Description Change Package Number 1. Section 4.3.2.7 Insert the following paragraph

WBN conforms fully with the criteria of 10 CFR 50.68(b)(6). There are five radiation monitors located on elevation 757 of the Auxiliary Building in the vicinity of the new fuel vault and the

spent fuel pool. Two of the monitors, 1-RE-90-1 and 2-RE-90-1, are area monitors that alert personnel in the vicinity of the fuel storage areas of excessive radiation for personnel protection

and to initiate safety actions. These monitors also alarm in the main control room to alert the operators to initiate appropriate safety actions. There are two additional area radiation monitors, 0-RE-90-102 and 0-RE-90-103, that are located at the spent fuel pool to provide a more rapid response to a fuel handling

accident, the presence of excessive radiation, or the presence of a fuel bundle with inadequate water shielding. These monitors alarm in the main control room and also isolate the normal Auxiliary Building ventilation system to reduce the release of radioactivity offsite. These monitors will also isolate the containment ventilation system if the containment or annulus is open to the Auxiliary Building during refueling operations. The fifth radiation monitor in the spent and new fuel area is a particulate air monitor. This monitor alarms locally for protection

of personnel in the vicinity of the monitor and also serves to alert the plant staff of an excessive radiation condition that requires action. 2-105-01 2. Table 6.2.6-3 Remove the phrase, "as specified in 10 CFR 50, Appendix J," in Note 3. 2-105-02 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-2 Item No. Change Area Change Description Change Package Number 3. Section 11.2 1. On Page 11.2-19, modify Section 11.2.6.5.1 to read as follows (changes are bolded and underlined):

11.2.6.5.1 Expected Normal Plant Operation

The expected plant alignment and resultant releases are as follows: CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

The reactor coolant drain tank, the tritiated drain collector tank, and the floor drain collector tank discharges and processed using the mobile demineralizer.

Liquid releases from the L aundry and Hot Shower Drain Tank and the Turbine Building drains can be released without processing by mobile demineralizer.

Steam Generator Blowdown is released without processing.

The condensate demineralizers are bypassed. Thus there is no condensate demineralizer regeneration waste to be processed.

2. On Page 11.2-20, modify Section 11.2.6.5.2 to read as follows: 11.2.6.5.2 Other Plant Alignment Evaluations

The values in Table 11.2-5 Column 4 assume the following:

CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

The reactor coolant drain tank, the tritiated drain collector tank, and the floor drain collector tank discharges and processed using the mobile demineralizer.

Activity from Condensate Demineralizer waste due to the processing of condensate and steam generator blowdown

is routed directly to the Cooling Tower Blowdown or the turbine building sump.

Liquid releases from the L aundry and Hot Shower Drain Tank and the Turbine Building drains were released without processing by mobile demineralizer.

2-105-03 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-3 Item No. Change Area Change Description Change Package Number 3. (cont.) Section 11.2 The values in Table 11.2-5 Column 5 assume the following:

CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

The reactor coolant drain tank, the tritiated drain collector tank, and the floor drain collector tank discharges and processed using the mobile demineralizer.

Condensate demineralizer regeneration waste is processed by the mobile demineralizer.

Liquid releases from the L aundry and Hot Shower Drain Tank and the Turbine Building drains were released without processing by mobile demineralizer.

3. On Page 11.2-38, modify Footnote F and Footnote for columns 4 and 5, as follows:

F (Ci/yr) = Activity from Condensate Demineralizer regeneration waste = Activity from 6 days of processing of

condensate and steam generato r blowdown flow by the condensate demineralizer.

Column 4: ((A+B/C)/D) + E + F + G Column 5: ((A+B/C)/D) + E + F/D + G 2-105-03 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-4 Item No. Change Area Change Description Change Package Number 4. Section 12.3.1 Insert the following text at the end of Section 12.3.1, but before heading for Section 12.3.2, "Shielding." "Integration of Unit 2 for Dual Unit Operation

The following section supplements the above discussion (written primarily for one unit operation) with the integration of Unit 2 operation for dual unit operation:

Controlled Access Areas The Unit 2 controlled access area will be common with the Unit 1 controlled access area. This facility is located in the Service Building and is sized and situated properly to support two operating units.

Personnel and Equipment Decontamination

The Unit 2 personnel and equipment decontamination facilities will be common areas shared with the Unit 1 personnel and equipment decontamination facilities. The personnel decontamination facility is located in the Service Building and is sized and situated properly to support two operating units. The equipment decontamination facility is located in the Auxiliary Building and is sized and situated properly to support two operating units.

Contamination Control Areas The primary Unit 2 contamination control area (i.e., radiologically controlled area [RCA] exit personnel monitoring station) will be a common area shared with the Unit 1 contamination control areas. This facility is located in the Service Building adjacent to the Auxiliary Building common entrance/exit point. This RCA exit point is equipped with personnel contamination monitors (PCMs), personnel gamma monitors, and tool and equipment monitors. PCMs are also provided at common locations inside the Auxiliary Building (i.e., 676', 713, and 757' elevations) for prompt personnel contamination monitoring when personnel exit contaminated areas. Frisker stations are also set up at remote exit points from the RCA when the use of PCMs is not

practicable. Remote exit points are used only after prior approval by Radiation Protection and in the event of an emergency.

2-105-04 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-5 Item No. Change Area Change Description Change Package Number 4. (cont.) Section 12.3.1 Protective clothing laundry services are provided offsite by a contractor. Soiled protective clothing is temporarily stored onsite in designated containers until ready for shipment offsite. Laundered protective clothing retu rned from the laundry contractor is received at the plant Power Stores loading dock and temporarily stored in a room adjacent to the loading dock until issued for use. This facility is located in the Service Building and is sized and situated properly to support two operating units. Hot machine shop type activities are not normally performed onsite. Instead, radioactive materials requiring machine shop support are normally sent to either the TVA Western Area Radiological Laboratory or to a contractor

licensed to receive radioactive material. If machining is performed onsite, a temporary RCA is set up in the clean area machine shop and controlled by Radiation Protection.

Contamination control barriers, containments, or tents, as appropriate, are used to prevent the spread of contamination and airborne radioactivity. Storage facilities are established in the Auxiliary Building and the Service Building to maintain a central location for the inventory of standard portable decontamination equipment and sup plies (i.e., high energy particulate air [HEPA] vacuums, HEPA ventilation units, pressure washers, spray wands, mops, etc.) that may be used during the normal decontamination and control of radioactive contamination in the plant. These facilities are sized and situated properly to support two operating units.

In Plant Traffic Patterns to Radiologically Controlled Areas The Unit 2 in plant traffic patterns to RCAs will be virtually the mirror image of the Unit 1 in plant traffic patterns to RCAs. Access to Unit 1 and Unit 2 RCAs will share common corridors at each elevation of the Auxiliary Building. Common areas are sized and situated properly to support two operating units. Access to satellite Unit 2 RCAs (i.e., outside tanks) will be controlled in the same manner as Unit 1.

2-105-04 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-6 Item No. Change Area Change Description Change Package Number 4. (cont.) Section 12.3.1 Health Physics Facilities The Unit 2 Health Physics facilities (including dosimetry issue and maintenance, respiratory protection issue and maintenance, in-vivo and in-vitro bioassay, protective clothing and radiation survey instrument issue, Radiation Protection Manager [RPM] and technical staff office/work space) will be common with Unit 1 facilities. These facilities and offices are located in the Training Center (dosimetry issue and maintenance, and in-vivo and in-vitro bioassay), Service Building (respiratory protection issue and maintenance, protective clothing and radiation survey instrument issue), and Office Building (RPM and technical staff office/work space). These facilities are sized and situated properly to support two operating units.

Onsite Laboratory for Analysis of Chemical and Radiological Samples The Unit 2 onsite laboratory for analysis of chemical and radiological samples will be common with the Unit 1 onsite laboratory for analysis of chemical and radiological samples.

These facilities are located in the Auxiliary Building and the Service Building and are sized and situated properly to support two operating units.

Radiological Counting Room

The Unit 2 radiological counting room will be common with the Unit 1 radiological counting room. This facility is located in the Service Building and is sized and situated properly to support

two operating units." 2-105-04 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-7 Item No. Change Area Change Description Change Package Number 5. 12.4 On Page 12.4-2, insert prior to the Reference section, the following new section:

Unit 2 Dose Assessment

Watts Bar Unit 2 operation and maintenance is expected to be virtually the same as that experienced in the operation and maintenance of Watts Bar Unit 1, including the radiation source term. Historic exposures for Watts Bar Unit 1 are provided in NUREG-0713, Volume 29, beginning in 1997 until 2007. The annual collective dose (person-rem) for this time frame ranged from a low of 3.106 person-rem to a high of 322.682 person-

rem. The high collective dose of 322.682 person-rem occurred in 2006 at which time all four Unit 1 steam generators were replaced. Steam generator re placement and the resultant collective dose is not typica l of normal operation and maintenance activities, thus is treated as special maintenance and not included in the proposed Watts Bar Unit 2 exposure

estimate. (Steam generator repla cement activities contributed to approximately 180 person-rem of the 322.682 person-rem for that year.) The proposed annual collective dose was determined by averaging the annual dose (less the steam generator replacement dose). This yields an average annual dose estimate of [(113 + 3.106 + 98.946 + 122.453 + 5.912 +

93.598 + 165.741 + 5.893 + 143.506 + (322.682-180) + 4.414)/11)] = 81.75 person-rem. Additionally, the collective doses for years 2008 and 2009 show a continuing downward trend towards dose reduction.

2-105-05 6. Section 13.1.3 In Section 13.1.3, Qualification Requirements for Nuclear Facility Personnel, on page 13.1-4, insert the following information:

1. Place a 1 as a footnote indicator after the position of Radiological Control Superintendent.
2. Insert the following as footnote 1, 1The position of Radiological Control Superintendent will meet the requirements of RG 1.8, Revision 2, and ANSI/ANS 3.1-1981, for all new personnel qualifying on positions identified in RG 1.8, Regulatory Position C.1, after January 1, 1990 as clarified by Reference 3.
3. Add a new Reference 3 as follows:

(3) TVA Standard Program and Processes, NPG-SPP-05.1, Radiological Controls.

2-105-06 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-8 Item No. Change Area Change Description Change Package Number 7. Section 1.1.1 Section 1.2.2.2 Section 7.1.2 Section 7.2.1.1.5 Section 7.4.2

Section 7.4.3 Table 7.1-1 Table 7.2-2 Section 7.5.1.2 Table 7.5-2 References 7.1 References 7.2 References 7.3 Section 11.4.4 Section 12.3.4.1.3 1. In Sections 1.1.1 and 1.2.2.2, change heat input for Reactor Coolant Pumps (RCPs) from 14MWt to 16MWt.

2. Insert new section 7.4.2 entitled, Auxiliary Control Room (ACR), and renumber 7.4.2, Analysis, to 7.4.3.
3. For Section 7.1.2, remove the entries that are duplicated in Table 7.1-1, provide appropriate reference to Table 7.1-1 and renumber remaining items.
4. For Section 1.1.1, 7.1.2, 7.4.3, and Tables 7.1-1 and 7.5-2, correct the use of quotes, correct spelling errors, and adjust page numbers and entries in Table 7.1-1. Reformat Table 7.1-1 Notes for consistency and clarity.
5. For Table 7.1-1, add entries and notes associated with installation of the Common Q Post Accident Monitoring System (PAMS) and the RM-1000 digital radiation monitors
6. For Table 7.2-2, delete the word chamber from the description of the P-7 interlock.
7. For Section 7.5.1.2 and Table 7.5-2, revise definition of Type A variables to reflect the fact that TVA includes variables that do not meet the Regulatory Guide (RG) 1.97

definition and identify those variables in Table 7.5-2.

8. For References 7.1, 7.2, and 7.3, correct reference entries for WCAPs 17044 and 13869.
9. For Section 12.3.4.1.3, provide details of Channel Operability Test (COT) periodic test frequency in accordance with calculation WBN EEB EDQ1090-99005, Rev. 2. 10. For Section 11.4.4, revise terms used to describe monitor testing. 11. For 12.3.4.1.3, delete reference to the Offsite Dose Calculation Manual (ODCM) and reword for clarity.
12. For 7.2.1.1.5, delete discussion of the pressurizer level condensing chambers.

2-105-07 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-9 Item No. Change Area Change Description Change Package Number 8. Table 6.3-8 On Table 6.3-8, Sheets 7 and 8 of 66, change the Method of Detection for the Stuck Closed and Stuck Open Failure Modes associated with Items 8 and 9, as revised. 2-105-08 9. Section 15.5 Revise Chapter 15 Tables as listed below with new values provided from recent dose calculation revisions:

15.5-2, Doses from Loss of A/C Power 15.5-5, Doses from Ga s Decay Tank Rupture 15.5-9, Doses from Loss of Coolant Accident 15.5-13, Doses from Recirculation Loop Leakage following a LOCA 15.5-14, Atmospheric Dilution Factors at the Control Building 15.5-17, Doses from Main Steam Line Break

15.5-18, Parameters Used in Steam Generator Tube Rupture Analysis 15.5-19, Doses from Steam Generator Tube Rupture 15A-2, Accident Atmospheric Dilution Factors (sec/m

3) 2-105-09 10. Section 14.2 1. On page 14.2-19, insert new Item j to read as follows:

(j) Appendix A, subparagraphs 2.b.

Cold, no-flow, cold, full-flow and hot, no-flow rod drops do not provide any additional useful data. The drop times for these flow conditions are less conservative than for hot full flow conditions. WBN does not intend to perform cold, no-flow, cold, full-flow and hot, no-flow rod drops.

2. Since Table 14.2-2, Sheet 11 of 39 was previously deleted, modify the title on Table 14-2.2 (Sheet 1 of 39) POWER ASCENSION TEST SUMMARIES INDEX to read "DELETED" rather than say "Spent Fuel Pool Cooling System." 3. For Table 14.2-2, Sheet 3 of 39, under TEST METHOD, revise the third sentence from A minimum of two source range channels will be responding following the loading of the initial nucleus of eight assemblies. to reword to read as follows: A minimum of two source range channels will be responding to source neutrons before additional assemblies are loaded. Then following the loading of the initial nucleus of eight assemblies near each of the two installed source range channels, each channel will be adequately responding to subcritical multiplication of additional assemblies loaded.

2-105-10 ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" E1-10 Item No. Change Area Change Description Change Package Number 10. (cont.) Section 14.2 4. For Table 14.2-2, Sheet 3 of 39: correct typographical error by adding space between increased and (decrease) at ACCEPTANCE CRITERIA.

5. For Table 14.2-2, Sheet 4 of 39, revise the sentence in the PREREQUISITES that now reads from: The water level in the reactor vessel has been established. to The water level in the reactor cavity has been established.
6. For Table 14.2-2, Sheet 9 of 39: revise TEST Method Description in the fifth sentence to read, Testing will be performed under hot full flow conditions. In addition, add Note to say: NOTE: Additional rod drops may be performed at either hot or cold RCS conditions with any RCS flow conditions. These drops are not used to satisfy

acceptance criteria and their times are not included in calculating averages.

7. For Table 14.2-2, Sheet 15 of 39, revise PREREQUISITES 1 to read: RCS flow measurement testing has been completed in Mode 3. 2-105-10 11. Section 2.3 Section 7.7 1. On Pages 2.3-25 and 2.3-2 6 (A104), correct typographical errors in Table 2.3-1B header by changing Surronding to Surrounding
2. On page 2.3-41 (A104), delete 98 from heading of Table 2.3-32. (By making this change in this section, this heading in the list of tables will be automatically changed)
3. On Page 7.7-20 (A104), correct typographical error by changing Section 7.7.1.11 heading from Distribution Control System to Distributed Control System. (By making this change in this se ction, this heading in the table of contents will be automatically changed.) 2-105-11 12. Table 6.2.6-3 Delete valves ISV-41-586, ISV-41-589, ISV-41-592 and ISV-41-595 from FSAR Table 6.2.6-3 as shown on the attached FSAR mark-up. 2-105-12 13. Section 9.2.2.4 Section 9.2.5.3 1. For Section 9.2.2.4, correct the typographical error in the second sentence of the first paragraph on FSAR page 9.2-19 (A104), as shown on the attached markup.
2. Clarify Section 9.2.5.3 to indicate the UHS has sufficient capacity to support bringing the non-accident unit to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from entry into the Hot Standby mode. 2-105-13 ENCLOSURE 2 WBN Unit 2 FSAR A105 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 A105 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 8.2-14 8.2 Text only Security Related, 10CFR2.390(d)(1) 8 8.2-15 8.2 Text only Security Related, 10CFR2.390(d)(1)

ENCLOSURE 2 WBN Unit 2 FSAR A105 Summary of Redacted Pages Chapter Page(S) Section No. Figure No. Basis For Redaction E2-3 8 8.2-30 8.2 8.2-3 Security Related, 10CFR2.390(d)(1) 8 8.2-31 8.2 8.2-4 Security Related, 10CFR2.390(d)(1) 8 8.2-44 8.2 8.2-11 Security Related, 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 A105 List Of Files And File Sizes On The Security-Related OSM (OSM #1)

E3-1 ENCLOSURE 3TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 - List of Files on Security-Related OSMFile NameFile Size - BytesTVA_WBN-2_FSAR_Files001_TVA_WB_FSAR_TOC.pdf362,108002_TVA_WB_FSAR_LRP.pdf88,451003_TVA_WB_FSAR_Section_1.pdf 4,643,883004_TVA_WB_FSAR_Section_2_A.pdf 10,467,163005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 44,606,435005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 49,572,114006_TVA_WB_FSAR_Section_2_C.pdf 2,107,389007_TVA_WB_FSAR_Section_2_D.pdf 31,323,839008_TVA_WB_FSAR_Section_2_E.pdf 47,312,480009_TVA_WB_FSAR_Section_3_A.pdf 2,622,917010_TVA_WB_FSAR_Section_3_B.pdf 7,063,082011_TVA_WB_FSAR_Section_3_C.pdf 30,016,094012_TVA_WB_FSAR_Section_3_D.pdf 11,764,620013_TVA_WB_FSAR_Section_4.pdf 10,713,352014_TVA_WB_FSAR_Section_5.pdf 9,119,079015_TVA_WB_FSAR_Section_6_A.pdf 26,047,923016_TVA_WB_FSAR_Section_6_B.pdf 7,617,151017_TVA_WB_FSAR_Section_7.pdf 13,195,628018_TVA_WB_FSAR_Section_8.pdf 29,723,997019_TVA_WB_FSAR_Section_9_A.pdf 24,536,294020_TVA_WB_FSAR_Section_9_B.pdf 16,485,358021_TVA_WB_FSAR_Section_10.pdf 13,430,648022_TVA_WB_FSAR_Section_11.pdf 3,965,291023_TVA_WB_FSAR_Section_12.pdf 5,994,207024_TVA_WB_FSAR_Section_13.pdf 3,240,070025_TVA_WB_FSAR_Section_14.pdf 1,170,286Page 1 of 3 ENCLOSURE 3TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 - List of Files on Security-Related OSMFile NameFile Size - Bytes026_TVA_WB_FSAR_Section_15.pdf027_TVA_WB_FSAR_Section_16.pdf 028_TVA_WB_FSAR_Section_17.pdfTotal 407,189,859TVA_WBN-2_Oversized_FSAR_Figures001_TVA_WB_FSAR_Figure_2.5_3.pdf 1,757,743002_TVA_WB_FSAR_Figure_2.5_11.pdf1,689,538 003_TVA_WB_FSAR_Figure_2.5_71.pdf2,263,087 004_TVA_WB_FSAR_Figure_2.5_222.pdf909,429 005_TVA_WB_FSAR_Figure_2.5_281_1.pdf2,155,627 006_TVA_WB_FSAR_Figure_2.5_281_2.pdf2,117,562 007_TVA_WB_FSAR_Figure_2.5_549_1.pdf3,600,807 008_TVA_WB_FSAR_Figure_2.5_549_2.pdf3,989,180 009_TVA_WB_FSAR_Figure_2.5_549_3.pdf2,863,719 010_TVA_WB_FSAR_Figure_2.5_549_4.pdf2,809,599011_TVA_WB_FSAR_Figure_2.5_550.pdf1,803,985 012_TVA_WB_FSAR_Figure_2.5_551.pdf1,996,869 013_TVA_WB_FSAR_Figure_2.5_554_1.pdf3,081,060 014_TVA_WB_FSAR_Figure_2.5_554_2.pdf1,996,707015_TVA_WB_FSAR_Figure_2.5_555.pdf1,993,312 016_TVA_WB_FSAR_Figure_2.5_556.pdf2,998,087 017_TVA_WB_FSAR_Figure_2.5_571_1.pdf844,484 018_TVA_WB_FSAR_Figure_2.5_571_2.pdf3,128,329019_TVA_WB_FSAR_Figure_2.5_571_3.pdf3,284,555 020_TVA_WB_FSAR_Figure_2.5_571_4.pdf2,142,316 021_TVA_WB_FSAR_Figure_2.5_572.pdf2,196,945Page 2 of 3 ENCLOSURE 3TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 - List of Files on Security-Related OSMFile NameFile Size - Bytes022_TVA_WB_FSAR_Figure_2.5_573.pdf2,013,286023_TVA_WB_FSAR_Figure_2.5_576_1.pdf3,238,525 024_TVA_WB_FSAR_Figure_2.5_576_2.pdf2,151,750 025_TVA_WB_FSAR_Figure_2.5_577.pdf2,207,622 026_TVA_WB_FSAR_Figure_2.5_578.pdf2,080,032 027_TVA_WB_FSAR_Figure_2.5_579.pdf2,308,985 028_TVA_WB_FSAR_Figure_2.5_583.pdf2,487,346 029_TVA_WB_FSAR_Figure_2.5_588.pdf2,528,515 030_TVA_WB_FSAR_Figure_2.5_589.pdf2,480,438 031_TVA_WB_FSAR_Figure_2.5_594.pdf13,054,127 032_TVA_WB_FSAR_Figure_2.5_595.pdf2,323,267 033_TVA_WB_FSAR_Figure_2.5_596.pdf5,732,107 034_TVA_WB_FSAR_Figure_2.5_597.pdf1,287,336 035_TVA_WB_FSAR_Figure_2.5_602.pdf5,549,537 036_TVA_WB_FSAR_Figure_2.5_603.pdf4,830,835 037_TVA_WB_FSAR_Figure_2.5_604.pdf6,392,279038_TVA_WB_FSAR_Figure_2.5_605.pdf20,823,108Total 131,112,035TVA_WBN-2_Oversized_FSAR_Table001_TVA_WB_FSAR_Table_6.2.4-1.pdf 1,215,573Total 1,215,573Page 3 of 3 ENCLOSURE 4 WBN Unit 2 FSAR A105 List Of Files And File Sizes On The Publicly Available OSM (OSM #2)

E4-1 ENCLOSURE 4TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 List of Files on Publicly Available OSMFile NameFile Size - BytesTVA_WBN-2_FSAR_Files001_TVA_WB_FSAR_TOC.pdf362,108002_TVA_WB_FSAR_LRP.pdf88,451003_TVA_WB_FSAR_Section_1.pdf 837,309004_TVA_WB_FSAR_Section_2_A.pdf 10,130,617005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 34,359,034005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 43,314,021006_TVA_WB_FSAR_Section_2_C.pdf 2,107,389007_TVA_WB_FSAR_Section_2_D.pdf 31,323,839008_TVA_WB_FSAR_Section_2_E.pdf 45,933,088009_TVA_WB_FSAR_Section_3_A.pdf 2,331,495010_TVA_WB_FSAR_Section_3_B.pdf 5,661,310011_TVA_WB_FSAR_Section_3_C.pdf 25,183,693012_TVA_WB_FSAR_Section_3_D.pdf 11,495,906013_TVA_WB_FSAR_Section_4.pdf 10,713,352014_TVA_WB_FSAR_Section_5.pdf 9,119,079015TVAWBFSARSection6Apdf23167481 015_TVA_WB_FSAR_S ec ti on_6_A.p df 23 , 167 , 481016_TVA_WB_FSAR_Section_6_B.pdf 7,617,151017_TVA_WB_FSAR_Section_7.pdf 13,195,628018_TVA_WB_FSAR_Section_8.pdf 26,763,889019_TVA_WB_FSAR_Section_9_A.pdf 24,275,275020_TVA_WB_FSAR_Section_9_B.pdf 15,270,859021_TVA_WB_FSAR_Section_10.pdf 13,430,648022_TVA_WB_FSAR_Section_11.pdf 3,965,291023_TVA_WB_FSAR_Section_12.pdf 1,726,180024_TVA_WB_FSAR_Section_13.pdf 3,240,070025_TVA_WB_FSAR_Section_14.pdf 1,170,286Note: Byte amounts in italics are redacted files.Page 1 of 3 ENCLOSURE 4TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 List of Files on Publicly Available OSMFile NameFile Size - Bytes026_TVA_WB_FSAR_Section_15.pdf 46,591,104027_TVA_WB_FSAR_Section_16.pdf 148,383028_TVA_WB_FSAR_Section_17.pdf 145,004Total 413,667,940TVA_WBN-2_Oversized_FSAR_Figures001_TVA_WB_FSAR_Figure_2.5_3.pdf 1,757,743002_TVA_WB_FSAR_Figure_2.5_11.pdf1,689,538 003_TVA_WB_FSAR_Figure_2.5_71.pdf2,263,087004_TVA_WB_FSAR_Figure_2.5_222.pdf909,429 005_TVA_WB_FSAR_Figure_2.5_281_1.pdf2,155,627006_TVA_WB_FSAR_Figure_2.5_281_2.pdf2,117,562 007_TVA_WB_FSAR_Figure_2.5_549_1.pdf3,600,807 008_TVA_WB_FSAR_Figure_2.5_549_2.pdf3,989,180 009_TVA_WB_FSAR_Figure_2.5_549_3.pdf2,863,719 010_TVA_WB_FSAR_Figure_2.5_549_4.pdf2,809,599011TVAWBFSARFigure25550pdf1803985 011_TVA_WB_FSAR_Figure_2.5_550.p df 1 , 803 , 985012_TVA_WB_FSAR_Figure_2.5_551.pdf1,996,869 013_TVA_WB_FSAR_Figure_2.5_554_1.pdf3,081,060 014_TVA_WB_FSAR_Figure_2.5_554_2.pdf1,996,707 015_TVA_WB_FSAR_Figure_2.5_555.pdf1,993,312016_TVA_WB_FSAR_Figure_2.5_556.pdf2,998,087 017_TVA_WB_FSAR_Figure_2.5_571_1.pdf844,484 018_TVA_WB_FSAR_Figure_2.5_571_2.pdf3,128,329 019_TVA_WB_FSAR_Figure_2.5_571_3.pdf3,284,555020_TVA_WB_FSAR_Figure_2.5_571_4.pdf2,142,316 021_TVA_WB_FSAR_Figure_2.5_572.pdf2,196,945Note: Byte amounts in italics are redacted files.Page 2 of 3 ENCLOSURE 4TVA Watts Bar Nuclear Plant Unit 2FSAR Amendment 105 List of Files on Publicly Available OSMFile NameFile Size - Bytes022_TVA_WB_FSAR_Figure_2.5_573.pdf2,013,286023_TVA_WB_FSAR_Figure_2.5_576_1.pdf3,238,525 024_TVA_WB_FSAR_Figure_2.5_576_2.pdf2,151,750 025_TVA_WB_FSAR_Figure_2.5_577.pdf2,207,622 026_TVA_WB_FSAR_Figure_2.5_578.pdf2,080,032 027_TVA_WB_FSAR_Figure_2.5_579.pdf2,308,985 028_TVA_WB_FSAR_Figure_2.5_583.pdf2,487,346 029_TVA_WB_FSAR_Figure_2.5_588.pdf2,528,515 030_TVA_WB_FSAR_Figure_2.5_589.pdf2,480,438 031_TVA_WB_FSAR_Figure_2.5_594.pdf13,054,127 032_TVA_WB_FSAR_Figure_2.5_595.pdf2,323,267 033_TVA_WB_FSAR_Figure_2.5_596.pdf5,732,107 034_TVA_WB_FSAR_Figure_2.5_597.pdf1,287,336 035_TVA_WB_FSAR_Figure_2.5_602.pdf5,549,537 036_TVA_WB_FSAR_Figure_2.5_603.pdf4,830,835 037_TVA_WB_FSAR_Figure_2.5_604.pdf6,392,279038TVAWBFSARFigure25605pdf20823108 038_TVA_WB_FSAR_Figure_2.5_605.p df 20 , 823 , 108Total 131,112,035TVA_WBN-2_Oversized_FSAR_Table001_TVA_WB_FSAR_Table_6.2.4-1.pdf 1,215,573Total 1,215,573Note: Byte amounts in italics are redacted files.Page 3 of 3 ENCLOSURE 5 Deviation Request from Regulatory Guide 1.68, Revision 2 E5-1 Background

In 1985, as documented in Reference 1, TVA formally requested an exemption from cold no-flow, cold full-flow, and hot no-flow rod drop testing for WBN Unit 1. The NRC reviewed and approved this request as shown in the following excerpt from Supplemental Safety Evaluation Report (SSER) 5 (Reference 3 below):

Cold No-Flow, Cold Full-Flow, and Hot No-Flow Rod Drop Testing

By letter dated February 13, 1985, the applicant requested a deviation from RG 1.68, Revision 2, which would allow the removal of rod drop timing tests at cold no-flow, cold full-flow, and hot no-flow conditions from the Watts Bar Initial Test Program. In support of this request, the applicant stated that scram capability is only required for the hot full-flow conditions by the Watts Bar Technical Specifications, except when exempted by Special Test Exemption 3.10.4. The staff has reviewed the February 13, 1985, submittal, concurs with its contents, and finds the deviation acceptable on the basis of the following:

(1) There is nothing new or unique in the design of the Watts Bar control rod system.

(2) Scram capability is only required for hot full-flow conditions.

(3) The deviation is consistent with a similar one allowed for the Initial Test Program at the Callaway Nuclear Plant, Unit 1.

Therefore, the staff approves the deviation and has determined that the applicant does not have to perform cold no-flow, cold full-flow, and hot no-flow rod drop testing at the Watts Bar

Nuclear Plant, Unit 1.

As a result of NRC approval, TVA subsequently submitted FSAR Amendment 56 (Reference 2 below) to incorporate this deviation into Chapter 14, Initial Test Program. In 2007, in the initial phases of Unit 2 completion, as stated in Reference 4, TVA initially did not intend to request a similar deviation for WBN Unit 2 for this item. However, based upon further review of the request granted for Unit 1, TVA has determined that it would pursue this request for Unit 2.

Justification for Request The Unit 1 justification for this request was provided in February 13, 1985 letter (Reference 1 below). Provided in the following is a point-by-point discussion of the Unit 1 justifications as documented in Reference 1 and their applicability to Unit 2:

Justification 1:

Regulatory Guide 1.68, Revision 2, Appendix A, section 2.b, states To the extent practical, testing should demonstrate control rod scram times. . .as required to bound conditions under which scram might be required. It is our position that hot full-flow rod drop testing fully meets these conditions of the Regulatory Guide.

Unit 2 Applicability: TVAs position remains unchanged and also applies to Unit 2.

E5-1 Justification 2:

Scram capability is required whenever the reactor is critical, i.e., Modes 1 and 2. Watts Bar TS 3.1.1.4 requires the reactor coolant system operating loop temperature (T AVG) to be greater than or equal to 551ºF in Modes 1 and 2. Specification 3.4.1.1 requires that all reactor coolant loops be in operation in Modes 1 and 2 except when exempted by Special Test Exemption 3.10.4. From these two specifications, it can be seen that hot full-flow rod drop testing would bound the conditions present for a critical reactor (Modes 1 and 2).

Unit 2 Applicability: The operating loop temperature, Tavg for Unit 2, will be the same as for Unit 1, with the Original Steam Generators (OSG), as required by LCO 3.4.2, RCS Minimum Temperature for Criticality. Condition A of LCO 3.4.2 requires the unit to be placed into Mode 3 if Tavg, in one or more RCS loops, is not within limit. Therefore, the hot full-flow rod drop testing would also bound the Unit 2 conditions present for a critical reactor in Modes 1 and 2.

Justification 3:

Scram capability is also required in the event of an uncontrolled rod cluster control assembly bank withdrawal from a subcritical condition. As discussed in the Watts Bar FSAR Section 15.2.1.2, hot zero power conditions (Mode 2) are the most conservative for this event. Thus, this transient condition is bounded by hot, full-flow rod drop testing conditions.

Unit 2 Applicability: This position remains unchanged and also applies to Unit 2.

Justification 4:

Additional justification for exemption from hot, no-flow rod drop testing is obtained from the

analysis rod drop test data for Sequoyah Unit 2 (provided in Reference 1). The rod drop times indicate that in all cases the hot, full-flow rod drop times were longer (more conservative) than the hot, no-flow rod drop times.

Unit 2 Applicability: This position remains unchanged and also applies to WBN Unit 2.

Justification 5:

Exemption from cold, no-flow, cold, full-flow, and hot, no-flow rod drop testing would be economically beneficial to Watts Bar. As each rod drop test requires at least one shift to complete, a significant amount of critical path work would be eliminated from the plant startup schedule. This is allowed by the requirements of Regulatory Guide 1.68, Revision 2, which requires testing To the extent practical. . . . TVA does not believe it obtains a practical benefit from the performance of these rod drop tests, as the hot full-flow rod drop test bounds the conditions necessary for scram capability. Consequently, TVA believes that exemption from all but hot, full-flow rod drop testing will still meet the requirements of

Regulatory Guide 1.68, Revision 2. The Watts Bar TS and FSAR ensure that the conditions requiring scram are bounded by hot, full-flow rod drop testing conditions.

Unit 2 Applicability: This position remains unchanged and also applies to Unit 2.

E5-1

Conclusion:

Therefore, based on the evaluation above, TVA requests the same deviation for Unit 2 as was approved for Unit 1 from the cold no-flow, cold full-flow, and hot no-flow rod drop testing

requirements of Regulatory Guide 1.68, Revision 2.

References

1. TVA letter to NRC dated February 13, 1985, Deviation Request (ML073511898)
2. TVA letter to NRC dated April 30, 1985, Deviation Request - FSAR Revision 56 (ML072890492)
3. NRC Supplemental Safety Evaluation Report (SSER) 5 dated November 1, 1990 (ML073520360)
4. TVA letter to NRC dated October 11, 2007, Watts Bar Nuclear Plant (WBN) - Unit 2 - Exemptions, Reliefs, Deviations and Exceptions (ML072910331)
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