ML11257A209

OL - TVA Lette to NRC_08-12-2011_WBN U2 FSAR A105

ML11257A209
Person / Time
Site:	Watts Bar
Issue date:	08/12/2011
From:	- No Known Affiliation
To:	Division of Operating Reactor Licensing
References
Download: ML11257A209 (30)

Text

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.pdf Please 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 1

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:

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 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" Change Item Change Area Change Description Package No.

Number 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

1. Section 4.3.2.7 pool to provide a more rapid response to a fuel handling 2-105-01 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.

Remove the phrase, "as specified in 10 CFR 50, Appendix J," in

2. Table 6.2.6-3 2-105-02 Note 3.

E1-1

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number

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:

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

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

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

x Steam Generator Blowdown is released without processing.

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

3. Section 11.2 processed. 2-105-03

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:

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

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

x 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.

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

E1-2

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

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

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

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

x Condensate demineralizer regeneration waste is processed by the mobile demineralizer.

3. x Liquid releases from the Laundry and Hot Shower Drain Section 11.2 Tank and the Turbine Building drains were released without 2-105-03 (cont.)

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 generator 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 E1-3

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number 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

4. Section 12.3.1 sized and situated properly to support two operating units. The 2-105-04 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.

E1-4

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number 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 returned 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

4. the Auxiliary Building and the Service Building to maintain a Section 12.3.1 2-105-04 (cont.) central location for the inventory of standard portable decontamination equipment and supplies (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.

E1-5

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number 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.

4. Onsite Laboratory for Analysis of Chemical and Radiological Section 12.3.1 2-105-04 (cont.) 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."

E1-6

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number 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

5. 12.4 replaced. Steam generator replacement and the resultant 2-105-05 collective dose is not typical 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 replacement 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.

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

6. Section 13.1.3 requirements of RG 1.8, Revision 2, and ANSI/ANS 3.1- 2-105-06 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.

E1-7

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number

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 Section 1.1.1 7.1-1 Notes for consistency and clarity.

Section 1.2.2.2 Section 7.1.2 5. For Table 7.1-1, add entries and notes associated with Section 7.2.1.1.5 installation of the Common Q Post Accident Monitoring Section 7.4.2 System (PAMS) and the RM-1000 digital radiation monitors Section 7.4.3 Table 7.1-1 6. For Table 7.2-2, delete the word chamber from the Table 7.2-2 description of the P-7 interlock.

7. Section 7.5.1.2 2-105-07 Table 7.5-2 7. For Section 7.5.1.2 and Table 7.5-2, revise definition of References 7.1 Type A variables to reflect the fact that TVA includes References 7.2 variables that do not meet the Regulatory Guide (RG) 1.97 definition and identify those variables in Table 7.5-2.

References 7.3

8. For References 7.1, 7.2, and 7.3, correct reference entries Section 11.4.4 for WCAPs 17044 and 13869.

Section 12.3.4.1.3 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.

E1-8

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number On Table 6.3-8, Sheets 7 and 8 of 66, change the Method of

8. Table 6.3-8 Detection for the Stuck Closed and Stuck Open Failure Modes 2-105-08 associated with Items 8 and 9, as revised.

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 Gas Decay Tank Rupture 15.5-9, Doses from Loss of Coolant Accident 15.5-13, Doses from Recirculation Loop Leakage following a

9. Section 15.5 LOCA 2-105-09 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 3

15A-2, Accident Atmospheric Dilution Factors (sec/m )

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

10. Section 14.2 "DELETED" rather than say "Spent Fuel Pool Cooling 2-105-10 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.

E1-9

ENCLOSURE 1 WBN Unit 2 FSAR A105 Summary Listing of A105 FSAR Changes" Change Item Change Area Change Description Package No.

Number

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 10.

Section 14.2 Description in the fifth sentence to read, Testing will be 2-105-10 (cont.)

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.

1. On Pages 2.3-25 and 2.3-26 (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 Section 2.3

11. in the list of tables will be automatically changed) 2-105-11 Section 7.7

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 section, this heading in the table of contents will be automatically changed.)

Delete valves ISV-41-586, ISV-41-589, ISV-41-592 and ISV 12. Table 6.2.6-3 595 from FSAR Table 6.2.6-3 as shown on the attached FSAR 2-105-12 mark-up.

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.

Section 9.2.2.4

13. 2-105-13 Section 9.2.5.3 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.

E1-10

ENCLOSURE 2 WBN Unit 2 FSAR A105 Summary of Redacted Pages Chapter Page(S) Section No. Figure No. Basis For Redaction 1 1.2-15 1.2 1.2-1 Security Related, 10CFR2.390(d)(1) 1 1.2-16 1.2 1.2-2 Security Related, 10CFR2.390(d)(1) 1 1.2-17 1.2 1.2-3 Security Related, 10CFR2.390(d)(1) 1 1.2-18 1.2 1.2-4 Security Related, 10CFR2.390(d)(1) 1 1.2-19 1.2 1.2-5 Security Related, 10CFR2.390(d)(1) 1 1.2-20 1.2 1.2-6 Security Related, 10CFR2.390(d)(1) 1 1.2-21 1.2 1.2-7 Security Related, 10CFR2.390(d)(1) 1 1.2-22 1.2 1.2-8 Security Related, 10CFR2.390(d)(1) 1 1.2-23 1.2 1.2-9 Security Related, 10CFR2.390(d)(1) 1 1.2-24 1.2 1.2-10 Security Related, 10CFR2.390(d)(1) 1 1.2-25 1.2 1.2-11 Security Related, 10CFR2.390(d)(1) 1 1.2-26 1.2 1.2-12 Security Related, 10CFR2.390(d)(1) 1 1.2-27 1.2 1.2-13 Security Related, 10CFR2.390(d)(1) 1 1.2-28 1.2 1.2-14 Security Related, 10CFR2.390(d)(1) 1 1.2-29 1.2 1.2-15 Security Related, 10CFR2.390(d)(1) 2 2.2-7 2.2 2.2-1 Security Related, 10CFR2.390(d)(1) 2 2.2-8 2.2 2.2-2 Security Related, 10CFR2.390(d)(1) 2 2.4-89 2.4 2.4-2 Security Related, 10CFR2.390(d)(1) 2 2.4-159 2.4 2.4-24 Security Related, 10CFR2.390(d)(1) 2 2.4-162 2.4 2.4-27 Security Related, 10CFR2.390(d)(1) 2 2.4-163 2.4 2.4-28 Security Related, 10CFR2.390(d)(1) 2.4-40a 2 2.4-168 2.4 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) 2.4-40d 2 2.4-173 2.4 Security Related, 10CFR2.390(d)(1)

Sheet 1 2.4-40f 2 2.4-178 2.4 Security Related, 10CFR2.390(d)(1)

Sheet 1 2.4-40g 2 2.4-181 2.4 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)

E2-1

ENCLOSURE 2 WBN Unit 2 FSAR A105 Summary of Redacted Pages Chapter Page(S) Section No. Figure No. Basis For Redaction 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)

E2-2

ENCLOSURE 2 WBN Unit 2 FSAR A105 Summary of Redacted Pages Chapter Page(S) Section No. Figure No. Basis For Redaction 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)

E2-3

ENCLOSURE 3 WBN Unit 2 FSAR A105 List Of Files And File Sizes On The Security-Related OSM (OSM #1)

E3-1

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 - List of Files on Security-Related OSM File Name File Size - Bytes TVA_WBN-2_FSAR_Files 001_TVA_WB_FSAR_TOC.pdf 362,108 002_TVA_WB_FSAR_LRP.pdf 88,451 003_TVA_WB_FSAR_Section_1.pdf 4,643,883 004_TVA_WB_FSAR_Section_2_A.pdf 10,467,163 005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 44,606,435 005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 49,572,114 006_TVA_WB_FSAR_Section_2_C.pdf 2,107,389 007_TVA_WB_FSAR_Section_2_D.pdf 31,323,839 008_TVA_WB_FSAR_Section_2_E.pdf 47,312,480 009_TVA_WB_FSAR_Section_3_A.pdf 2,622,917 010_TVA_WB_FSAR_Section_3_B.pdf 7,063,082 011_TVA_WB_FSAR_Section_3_C.pdf 30,016,094 012_TVA_WB_FSAR_Section_3_D.pdf 11,764,620 013_TVA_WB_FSAR_Section_4.pdf 10,713,352 014_TVA_WB_FSAR_Section_5.pdf 9,119,079 015_TVA_WB_FSAR_Section_6_A.pdf 26,047,923 016_TVA_WB_FSAR_Section_6_B.pdf 7,617,151 017_TVA_WB_FSAR_Section_7.pdf 13,195,628 018_TVA_WB_FSAR_Section_8.pdf 29,723,997 019_TVA_WB_FSAR_Section_9_A.pdf 24,536,294 020_TVA_WB_FSAR_Section_9_B.pdf 16,485,358 021_TVA_WB_FSAR_Section_10.pdf 13,430,648 022_TVA_WB_FSAR_Section_11.pdf 3,965,291 023_TVA_WB_FSAR_Section_12.pdf 5,994,207 024_TVA_WB_FSAR_Section_13.pdf 3,240,070 025_TVA_WB_FSAR_Section_14.pdf 1,170,286 Page 1 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 - List of Files on Security-Related OSM File Name File Size - Bytes 026_TVA_WB_FSAR_Section_15.pdf 027_TVA_WB_FSAR_Section_16.pdf 028_TVA_WB_FSAR_Section_17.pdf Total 407,189,859 TVA_WBN-2_Oversized_FSAR_Figures 001_TVA_WB_FSAR_Figure_2.5_3.pdf 1,757,743 002_TVA_WB_FSAR_Figure_2.5_11.pdf 1,689,538 003_TVA_WB_FSAR_Figure_2.5_71.pdf 2,263,087 004_TVA_WB_FSAR_Figure_2.5_222.pdf 909,429 005_TVA_WB_FSAR_Figure_2.5_281_1.pdf 2,155,627 006_TVA_WB_FSAR_Figure_2.5_281_2.pdf 2,117,562 007_TVA_WB_FSAR_Figure_2.5_549_1.pdf 3,600,807 008_TVA_WB_FSAR_Figure_2.5_549_2.pdf 3,989,180 009_TVA_WB_FSAR_Figure_2.5_549_3.pdf 2,863,719 010_TVA_WB_FSAR_Figure_2.5_549_4.pdf 2,809,599 011_TVA_WB_FSAR_Figure_2.5_550.pdf 1,803,985 012_TVA_WB_FSAR_Figure_2.5_551.pdf 1,996,869 013_TVA_WB_FSAR_Figure_2.5_554_1.pdf 3,081,060 014_TVA_WB_FSAR_Figure_2.5_554_2.pdf 1,996,707 015_TVA_WB_FSAR_Figure_2.5_555.pdf 1,993,312 016_TVA_WB_FSAR_Figure_2.5_556.pdf 2,998,087 017_TVA_WB_FSAR_Figure_2.5_571_1.pdf 844,484 018_TVA_WB_FSAR_Figure_2.5_571_2.pdf 3,128,329 019_TVA_WB_FSAR_Figure_2.5_571_3.pdf 3,284,555 020_TVA_WB_FSAR_Figure_2.5_571_4.pdf 2,142,316 021_TVA_WB_FSAR_Figure_2.5_572.pdf 2,196,945 Page 2 of 3

ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 - List of Files on Security-Related OSM File Name File Size - Bytes 022_TVA_WB_FSAR_Figure_2.5_573.pdf 2,013,286 023_TVA_WB_FSAR_Figure_2.5_576_1.pdf 3,238,525 024_TVA_WB_FSAR_Figure_2.5_576_2.pdf 2,151,750 025_TVA_WB_FSAR_Figure_2.5_577.pdf 2,207,622 026_TVA_WB_FSAR_Figure_2.5_578.pdf 2,080,032 027_TVA_WB_FSAR_Figure_2.5_579.pdf 2,308,985 028_TVA_WB_FSAR_Figure_2.5_583.pdf 2,487,346 029_TVA_WB_FSAR_Figure_2.5_588.pdf 2,528,515 030_TVA_WB_FSAR_Figure_2.5_589.pdf 2,480,438 031_TVA_WB_FSAR_Figure_2.5_594.pdf 13,054,127 032_TVA_WB_FSAR_Figure_2.5_595.pdf 2,323,267 033_TVA_WB_FSAR_Figure_2.5_596.pdf 5,732,107 034_TVA_WB_FSAR_Figure_2.5_597.pdf 1,287,336 035_TVA_WB_FSAR_Figure_2.5_602.pdf 5,549,537 036_TVA_WB_FSAR_Figure_2.5_603.pdf 4,830,835 037_TVA_WB_FSAR_Figure_2.5_604.pdf 6,392,279 038_TVA_WB_FSAR_Figure_2.5_605.pdf 20,823,108 Total 131,112,035 TVA_WBN-2_Oversized_FSAR_Table 001_TVA_WB_FSAR_Table_6.2.4-1.pdf 1,215,573 Total 1,215,573 Page 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 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 List of Files on Publicly Available OSM File Name File Size - Bytes TVA_WBN-2_FSAR_Files 001_TVA_WB_FSAR_TOC.pdf 362,108 002_TVA_WB_FSAR_LRP.pdf 88,451 003_TVA_WB_FSAR_Section_1.pdf 837,309 004_TVA_WB_FSAR_Section_2_A.pdf 10,130,617 005_TVA_WB_FSAR_Section_2_B_Part_1_of_2.pdf 34,359,034 005_TVA_WB_FSAR_Section_2_B_Part_2_of_2.pdf 43,314,021 006_TVA_WB_FSAR_Section_2_C.pdf 2,107,389 007_TVA_WB_FSAR_Section_2_D.pdf 31,323,839 008_TVA_WB_FSAR_Section_2_E.pdf 45,933,088 009_TVA_WB_FSAR_Section_3_A.pdf 2,331,495 010_TVA_WB_FSAR_Section_3_B.pdf 5,661,310 011_TVA_WB_FSAR_Section_3_C.pdf 25,183,693 012_TVA_WB_FSAR_Section_3_D.pdf 11,495,906 013_TVA_WB_FSAR_Section_4.pdf 10,713,352 014_TVA_WB_FSAR_Section_5.pdf 9,119,079 015 TVA WB FSAR Section 6 A pdf 015_TVA_WB_FSAR_Section_6_A.pdf 23 167 481 23,167,481 016_TVA_WB_FSAR_Section_6_B.pdf 7,617,151 017_TVA_WB_FSAR_Section_7.pdf 13,195,628 018_TVA_WB_FSAR_Section_8.pdf 26,763,889 019_TVA_WB_FSAR_Section_9_A.pdf 24,275,275 020_TVA_WB_FSAR_Section_9_B.pdf 15,270,859 021_TVA_WB_FSAR_Section_10.pdf 13,430,648 022_TVA_WB_FSAR_Section_11.pdf 3,965,291 023_TVA_WB_FSAR_Section_12.pdf 1,726,180 024_TVA_WB_FSAR_Section_13.pdf 3,240,070 025_TVA_WB_FSAR_Section_14.pdf 1,170,286 Note: Byte amounts in italics are redacted files. Page 1 of 3

ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 List of Files on Publicly Available OSM File Name File Size - Bytes 026_TVA_WB_FSAR_Section_15.pdf 46,591,104 027_TVA_WB_FSAR_Section_16.pdf 148,383 028_TVA_WB_FSAR_Section_17.pdf 145,004 Total 413,667,940 TVA_WBN-2_Oversized_FSAR_Figures 001_TVA_WB_FSAR_Figure_2.5_3.pdf 1,757,743 002_TVA_WB_FSAR_Figure_2.5_11.pdf 1,689,538 003_TVA_WB_FSAR_Figure_2.5_71.pdf 2,263,087 004_TVA_WB_FSAR_Figure_2.5_222.pdf 909,429 005_TVA_WB_FSAR_Figure_2.5_281_1.pdf 2,155,627 006_TVA_WB_FSAR_Figure_2.5_281_2.pdf 2,117,562 007_TVA_WB_FSAR_Figure_2.5_549_1.pdf 3,600,807 008_TVA_WB_FSAR_Figure_2.5_549_2.pdf 3,989,180 009_TVA_WB_FSAR_Figure_2.5_549_3.pdf 2,863,719 010_TVA_WB_FSAR_Figure_2.5_549_4.pdf 2,809,599 011 TVA WB FSAR Figure 2 5 550 pdf 011_TVA_WB_FSAR_Figure_2.5_550.pdf 1 803 985 1,803,985 012_TVA_WB_FSAR_Figure_2.5_551.pdf 1,996,869 013_TVA_WB_FSAR_Figure_2.5_554_1.pdf 3,081,060 014_TVA_WB_FSAR_Figure_2.5_554_2.pdf 1,996,707 015_TVA_WB_FSAR_Figure_2.5_555.pdf 1,993,312 016_TVA_WB_FSAR_Figure_2.5_556.pdf 2,998,087 017_TVA_WB_FSAR_Figure_2.5_571_1.pdf 844,484 018_TVA_WB_FSAR_Figure_2.5_571_2.pdf 3,128,329 019_TVA_WB_FSAR_Figure_2.5_571_3.pdf 3,284,555 020_TVA_WB_FSAR_Figure_2.5_571_4.pdf 2,142,316 021_TVA_WB_FSAR_Figure_2.5_572.pdf 2,196,945 Note: Byte amounts in italics are redacted files. Page 2 of 3

ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 105 List of Files on Publicly Available OSM File Name File Size - Bytes 022_TVA_WB_FSAR_Figure_2.5_573.pdf 2,013,286 023_TVA_WB_FSAR_Figure_2.5_576_1.pdf 3,238,525 024_TVA_WB_FSAR_Figure_2.5_576_2.pdf 2,151,750 025_TVA_WB_FSAR_Figure_2.5_577.pdf 2,207,622 026_TVA_WB_FSAR_Figure_2.5_578.pdf 2,080,032 027_TVA_WB_FSAR_Figure_2.5_579.pdf 2,308,985 028_TVA_WB_FSAR_Figure_2.5_583.pdf 2,487,346 029_TVA_WB_FSAR_Figure_2.5_588.pdf 2,528,515 030_TVA_WB_FSAR_Figure_2.5_589.pdf 2,480,438 031_TVA_WB_FSAR_Figure_2.5_594.pdf 13,054,127 032_TVA_WB_FSAR_Figure_2.5_595.pdf 2,323,267 033_TVA_WB_FSAR_Figure_2.5_596.pdf 5,732,107 034_TVA_WB_FSAR_Figure_2.5_597.pdf 1,287,336 035_TVA_WB_FSAR_Figure_2.5_602.pdf 5,549,537 036_TVA_WB_FSAR_Figure_2.5_603.pdf 4,830,835 037_TVA_WB_FSAR_Figure_2.5_604.pdf 6,392,279 038 TVA WB FSAR Figure 2 5 605 pdf 038_TVA_WB_FSAR_Figure_2.5_605.pdf 20 823 108 20,823,108 Total 131,112,035 TVA_WBN-2_Oversized_FSAR_Table 001_TVA_WB_FSAR_Table_6.2.4-1.pdf 1,215,573 Total 1,215,573 Note: Byte amounts in italics are redacted files. Page 3 of 3

ENCLOSURE 5 Deviation Request from Regulatory Guide 1.68, Revision 2

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 (TAVG) 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)

E5-1