ML11187A335

OL - FW: NRC PM Open Items List 6-20-11.docx

ML11187A335
Person / Time
Site:	Watts Bar
Issue date:	06/17/2011
From:	- No Known Affiliation
To:	Division of Operating Reactor Licensing
References
Download: ML11187A335 (25)

Text

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

Sent: Friday, June 17, 2011 9:28 AM To: Poole, Justin; Milano, Patrick; Campbell, Stephen Cc: Arent, Gordon; Smith, James D; Bryan, Robert H Jr; Smith, James D

Subject:

FW: NRC PM Open Items List 6-20-11.docx Attachments: NRC PM Open Items List 6-20-11.docx For next phone call.

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

Désireé L. Boyd WBN 2 Licensing Support Sun Technical Services dlboyd@tva.gov 4233658764 1

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 422 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF1FFA529F)

Subject:

FW: NRC PM Open Items List 6-20-11.docx Sent Date: 6/17/2011 9:28:19 AM Received Date: 6/17/2011 9:28:54 AM From: Boyd, Desiree L Created By: dlboyd@tva.gov Recipients:

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

Tracking Status: None "Smith, James D" <jdsmith@tva.gov>

Tracking Status: None "Bryan, Robert H Jr" <rhbryan@tva.gov>

Tracking Status: None "Smith, James D" <smith1jd@westinghouse.com>

Tracking Status: None "Poole, Justin" <Justin.Poole@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 243 6/17/2011 9:28:54 AM NRC PM Open Items List 6-20-11.docx 59824 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Page 1 of 23 NRC PM Open Items List 6/20/11 (423) 751-6338 ID 657601 No. Description Status Additional Comments Resp Org/Person

1. Cyber Security Plan/Controls and Plan for NRC Inspection in 2011 Heinrich/Snyder Implementation Common (Bryan)

Systems Provide detail for systems (unit specific and common) 6/8/11A which will be complete and which will not be complete for Unit 2 fuel load.

Identify Required Exemptions 6/8/11A Provide forecast for Inspection Readiness 6/8/11A NRC TI issued TBD NRC Table Top/Pilot Oct 2011 Procedures complete 9/30/11 Inspection Dec 2011

Page 2 of 23 No. Description Status Additional Comments Resp Org/Person

2. Instrumentation RAI List (Knuettel) Ongoing RAI Responses Eng/Hilmes (Smith) 6/22/11 Provide response to Q377 and Q375, item 9

3. Resolve Licensing Basis Preservation 6/17/11A TVA to provide QA audit results. Audit is complete. Eng/Freeman Self Assessment PERs (Crouch) Will docket the audit. (Smith)

4. Status of GSI 199 Eastern Seismicity Fall 2011 No action pending upcoming Generic Letter TVA/NRR (Crouch)

5. Complete Implementation (Hemmer) Diesel Diesel is onsite, need support equipment Hemmer 8/1/11 (Smith)

Pump Additional clarification to phase I actions will be Relocation needed. Fleet wide issue.

10/1/11 Procedures Issued 6/30/11 Inspection -

November 2011 Phase I commitments 8/1/11

6. Provide feedback on the status of NRC SSER 23 NRC to provide status of review in SSER 23 NRR review of Integrated Safeguards Test submittal

Page 3 of 23 No. Description Status Additional Comments Resp Org/Person

7. Document Control Issues for two letters 6/15/11 7/15, 10/5, 10/21 and 10/29 letters. NRC to reprint Licensing/Boyd 7/15 letter and provide to NRC Document control.

TVA/Bechtel to provide non-proprietary version of documents that can be released to the public. TVA to provide revised letter that says non-prop once prop documents removed. NRC action to contact Kenny Nguyen, NRC Document Control regarding A102.

Additional copy of A102 provided to NRC on 6/7/11.

8. Chapter 15.5 RAIs TBD Additional question regarding meteorology data from Wastrack 2008-2009. Calc revisions required. TVA formulating (Bryan) plan/schedule. Small increases in doses expected except control room which will decrease. NRC is targeting SSER 24 (early August) to contain this updated information. NRC to perform confirmatory runs in parallel. Will provide data by 6/27/11.

9. Fire Protection Report Questions TBD Justifications - date will be determined by 6/17/11. ENG/Hilmes regarding OMA (Crouch) 6/21/11 Set 5 RAIs TBD Clarification to 5/26/11 ltr Qs VII-2, VIII-13,14 and 6/7/11 ltr Qs II-43, VIII telecom week of 6/13/11 6/30/11 Technical Meeting - pipe corrosion TBD Group 6 RAIs to come shortly.

10. IST Tech Spec Change 6/17/11 Schedule by 6/17/11. TVA Corporate Pre-submittal meeting being arranged. Licensing (Shea)

11. Tech Spec Revisions from latest T/S 6/20/11 Submittal to address NRC review comments Licensing/Elton markup and NRC Review comments (Bryan)

TBD CSST A & B June, 2011 I-131 DEI June, 2011 Diesel Generator Frequency

Page 4 of 23 No. Description Status Additional Comments Resp Org/Person

12. ASME III to XI transition Need NRC When does ISI program begin with partial plant N-3? Eng/Helms Letter Are repairs/mods after N-5 controlled under Section III (Crouch) or Section XI? The timing for the NIS-2 in the letter does not comply with the ASME Code . The NIS-2 must be before commercial operation.

Review Code Cases 801/802 vs TVA letter for conflicts. Review complete - no impact.

13. Chapter 11/FSEIS RAIs 6/20/11 NRC Computer Code Input Request Chem/Woods (Bryan) 7/29/11 Cost Benefit Analyses - need to improve date complete NRC to provide additional RAIs

14. Letter to notify NRC when Vital Area 11/1/11 Security Plan Update - Boundary to be restored by Lic/Crouch Boundary returned to original location 9/30/11

15. Part 70 License EA - 6/13/11A NRC to issue Part 70 license. Fuel receipt is 6/20/11. Milano FL - 6/15/11

16. ACRS Topics 7/12/11 Improvements, Inspection status, Refurb status, Construction Status, Japan, IST Re-Presentation, Cyber Security, Ch 7 digital upgrades. Agenda has been finalized.

17. SAMDA RAIs 6/17/11A 5 questions regarding 2nd submittal

18. SSER 22/23 Open Items Response 7/15/11 7/15 is the target date for the next SSER update. The expanded HH list and its status is provided at the end of this letter.

19. Chapter 12 RAI on Instrument Channel 6/24/11 ENG/Hilmes Operability Tests

20. Transient Analysis issues 6/28-30/11 & TVA/WEC confirming availability of personnel. Final ENG/Koontz 7/1/11 until audit plan to come. WEC/Morgan Additional Follow up Audit noon, if necessary 6/13/11A NRC to provide audit questions

21. FSAR A105 7/29/11 Lic/Stockton

Page 5 of 23 No. Description Status Additional Comments Resp Org/Person

22. IEB 88-02 SG Tube Cracking 6/13-17/11 What are the SG inspection plans in light of the Corp SG/

NRC to setup experience with a French reactor exhibiting SG tube Webber telecon cracking early? Is TVA planning to change the ISI/Tinley inspection plan due to this operating experience?

23. Develop list of planned License 9/1/11 Review Unit 1 SER for exemptions. NRR/TVA Conditions, Exemptions and Relief (Bryan)

Requests (Crouch)

24. Submit final REP prior to fuel load 10/1/11 Submit Final REP and EPIPs 180 days prior to OL. EP/

(Spink) Detchemendy (Bryan)

25. Issue two Unit Offsite Dose Calculation 9/1/11 Chemistry/

Manual (Beach) Review TS Chapter 5 Woods programs also (Bryan)

26. Copy of Site Plan for NSIR TBD No action until inspection scheduled. Fire Ops/Sterchi NRC to determine level of detail is needed.

27. Issue Unit 2 Completion Letter (Crouch) 3/1/12 Licensing

28. Combined U1/U2 FSAR (Stockton) 3/1/12 Licensing

29. Submit final as-constructed FSAR 10/1/11 Licensing/

figures Stockton

30. Verify Tech Spec Setpoints match calcs 8/1/11 Eng/Hilmes (Bryan)

31. Letter to terminate Part 30/40 License 4/1/12 Licensing after receipt of Part 50 License (Crouch)

32. B 2011-01 60 day response Licensing (Gordon)

33. TMI action items Review list Licensing (Gordon)

Page 6 of 23 SSER NRC SSER Item Item TVA Status No. Description Status

1. Review evaluations and corrective actions For NRC Inspection /

associated with a power assisted cable pull. Review (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)

2. Conduct appropriate inspection activities to For NRC Inspection /

verify cable lengths used in calculations and Review analysis match as-installed configuration.

(NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)

3. Confirm TVA submitted update to FSAR Response provided in TVA section 8.3.1.4.1. (NRC safety evaluation to NRC letter dated April 6, dated August 31, 2009, ADAMS Accession 2011.

No. ML092151155)

4. Conduct appropriate inspection activities to Closed by IR 2010604 verify that TVAs maximum SWBP criteria for signal level and coaxial cables do not exceed the cable manufacturers maximum SWBP criteria. (NRC safety evaluation dated August 31, 2009, ADAMS Accession No. ML092151155)

5. Verify timely submittal of pre-startup core Response provided in TVA map and perform technical review. (TVA to NRC letter dated April 6, letter dated September 7, 2007, ADAMS 2011.

Accession No. ML072570676)

6. Verify implementation of TSTF-449. (TVA Response provided in TVA letter dated September 7, 2007, ADAMS to NRC letter dated April 6, Accession No. ML072570676) 2011.

7. Verify commitment completion and review For NRC Inspection /

electrical design calculations. (TVA letter Review dated October 9, 1990, ADAMS Accession No. ML073551056)

8. Verify rod control system operability during Response provided in TVA

Page 7 of 23 SSER NRC SSER Item Item TVA Status No. Description Status power ascension. TVA should provide a pre- to NRC letter dated April 6, startup map to the NRC staff indicating the 2011.

rodded fuel assemblies and a projected end of cycle burnup of each rodded assembly for the initial fuel cycle 6-months prior to fuel load. (NRC safety evaluation dated May 3, 2010, ADAMS Accession No. ML101200035)

9. Confirm that education and experience of For NRC Inspection /

management and principal supervisory Review positions down through the shift supervisory level conform to Regulatory Guide 1.8.

(Section 13.1.3)

10. Confirm that TVA has an adequate number TVA to answer later.

of licensed and non-licensed operators in the training pipeline to support the preoperational test program, fuel loading, and dual unit operation. (Section 13.1.3)

11. The plant administrative procedures should For NRC Inspection /

clearly state that, when the Assistant Shift Review Engineer assumes his duties as Fire Brigade Leader, his control room duties are temporarily assumed by the Shift Supervisor (Shift Engineer), or by another SRO, if one is available. The plant administrative procedures should clearly describe this transfer of control room duties. (Section 13.1.3)

12. TVAs implementation of NGDC PP-20 and For NRC Inspection /

EDCR Appendix J is subject to future NRC Review audit and inspection. (Section 25.9)

13. TVA is expected to submit an IST program TVA to answer later.

and specific relief requests for WBN Unit 2

Page 8 of 23 SSER NRC SSER Item Item TVA Status No. Description Status nine months before the projected date of OL issuance. (Section 3.9.6)

14. TVA stated that the Unit 2 PTLR is included Response provided in TVA in the Unit 2 System Description for the to NRC letter dated April 6, Reactor Coolant System (WBN2-68-4001), 2011.

which will be revised to reflect required revisions to the PTLR by September 17, 2010. (Section 5.3.1)

15. TVA should confirm to the NRC staff the Response provided in TVA completion of Primary Stress Corrosion to NRC letter dated April 6, Cracking (PWSCC) mitigation activities on 2011.

the Alloy 600 dissimilar metal butt welds (DMBWs) in the primary loop piping. (Section 3.6.3)

16. Based on the uniqueness of EQ, the NRC For NRC Inspection /

staff must perform a detailed inspection and Review evaluation prior to fuel load to determine how the WBN Unit 2 EQ program complies with the requirements of 10 CFR 50.49. (Section 3.11.2)

17. The NRC staff should verify the accuracy of For NRC Inspection /

the WBN Unit 2 EQ list prior to fuel load. Review (Section 3.11.2.1)

18. Based on the extensive layup period of Response provided in TVA equipment within WBN Unit 2, the NRC staff to NRC letter dated April 6, must review, prior to fuel load, the 2011.

assumptions used by TVA to re-establish a baseline for the qualified life of equipment.

The purpose of the staffs review is to ensure that TVA has addressed the effects of environmental conditions on equipment during the layup period. (Section 3.11.2.2)

Page 9 of 23 SSER NRC SSER Item Item TVA Status No. Description Status

19. The NRC staff should complete its review of For NRC Inspection /

TVAs EQ Program procedures for WBN Unit Review 2 prior to fuel load. (Section 3.11.2.2.1)

20. Resolve whether or not routine maintenance Response provided in TVA activities should result in increasing the EQ to NRC letter dated April 6, of the 6.9 kV motors to Category I status in 2011.

accordance with 10 CFR 50.49. (Section 3.11.2.2.1).

21. The NRC staff should confirm that the For NRC Inspection /

Electrical Penetration Assemblies (EPAs) are Review installed in the tested configuration, and that the feedthrough module is manufactured by the same company and is consistent with the EQ test report for the EPA. (Section 3.11.2.2.1)

22. TVA must clarify its use of the term Response provided in TVA equivalent (e.g., identical, similar) regarding to NRC letter dated April 6, the replacement terminal blocks to the NRC 2011.

staff. If the blocks are similar, then a similarity analysis should be completed and presented to the NRC for review. (Section 3.11.2.2.1)

23. Resolve whether or not TVAs reasoning for Response provided in TVA not upgrading the MSIV solenoid valves to to NRC letter dated April 6, Category I is a sound reason to the contrary, 2011.

as specified in 10 CFR 50.49(l). (Section 3.11.2.2.1)

24. The NRC staff requires supporting Response provided in TVA documentation from TVA to justify its to NRC letter dated April 6, establishment of a mild environment 2011.

threshold for total integrated dose of less than 1x103 rads for electronic components

Page 10 of 23 SSER NRC SSER Item Item TVA Status No. Description Status such as semiconductors or electronic components containing organic material.

(Section 3.11.2.2.1)

25. Prior to the issuance of an operating license, TVA to answer later.

TVA is required to provide satisfactory documentation that it has obtained the maximum secondary liability insurance coverage pursuant to 10 CFR 140.11(a)(4),

and not less than the amount required by 10 CFR 50.54(w) with respect to property insurance, and the NRC staff has reviewed and approved the documentation. (Section 22.3)

26. For the scenario with an accident in one unit Response provided in TVA and concurrent shutdown of the second unit to NRC letter dated April 6, without offsite power, TVA stated that Unit 2 2011.

pre-operational testing will validate the diesel response to sequencing of loads on the Unit 2 emergency diesel generators (EDGs). The NRC staff will evaluate the status of this issue and will update the status of the EDG load response in a future SSER. (Section 8.1)

27. TVA should provide a summary of margin Response provided in TVA studies based on scenarios described in to NRC letter dated April 6, Section 8.1 for CSSTs A, B, C, and D. 2011.

(Section 8.2.2)

28. TVA should provide to the NRC staff a Response provided in TVA detailed discussion showing that the load tap to NRC letter dated April 6, changer is able to maintain the 6.9 kV bus 2011.

voltage control band given the normal and post-contingency transmission operating

Page 11 of 23 SSER NRC SSER Item Item TVA Status No. Description Status voltage band, bounding voltage drop on the grid, and plant conditions. (Section 8.2.2)

29. TVA should provide the transmission system Response provided in TVA specifics (grid stability analyses) to the NRC to NRC letter dated June 7, staff. In order to verify compliance with GDC 2011.

17, the results of the grid stability analyses must indicate that loss of the largest electric supply to the grid, loss of the largest load from the grid, loss of the most critical transmission line, or loss of both units themselves, will not cause grid instability.

(Section 8.2.2)

30. TVA should confirm that all other safety- TVA to answer later.

related equipment (in addition to the Class 1E motors) will have adequate starting and running voltage at the most limiting safety related components (such as motor operated valves, contactors, solenoid valves or relays) at the degraded voltage relay setpoint dropout setting. TVA should also confirm that the final Technical Specifications are properly derived from these analytical values for the degraded voltage settings. (Section 8.3.1.2)

31. TVA should evaluate the re-sequencing of Response provided in TVA loads, with time delays involved, in the to NRC letter dated April 6, scenario of a LOCA followed by a delayed 2011.

LOOP, and ensure that all loads will be sequenced within the time assumed in the accident analysis. (Section 8.3.1.11)

32. TVA should provide to the NRC staff the TVA to answer later.

details of the administrative limits of EDG

Page 12 of 23 SSER NRC SSER Item Item TVA Status No. Description Status voltage and speed range, and the basis for its conclusion that the impact is negligible, and describe how it accounts for the administrative limits in the Technical Specification surveillance requirements for EDG voltage and frequency. (Section 8.3.1.14)

33. TVA stated in Attachment 9 of its letter dated Response provided in TVA July 31, 2010, that certain design change to NRC letter dated April 6, notices (DCNs) are required or anticipated 2011.

for completion of WBN Unit 2, and that these DCNs were unverified assumptions used in its analysis of the 125 V dc vital battery system. Verification of completion of these DCNs to the NRC staff is necessary prior to issuance of the operating license. (Section 8.3.2.3)

34. TVA stated that the method of compliance Response provided in TVA with Phase I guidelines would be to NRC letter dated April 6, substantially similar to the current Unit 1 2011.

program and that a new Section 3.12 will be added to the Unit 2 FSAR that will be materially equivalent to Section 3.12 of the current Unit 1 FSAR. (Section 9.1.4)

35. TVA should provide information to the NRC Response provided in TVA staff that the CCS will produce feedwater to NRC letter dated June 7, purity in accordance with BTP MTEB 5-3 or, 2011.

alternatively, provide justification for producing feedwater purity to another acceptable standard. (Section 10.4.6)

36. TVA should provide information to the NRC Response provided in TVA staff to enable verification that the SGBS to NRC letter dated April 6,

Page 13 of 23 SSER NRC SSER Item Item TVA Status No. Description Status meets the requirements and guidance 2011.

specified in the SER or provide justification that the SGBS meets other standards that demonstrate conformance to GDC 1 and GDC 14. (Section 10.4.8)

37. The NRC staff will review the combined WBN TVA to answer later.

Unit 1 and 2 Appendix C prior to issuance of the Unit 2 OL to confirm (1) that the proposed Unit 2 changes were incorporated into Appendix C, and (2) that changes made to Appendix C for Unit 1 since Revision 92 and the changes made to the NP-REP since Revision 92 do not affect the bases of the staffs findings in this SER supplement.

(Section 13.3.2)

38. The NRC staff will confirm the availability and For NRC Inspection /

operability of the ERDS for Unit 2 prior to Review issuance of the Unit 2 OL. (Section 13.3.2.6)

39. The NRC staff will confirm the adequacy of For NRC Inspection /

the communications capability to support Review dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.6)

40. The NRC staff will confirm the adequacy of For NRC Inspection /

the emergency facilities and equipment to Review support dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.8)

41. TVA committed to (1) update plant data For NRC Inspection /

displays as necessary to include Unit 2, and Review (2) to update dose assessment models to provide capabilities for assessing releases from both WBN units. The NRC staff will confirm the adequacy of these items prior to

Page 14 of 23 SSER NRC SSER Item Item TVA Status No. Description Status issuance of the Unit 2 OL. (Section 13.3.2.9)

42. The NRC staff will confirm the adequacy of For NRC Inspection /

the accident assessment capabilities to Review support dual unit operations prior to issuance of the Unit 2 OL. (Section 13.3.2.9)

43.Section V of Appendix E to 10 CFR Part 50 TVA to answer later.

requires TVA to submit its detailed implementing procedures for its emergency plan no less than 180 days before the scheduled issuance of an operating license.

Completion of this requirement will be confirmed by the NRC staff prior to the issuance of an operating license. (Section 13.3.2.18)

44. TVA should provide additional information to Response provided in TVA clarify how the initial and irradiated RTNDT to NRC letter dated April 6, was determined. (Section 5.3.1) 2011.

45. TVA stated in its response to RAI 5.3.2-2, Response provided in TVA dated July 31, 2010, that the PTLR would be to NRC letter dated April 6, revised to incorporate the COMS arming 2011.

temperature. (Section 5.3.2)

46. The LTOP lift settings were not included in Response provided in TVA the PTLR, but were provided in TVAs to NRC letter dated April 6, response to RAI 5.3.2-2 in its letter dated 2011.

July 31, 2010. TVA stated in its RAI response that the PTLR would be revised to incorporate the LTOP lift settings into the PTLR. (Section 5.3.2)

47. The NRC staff noted that TVAs changes to Response provided in TVA Section 6.2.6 in FSAR Amendment 97, to NRC letter dated June 7, regarding the implementation of Option B of 2011.

Appendix J, were incomplete, because

Page 15 of 23 SSER NRC SSER Item Item TVA Status No. Description Status several statements remained regarding performing water-sealed valve leakage tests as specified in 10 CFR [Part] 50, Appendix J. With the adoption of Option B, the specified testing requirements are no longer applicable; Option A to Appendix J retains these requirements. The NRC discussed this discrepancy with TVA in a telephone conference on September 28, 2010. TVA stated that it would remove the inaccurate reference to Appendix J for specific water testing requirements in a future FSAR amendment. (Section 6.2.6)

48. The NRC staff should verify that its Response provided in TVA conclusions in the review of FSAR Section to NRC letter dated June 7, 15.4.1 do not affect the conclusions of the 2011.

staff regarding the acceptability of Section 6.5.3. (Section 6.5.3)

49. The NRC staff was unable to determine how For NRC Inspection /

TVA linked the training qualification Review requirements of ANSI N45.2-1971 to TVA Procedure TI-119. Therefore, the implementation of training and qualification for inspectors will be the subject of future NRC staff inspections. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050)

50. TVA stated that about 5 percent of the For NRC Inspection /

anchor bolts for safety-related pipe supports Review do not have quality control documentation, because the pull tests have not yet been performed. Since the documentation is still

Page 16 of 23 SSER NRC SSER Item Item TVA Status No. Description Status under development, the NRC staff will conduct inspections to follow-up on the adequate implementation of this construction refurbishment program requirement. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050)

51. The implementation of TVA Procedure TI- For NRC Inspection /

119 will be the subject of NRC follow-up Review inspection to determine if the construction refurbishment program requirements are being adequately implemented. (NRC letter dated July 2, 2010, ADAMS Accession No. ML101720050) 52[A] TVA should provide an update to the FSAR Response provided in TVA replacing Table 12.2-3 with the expected source to NRC letter dated June 7, strength values of the freshly irradiated IITAs. 2011.

(Section 12.3) 53 TVA should provide an update to the FSAR reflecting the information provided in its letter dated October 4, 2010, regarding the WBN radiation protection design features, including controlled access areas, decontamination areas, and onsite laboratories and counting rooms. (Section 12.4) 54 TVA should provide adequate technical justification to the staff to relax the frequency of the radiation monitor channel quarterly operability tests. TVA should provide sufficient information to the staff to determine that the portable airborne radiation monitors comply with the requirements of 10 CFR 20.1501. TVA should provide sufficient information to the staff to determine that the licensing or TVA program requirements for the calibration and operability testing of area radiation monitors are sufficient to meet the regulatory requirements of 10 CFR 20.1501.

(Section 12.4) 55 TVA should provide sufficient information to the staff to demonstrate that the two area radiation monitors for the Spent Fuel Pit comply with the requirements of 10 CFR

Page 17 of 23 SSER NRC SSER Item Item TVA Status No. Description Status 70.24 and 10 CFR 50.68 for radiation monitoring in areas where fuel is handled or stored. (Section 12.4) 56 TVA should update the FSAR to reflect the information regarding the dose assessment program provided in its letter the the NRC dated June 3, 2010. (Section 12.5) 57 TVA should update the FSAR to reflect the qualification standards of the RPM as provided in its letter to the NRC dated October 4, 2010. (Section 12.6) 58 The staff has insufficient information to conclude that TVA has taken appropriate actions to reduce radiation levels and increase the capability of operators to control and mitigate the consequences of an accident at WBN Unit 2, in accordance with the guidance of NUREG-0737, Item II.B.2, or can maintain occupational doses to plant operators within the requirements of GDC 19. Therefore, the staff cannot conclude that the plant shielding for WBN Unit 2 is acceptable. (Section 12.7.1) 59[B] The staff's evaluation of the compatibility of the Response provided in TVA ESF system materials with containment sprays to NRC letter dated June 7, and core cooling water in the event of a LOCA is 2011.

incomplete pending resolution of GSI-191 for WBN Unit 2. (Section 6.1.1.4) 60[C] TVA should amend the FSAR description of the Response provided in TVA design and operation of the spent fuel pool to NRC letter dated June 7, cooling and cleanup system in FSAR Section 9.1.3 2011.

as proposed in its December 21, 2010, letter to the NRC. (Section 9.1.3) 61[D] TVA should provide information to the NRC staff Will result in a License to demonstrate that PAD 4.0 can conservatively Condition.

calculate the fuel temperature and other impacted variables, such as stored energy, given the lack of a fuel thermal conductivity degradation model.

(Section 4.2.2.1) 62[E] Confirm TVA's change to FSAR Section 10.4.9 to Response provided in TVA reflect its intention to operate with each CST to NRC letter dated June 7,

Page 18 of 23 SSER NRC SSER Item Item TVA Status No. Description Status isolated from the other. (Section 10.4.9) 2011.

63[F] TVA should confirm to the NRC staff that testing TVA to answer later.

prior to Unit 2 fuel load has demonstrated that two-way communications is impossible with the Eagle 21 communications interface. (Section 7.2.1.1) 64[G] TVA stated that, "Post modification testing will be For NRC Inspection /

performed to verify that the design change Review corrects the Eagle 21, Rack 2 RTD accuracy issue prior to WBN Unit 2 fuel load. This issue is open pending NRC review of the testing results.

65[H] TVA should provide justification to the staff Response provided in TVA regarding why different revisions of WCAP- to NRC letter dated June 7, 13869 are referenced in WBN Unit 1 and Unit 2. 2011.

(Section 7.2.1.1) 66[I] TVA should clarify FSAR Section 9.2.5 to add the TVA to answer later.

capability of the UHS to bring 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 />. (SRP Section 9.2.5) 67[J] TVA should confirm, and the NRC staff should For NRC Inspection /

verify, that the component cooling booster pumps Review for Unit 2 are above PMF level. (Section 9.2.2) 68[K] TVA should clarify to the NRC staff how the CSS TVA to answer later.

complies with GDC 5. (Section 9.2.2) 69[L] The WBN Unit 2 RCS vent system is acceptable, For NRC Inspection /

pending verification that the RCS vent system is Review installed. (Section 5.4.5) 70[M] TVA should provide the revised WBN Unit 2 PSI TVA to answer later.

program ASME Class 1, 2, and 3 Supports "Summary Tables," to include numbers of components so that the NRC staff can verify that the numbers meet the reference ASME Code.

Page 19 of 23 SSER NRC SSER Item Item TVA Status No. Description Status (Section 3.2.3 of Appendix Z of this SSER) 71[N] TVA should confirm to the staff the replacement Response provided in TVA of the current Unit 2 clevis insert bolts to the to NRC letter dated June 7, latest design, which uses an X-750 alloy with an 2011.

HTH process, rolled threads, and a larger radius on the undercut of the cap screw head. (Section 3.9.5) 72[O] Based on its review, the staff asked TVA several For NRC Inspection /

questions regarding the ICC instrumentation. Review TVA responded to the staff questions by letter dated October 26, 2010 (ADAMS Accession No. ML103020322). The NRC staff has not completed the review of the additional information provided by TVA. The staff will provide its evaluation after completion of that review. (Section 4.4.8) 73[P] The NRC staff will inspect to confirm that TVA For NRC Inspection /

has completed the WBN Unit 2 EOPs prior to fuel Review load. (Section 7.5.3) 74[Q] The NRC staff will verify installation of the For NRC Inspection /

acoustic-monitoring system for the power- Review operated relief valve (PORV) position indication in WBN Unit 2 before fuel load. (Section 7.8.1) 75[R] The NRC staff will verify that the test procedures For NRC Inspection /

and qualification testing for auxiliary feedwater Review initiation and control and flow indication are completed in WBN Unit 2 before fuel load.

(Section 7.8.2) 76[S] The NRC staff will verify that the derivative time For NRC Inspection /

constant is set to zero in WBN Unit 2 before fuel Review load. (Section 7.8.3) 77 It is unclear to the NRC staff which software V&V documents are applicable to the HRCAR monitors. TVA

Page 20 of 23 SSER NRC SSER Item Item TVA Status No. Description Status should clarify which software V&V documents are applicable, in order for the staff to complete its evaluation.

(Section 7.5.2.3) 78 TVA intends to issue a revised calculation reflecting that the TID in the control room is less than 103 rads, which will be evaluated by the NRC staff. (Section 7.5.2.3) 79 TVA should perform a radiated susceptibility survey, after the installation of the hardware but prior to the RM-1000 being placed in service, to establish the need for exclusion distance for the HRCAR monitors while using handheld portable devices (e.g., walkie-talkie) in the control room, as documented in Attachment 23 to TVAs letter dated February 25, 2011, and item number 355 of TVAs letter dated April 15, 2011. (Section 7.5.2.3) 80 TVA should provide clarification to the staff on how TVA Standard Specification SS-E18-14.1 meets the guidance of RG 1.180, and should address any deviations from the guidance of the RG. (Section 7.5.2.3) 81 The extent to which TVAs supplier, General Atomics (GA), complies with EPRI TR-106439 and the methods that GA used for its commercial dedication process should be provided by TVA to the NRC staff for review. (Section 7.5.2.3) 82 The staff concluded that the information provided by TVA pertaining to the in-containment LPMS equipment qualification for vibration was incomplete. TVA should provide (item number 362 of ADAMS Accession No. ML111050009), documentation that demonstrates the LPMS in-containment equipment has been qualified to remain functional in its normal operating vibration environment, per RG 1.133, Revision 1. (Section 7.6.1) 83 TVA should confirm to the NRC staff the completion of the data storm test on the DCS. (Section 7.7.1.4) 84 TVA should provide additional information for the NRC staff to complete its review of post-LOCA long term cooling boric acid precipitation. (Section 15.3.1) 85 The 95/95 peak local oxidation was calculated to be 1.04 percent, while core-wide oxidation was calculated to be much less than 0.1 percent. TVA should provide to the

Page 21 of 23 SSER NRC SSER Item Item TVA Status No. Description Status NRC staff the value of the decay heat multiplier used for this limiting large break, in order for the staff to complete its evaluation. (Section 15.3.1) 86 TVA should demonstrate to the staff, in the WCOBRA/TRAC analysis of the limiting break, that the core remains covered with a two-phase mixture and can be cooled for an indefinite period of time. (Section 15.3.1) 87 In order for the staff to complete its evaluation, TVA should provide (1) a time step sensitivity study for the limiting break displaying downcomer boiling, (2) a list of ten key parameter plots for the worst case downcomer boiling transient, (3) values for the lateral k-factors used in the evaluation, and (4) the manner in which condensation was modeled in the downcomer. (Section 15.3.1) 88 It is also unclear to the staff that the entrainment correlation information has been incorporated into the EOP, to ensure that operators do not initiate hot and cold side injection during the period of time that entrainment could preclude injection into the hot legs. TVA should provide the EOP guidance/instructions for the operators to the staff for review. (Section 15.3.1) 89 TVA should demonstrate, quantitatively, the applicability of the generic analysis to WBN Unit 2, to demonstrate that the EOP instructions to the operators can effectively deal with the failure of a bottom mounted instrument tube in the lower head. (Section 15.3.1) 90 Verify that the ERCW pumps meet GDC 5 requirements for two unit operation. (Section 9.2.1) 91 TVA should update the FSAR with information describing how WBN Unit 2 meets GDC 5, assuming the worst case single failure and a LOOP, as provided in TVAs letter dated April 13, 2011. (Section 9.2.1) 92 The NRC staff should perform an inspection in accordance with NRC Temporary Instruction 2515/087, Inspection of Licensees Implementation of Multi-Plant Action A-17:

Instrumentation for Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident (Regulatory Guide 1.97). (Section 7.5.2.1.4) 93 TVA should confirm to the staff that testing of the Eagle 21

Page 22 of 23 SSER NRC SSER Item Item TVA Status No. Description Status system has sufficiently demonstrated that two-way communication to the ICS is precluded with the described configurations. (Section 7.9.3.2) 94 TVA should provide to the staff either information that demonstrates that the WBN Unit 2 Common Q PAMS meets the applicable requirements in IEEE Std. 603-1991, or justification for why the Common Q PAMS should not meet those requirements. (Section 7.5.2.2.3) 95 TVA should update FSAR Table 7.1-1, Watts Bar Nuclear Plant NRC Regulatory Guide Conformance, to reference IEEE Std. 603-1991 for the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3) 96 TVA should (1) update FSAR Table 7.1-1 to include RG 1.100, Revision 3, for the Common Q PAMS, or (2) demonstrate that the Common Q PAMS is in conformance with RG 1.100, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3) 97 TVA should demonstrate that the WBN Unit 2 Common Q PAMS is in conformance with RG 1.153, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3) 98 TVA should demonstrate that the WBN Unit 2 Common Q PAMS is in conformance with RG 1.152, Revision 2, or provide justification for not conforming. (Section 7.5.2.2.3) 99 TVA should update FSAR Table 7.1-1 to reference IEEE 7-4.3.2-2003 as being applicable to the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3) 100 TVA should update FSAR Table 7.1-1 to reference RG 1.168, Revision 1; IEEE 1012-1998; and IEEE 1020-1997 as being applicable to the WBN Unit 2 Common Q PAMS.

(Section 7.5.2.2.3) 101 TVA should demonstrate that the WBN Unit 2 Common Q PAMS application software is in conformance with RG 1.168, Revision 1, or provide justification for not conforming. (Section 7.5.2.2.3) 102 TVA should update FSAR Table 7.1-1 to reference RG 1.209 and IEEE Std. 323-2003 as being applicable to the WBN Unit 2 Common Q PAMS. (Section 7.5.2.2.3) 103 TVA should demonstrate that the WBN Unit 2 Common Q PAMS conforms to RG 1.209 and IEEE Std. 323-2003, or

Page 23 of 23 SSER NRC SSER Item Item TVA Status No. Description Status provide justification for not conforming. (Section 7.5.2.2.3) 104 The NRC staff will review the WEC self assessment to verify that it the WBN Unit 2 PAMS is compliant to the V&V requirements in the SPM or that deviations from the requirements are adequately justified. (Section 7.5.2.2.3.4.2) 105 TVA should produce an acceptable description of how the WBN Unit 2 Common Q PAMS SysRS and SRS implement the design basis requirements of IEEE Std. 603-1991 Clause 4. (Section 7.5.2.2.3.4.3.1) 106 TVA should produce a final WBN Unit 2 Common Q PAMS SRS that is independently reviewed. (Section 7.5.2.2.3.4.3.1) 107 TVA should provide to the NRC staff documentation to confirm that the final WBN Unit 2 Common Q PAMS SDDs that are independently reviewed. (Section 7.5.2.2.3.4.3.2) 108 TVA should demonstrate to the NRC staff that there are no synergistic effects between temperature and humidity for the Common Q PAMS equipment. (Section 7.5.2.2.3.5.2) 109 TVA should demonstrate to the NRC staff acceptable data storm testing of the Common Q PAMS. (Section 7.5.2.2.3.7.1.8) 110 TVA should provide information to the NRC staff describing how the WBN Unit 2 Common Q PAMS design supports periodic testing of the RVLIS function. (Section 7.5.2.2.3.9.2.6) 111 TVA should provide the technical specifications for the Common Q PAMS to the NRC staff for review. (Section 7.5.2.2.3.11)