Letter Sequence RAI |
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MONTHYEARML1001914212010-01-11011 January 2010
Final Safety Analysis Report, Amendment 97
Project stage: Request
ML1000800082010-01-11011 January 2010
Notice of Forthcoming Conference Call with Tennessee Valley Authority Sequoyah Nuclear Plant, Units 1 & 2; Watts Bar Unit 1
Project stage: Request
GNRO-2010/00007, Request for Exemption from Physical Security Requirements (Redacted)2010-01-18018 January 2010
Request for Exemption from Physical Security Requirements (Redacted)
Project stage: Request
ML1004917722010-02-18018 February 2010
Acceptance Review Email Request for Exemption from the Requirements of 10 CFR Part 73
Project stage: Acceptance Review
ML1001902362010-02-25025 February 2010
Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption for Physical Security Requirements
Project stage: Other
ML1001902292010-02-25025 February 2010
Environmental Assessment and Finding of No Significant Impact
Project stage: Other
NRC-2010-0082, Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption for Physical Security Requirements2010-02-25025 February 2010
Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption for Physical Security Requirements
Project stage: Other
ML1005508062010-03-23023 March 2010
FRN: General Notice. Grand Gulf Nuclear Station, Unit 1 - Exemption from the 10 CFR Part 73 Physical Security Requirements Implementation Compliance Date
Project stage: Approval
ML1005508012010-03-23023 March 2010
Cover Letter, Exemption from the 10 CFR Part 73 Physical Security Requirements Implementation Compliance Date
Project stage: Approval
ML1013701862010-05-14014 May 2010
OL - FW: Call Summary - TVA Clarification Call
Project stage: Request
ML1015401332010-06-10010 June 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Accident Dose
Project stage: RAI
ML1018201562010-06-18018 June 2010
OL - Updated Open Items List
Project stage: Request
ML1019402362010-06-18018 June 2010
Instrumentation and Controls Staff Information Requests
Project stage: Request
ML1015402502010-06-24024 June 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091)
Project stage: RAI
ML1016002782010-07-12012 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Accident Dose
Project stage: RAI
ML1019506102010-07-30030 July 2010
Request for Additional Information, Licensees Final Safety Analysis Report Amendment Related to Chapters 3.9.1, 3.9.2, and 3.9.3
Project stage: RAI
ML1019404742010-07-30030 July 2010
Request for Additional Information, Licensees Final Safety Analysis Report Amendment Related to Chapter 10.4.7
Project stage: RAI
ML1026305982010-09-28028 September 2010
Request for Additional Information, Regarding Final Safety Analysis Report Related to Sections 3.2 and 5.2
Project stage: RAI
ML1029901502010-10-26026 October 2010
Cancelled - Notice of Meeting with (Tva), to Discuss Responses to the NRC Requests for Additional Information (Rals) for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis
Project stage: RAI
ML1035401772010-12-20020 December 2010
Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control
Project stage: Request
ML1036101142010-12-21021 December 2010
Submittal of Pre-op Test Instruction
Project stage: Request
ML1101401972011-01-14014 January 2011
Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control
Project stage: Request
ML1102801282011-02-0909 February 2011
Request for Additional Information, Regarding Final Safety Analysis Report Amendment Related to Section 9.5.1 Fire Protection System
Project stage: RAI
ML1106107452011-03-10010 March 2011
Request for Additional Information, Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Report - Round 2
Project stage: RAI
ML1107705372011-03-16016 March 2011
Instrumentation and Controls Staff Information Requests
Project stage: Request
ML1109104642011-04-13013 April 2011
Summary of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 9.5.1 Fire Protection
Project stage: Meeting
ML1109607652011-04-25025 April 2011
Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 3
Project stage: RAI
ML11129A1582011-05-0606 May 2011
Request for Additional Information Regarding Fire Protection Report,
Project stage: Request
ML11165A1452011-05-18018 May 2011
OL - Commitments and Sser Open Items
Project stage: Request
ML1112404832011-05-23023 May 2011
Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 4
Project stage: RAI
ML1114506732011-05-26026 May 2011
July 14, 2011 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss Bellefonte Nuclear Plant, Unit 1, Digital Instrumentation and Control and Human Factors
Project stage: Request
ML1115201192011-05-26026 May 2011
Response to Request for Additional Information Regarding Fire Protection Report
Project stage: Response to RAI
ML11161A1282011-06-0707 June 2011
Safety Evaluation Report Supplement 22 (Sser 22) - Second Response to NRC Required Action Items
Project stage: Request
ML1115109792011-06-0808 June 2011
Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 5
Project stage: RAI
ML11186A8642011-07-0101 July 2011
Submittal of Report in Accordance with 10 CFR 26.719(c)(1) for Drug and Alcohol Testing Errors
Project stage: Request
ML11200A1092011-07-14014 July 2011
Meeting Slides - TVA Phase 0 Meeting Bln/Nrc Bellefonte Digital I & C Upgrades
Project stage: Request
ML11200A1152011-07-14014 July 2011
Meeting Slides - TVA Phase 0 Meeting with NRC Bellefonte Units 1 & 2 Main Control Room Modernization
Project stage: Request
ML1118235802011-07-21021 July 2011
Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Group 6
Project stage: RAI
ML1120000992011-07-22022 July 2011
July 14, 2011 Summary of Pre-Application Meeting with Tennessee Valley Authority Regarding Digital Instrumentation and Control and Human Factors for the Potential, Proposed Updated Operating License Application at Bellefonte Nuclear Plant,
Project stage: Meeting
ML1120303872011-07-27027 July 2011
Request for Additional Information Regarding Incore Instrumentation System
Project stage: RAI
ML11215A1322011-07-29029 July 2011
Response to Request for Additional Information Regarding June 28, 2011 NRC Audit- Steam Line Break (Slb) and Other Miscellaneous RAIs
Project stage: Response to RAI
ML11227A2572011-08-0505 August 2011
Request for Additional Information (RAI) Group 6 Regarding Fire Protection Report
Project stage: Request
ML11230A3852011-08-15015 August 2011
Transmittal of Revised Unit 1 / Unit 2 As-Designed Fire Protection Report
Project stage: Request
ML1124904742011-09-14014 September 2011
Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Group 7
Project stage: RAI
ML11286A0382011-09-30030 September 2011
OL - Draft RAIs on Fire Protection - Group 8
Project stage: Request
ML13060A2252011-09-30030 September 2011
Response to Request for Additional Information Group 7 Regarding Fire Protection Report, (TAC No. ME3091) (Public Version)
Project stage: Response to RAI
ML11286A0352011-09-30030 September 2011
OL - Additional Draft RAI on Fire Protection - Group 8
Project stage: Request
ML11306A0902011-10-28028 October 2011
Response to Request for Additional Information Group 8 Regarding Fire Protection Report
Project stage: Response to RAI
ML11322A1032011-11-30030 November 2011
WCAP-17529-NP, Rev. 0, System Requirements Specification for the Common Q Post Accident Monitoring System
Project stage: Request
ML1135002392011-12-20020 December 2011
Audit Report of Fire Protection Relating to Final Safety Analysis Report Accident Analyses
Project stage: Other
2011-02-09
[Table View] |
Text
July 30, 2010 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO MECHANICAL ENGINEERING SYSTEMS (TAC NO. ME3091)
Dear Mr. Bhatnagar:
By letter dated January 11, 2010 (Agencywide Documents Access and Management System Accession No. ML100191426), the Tennessee Valley Authority submitted Final Safety Analysis Report (FSAR) Amendment No. 97 for Watts Bar Nuclear Plant (WBN), Unit 2. This update contained changes to a number of sections of the WBN Unit 2 FSAR, including Sections 3.9.1, 3.9.2 and 3.9.3.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
Sincerely,
/RA PMilano for/
Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSEES FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO MECHANICAL ENGINEERING SYSTEMS (TAC NO. ME3091)
Dear Mr. Bhatnagar:
By letter dated January 11, 2010 (Agencywide Documents Access and Management System Accession No. ML100191426), the Tennessee Valley Authority submitted Final Safety Analysis Report (FSAR) Amendment No. 97 for Watts Bar Nuclear Plant (WBN), Unit 2. This update contained changes to a number of sections of the WBN Unit 2 FSAR, including Sections 3.9.1, 3.9.2 and 3.9.3.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
Sincerely,
/RA PMilano for /
Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsNrrDeEmcb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr RidsNrrDciCptb Resource ADAMS Accession No. ML101950610
- via memo dated July 13, 2010 OFFICE LPWB/PM LPWB/LA EMCB/BC OGC LPWB/BC NAME JPoole BClayton MKhanna*
DRoth SCampbell DATE 07 / 21 /10 07/ 20 /10 7/13/10 07 / 29 /10 07 / 30 /10 OFFICIAL AGENCY RECORD
REQUEST FOR ADDITIONAL INFROMATION WATTS BAR NUCLEAR PLANT, UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT NO. 97 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 EMCB RAI 3.9.3-1 Provide bases or justification for deleting the following valves from Table 3.9-17, ACTIVE VALVES FOR PRIMARY FLUID SYSTEMS, and Table 3.9-25, VALVES REQUIRED TO BE ACTIVE FOR DESIGN BASIS EVENTS.
From Table 3.9-17:
Valves RFV-62-518, RFV-62-519, 1-RFV-62-1220, CKV-77-849, and CKV-77-868.
From Table 3.9-25:
Valves CKV-18-686A/B, CKV-18-687A/B, RFV-18-688A/B, CKV-18-689A/B, CKV-18-787A/B, 1-33-794, 2-33-797, FCV-62-1228, FCV-62-1229, CKV-67-513A/B, FCV-70-168, CKV-70-753, FCV-82-310, FSV-82-310-S, FCV-82-311, FSV-82-311-S, PCV-82-312A/B, PCV-82-313A/B, CKV-82-561, CKV-82-562, CKV-82-567, CKV-82-568, CKV-82-572, CKV-82-573, CKV-82-589, CKV-82-590, CKV-82-591, CKV-82-592, CKV-82-593, SPV-82-593, SPV-82-594, FCV-90-108, and FCV-90-109.
Enclosure
