Letter Sequence RAI |
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TAC:ME4074, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results|Request]]
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: CNL-14-077, Responses to Degraded Voltage Issue Requests for Additional Information, ML101050203, ML102240630, ML102290358, ML102290360, ML102290361, ML102290362, ML102290363, ML102290364, ML102290365, ML102290366, ML102290367, ML102290368, ML102290383, ML102290384, ML102290385, ML102290386, ML102290387, ML102290388, ML102290389, ML102290390, ML102290391, ML102290392, ML102290403, ML102290404, ML102290405, ML102290406, ML102290407, ML102290408, ML102290409, ML102290410, ML102290411, ML102290414, ML102290439, ML102290440, ML102290441, ML102290442, ML102290443, ML102290444, ML102290445, ML102290446, ML102290447, ML102290448, ML102290458, ML102290459, ML102290460, ML102290461, ML102290462, ML102290463, ML102290464... further results
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MONTHYEARML0933702752009-11-24024 November 2009
Final Safety Analysis Report, Amendment 95, Cover Letter
Project stage: Request
ML12192A3682009-12-0909 December 2009
Tennessee Department of Health Public Health Assessment 2009
Project stage: Request
ML1001916862010-01-11011 January 2010
Final Safety Analysis Report, Amendment 97, Section 8 - Electric Power Through 8E-12
Project stage: Request
ML1001914212010-01-11011 January 2010
Final Safety Analysis Report, Amendment 97
Project stage: Request
ML1002204742010-02-0505 February 2010
IP 37002, Construction Refurbishment Process - Watts Bar Unit 2
Project stage: Request
ML1005500072010-03-11011 March 2010
Request for Additional Information Related to Licensees Final Safety Analysis Report Amendment 95 Related to Section 4.2.2, Reactor Vessel Internal Components
Project stage: RAI
ML1007100112010-03-12012 March 2010
OL - List of Documents for Docketing Referenced on Page 5 of the Site Audit Trip Report
Project stage: Request
ML1010502032010-04-0808 April 2010
Additional Information Regarding Final Safety Analysis Report, Chapter 7, Instrumentation and Controls Review - Requested Common Q Proprietary Documents
Project stage: Other
ML1010405732010-04-0909 April 2010
Response to NRC Request for Additional Information Regarding Licensees Final Safety Analysis Report (FSAR) Amendment Related to Section 4.2.2, Reactor Vessel Internal Components
Project stage: Response to RAI
ML1011701022010-04-27027 April 2010
Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Submittals
Project stage: Request
ML1011303512010-05-0505 May 2010
Request for Withholding Information from Public Disclosure (Tac No. ME2731)
Project stage: Withholding Request Acceptance
ML1016102902010-05-27027 May 2010
Transmittal of Amendment 99 to Final Safety Analysis Report (FSAR)
Project stage: Request
ML1016203602010-06-17017 June 2010
Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss the Complete Status of TVA Hydrology Issues Including the Flooding Effects on the TVA Operating Nuclear Plants
Project stage: Request
ML1014500842010-06-23023 June 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Reactor Systems, Nuclear Performance and Code Review, Ansd Plant Systems
Project stage: RAI
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
ML1017903992010-06-28028 June 2010
Request for Additional Information (RAI) Regarding Licensees Final Safety Analysis Report Amendment Related to Section 4.2.2, Reactor Vessel Internal Components
Project stage: Request
ML1016200062010-06-29029 June 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review (Tac No. ME2731)
Project stage: RAI
ML1015304742010-07-0202 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Mechanical and Civil Engineering Systems
Project stage: RAI
ML1016000262010-07-0808 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report, Amendment Related to Quality and Vendor Branch Review
Project stage: RAI
ML1015303542010-07-12012 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Electrical Engineering Systems
Project stage: RAI
ML1018001562010-07-15015 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Chapter 8, Electric Power
Project stage: RAI
ML1020202812010-07-30030 July 2010
Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Chapter 3.11
Project stage: RAI
ML1023003322010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-9 (Dwg No. 1-47W611-67-5, R10)
Project stage: Other
ML1022904662010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-3 (Dwg No. 1-47W845-3, R23)
Project stage: Other
ML1023003332010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 (Dwg No. 1-47W610-67-1, R27)
Project stage: Other
ML1023003342010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 Sh a (Dwg No. 1-47W610-67-1A, R16)
Project stage: Other
ML1023003352010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-11 (Dwg No. 1-47W610-67-2, R15)
Project stage: Other
ML1023003432010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 Sh a (Dwg No. 1-47W610-67-3A, R7)
Project stage: Other
ML1023003442010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-13 (Dwg No. 1-47W610-67-4, R17)
Project stage: Other
ML1023003452010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-11 Sh a (Dwg No. 1-47W610-67-2A, R8)
Project stage: Other
ML1023003462010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 (Dwg No. 1-47W610-67-3, R12)
Project stage: Other
ML1023003472010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5, R14)
Project stage: Other
ML1023003482010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5A, R2)
Project stage: Other
ML1023003492010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23)
Project stage: Other
ML1023003502010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-17 (Dwg No. 1-47W859-3, R18)
Project stage: Other
ML1023003512010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-18 (Dwg No. 1-47W859-2, R36)
Project stage: Other
ML1023003522010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-19 (Dwg No. 1-47W859-1, R47)
Project stage: Other
ML1023003602010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-23 (Dwg No. 1-47W611-70-1, R9)
Project stage: Other
ML1023003612010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-20 (Dwg No. 1-47W610-70-1, R23)
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ML1023003622010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29)
Project stage: Other
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Final Safety Analysis Report Figure 9.2-21A (Dwg No. 1-47W610-70-2A, R15)
Project stage: Other
ML1023003642010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-22 (Dwg No. 1-47W610-70-3, R17)
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Final Safety Analysis Report Figure 9.2-24 (Dwg No. 1-47W611-70-2, R11)
Project stage: Other
ML1023003672010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-25 (Dwg No. 1-47W611-70-3, R4)
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ML1023003682010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-25A (Dwg No. 1-47W611-70-4, R4)
Project stage: Other
ML1023003692010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15)
Project stage: Other
ML1023003702010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-2 (Dwg No. 1-47W610-32-2, R19)
Project stage: Other
ML1023003732010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-6 (Dwg No. 1-47W848-1, R24)
Project stage: Other
ML1022903682010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-14B (Dwg No. 1-45W760-82-1, R17)
Project stage: Other
ML1022903652010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-7 (Dwg No. 1-45W760-211-9, R16)
Project stage: Other
2010-05-05
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 4, 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 SUB..IECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FINAL SAFETY ANALYSIS REPORT RELATED TO SECTION 15 (TAC NO. ME4074)
Dear Mr. Bhatnagar:
By letters dated November 24 and December 14, 2009, and January 11, May 7, and May 27, 2010, Tennessee Valley Authority submitted Amendments 95, 96, 97, 98, and 99, respectively, to the Final Safety Analysis Report for Watts Bar Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided and determined that further information is required to complete its assessment of your submittals.
The specific questions are discussed in the enclosed Request for Additional Information.
A response is required within 20 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
f11~. iJ~),¥~
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
Request for Additional Information Watts Bar Nuclear Plant. Unit 2 Final Safety Analysis Report Section 15 Tennessee Valley Authority Docket No. 50-391 By letters dated November 24 and December 14, 2009, and January 11, May 7, and May 27, 2010, Tennessee Valley Authority submitted Amendments 95,96,97,98, and 99, respectively, to the Final Safety Analysis Report (FSAR) for Watts Bar Nuclear Plant (WBN), Unit 2. The Nuclear Regulatory Commission staff has reviewed the information provided and has determined that the following information is required to complete its review.
SER 15.3.6, "Anticipated Transients Without Scram" FSAR Chapter 15.2, CONDITION" - FAULTS OF MODERATE FREQUENCY, contains a paragraph concerning anticipated transients without scram (ATWS), in which reference is made to a series of generic studies that indicate ATWS analyses would yield acceptable consequences in cases where the turbine trip and auxiliary feedwater actuation functions are successful. This paragraph concludes with a reference to the Watts Bar ATWS mitigation system actuation circuitry (AMSAC) design description in FSAR Chapter 7.7.1.12. Please provide the following additional information, concerning ATWS in Watts Bar Unit 2:
- 1.
Provide a discussion verifying that WBN Unit 2, with the AMSAC installed, meets the requirements of General Design Criteria 13, 14, 16, 35, 38, and 50 (NUREG-0800, Section 15.8).
- 2.
Provide a discussion of the analysis or evaluation that shows that the reactor coolant system pressure will not exceed the American Society of Mechanical Engineers Service Level C limits (approximately 3200 psig), with AMSAC installed, for the most limiting ATWS event. If the results of generic analyses are cited, show that they apply to the specifics of the WBN Unit 2 design.
- 3.
Provide a discussion of the analysis or evaluation showing that the containment safety parameters (e.g., temperature or pressure) will not exceed design limits, with AMSAC installed, for the most limiting ATWS event.
- 4.
Provide a discussion of the analysis or evaluation showing, with AMSAC installed, that the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," are met for the most limiting ATWS event.
- 5.
Verify that the moderator temperature coefficient, used in ATWS analyses or evaluations, is consistent with moderator temperature coefficient assumptions used in the bases for 10 CFR 50.62 (see Appendix C to NUREG-0460).
- 6.
Provide a discussion indicating that WBN Unit 2 has the capability for long-term shutdown and cooling following the most limiting ATWS event, and identify the operator actions and procedures that are used.
Enclosure
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FINAL SAFETY ANALYSIS REPORT RELATED TO SECTION 15 (TAC NO. ME4074)
Dear Mr. Bhatnagar:
Dear Mr. Bhatnagar:
By letters dated November 24 and December 14,2009, and January 11, May 7, and May 27, 2010, Tennessee Valley Authority submitted Amendments 95,96,97,98, and 99, respectively, to the Final Safety Analysis Report for Watts Bar Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided and determined that further information is required to complete its assessment of your submittals.
The specific questions are discussed in the enclosed Request for Additional Information.
A response is required within 20 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
Sincerely, IRA JWiebe forI 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:
PUBLIC RidsNrrPMWattsBar2 Resource RidsRgn2MailCenter Resource LPWB Reading File RidsNrrDssSrxb Resource RidsOgcRp Resource RidsNrrDorlLpwb Resource RidsNrrLABClayton Resource RidsNrrDorlDpr RidsAcrsAcnw_MailCTR Resource ADAMS Accession No. ML102700437
- per memo OFFICE LPWB/PM LPWB/LA SRXB/BC OGC/nio LPWB/BC NAME JPoole BClayton AUlses*
DRoth SCampbell/JWeibe for DATE 09/28/10 09/28/10 08/27/10 09/30/10 10104/10 OFFICIAL AGENCY RECORD
