Letter Sequence Other |
|---|
TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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
|
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
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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)
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Final Safety Analysis Report Figure 9.2-23 (Dwg No. 1-47W611-70-1, R9)
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Final Safety Analysis Report Figure 9.2-20 (Dwg No. 1-47W610-70-1, R23)
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Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29)
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Final Safety Analysis Report Figure 9.2-21A (Dwg No. 1-47W610-70-2A, R15)
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ML1023003642010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-22 (Dwg No. 1-47W610-70-3, R17)
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ML1023003652010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-24 (Dwg No. 1-47W611-70-2, R11)
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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)
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ML1023003692010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15)
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ML1023003702010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-2 (Dwg No. 1-47W610-32-2, R19)
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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)
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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 January 18, 2012 Mr. Michael D. Skaggs 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 - SUBMITTAL ISSUES WITH OPERATING LICENSE APPLICATION REVIEW REGARDING FIRE PROTECTION PROGRAM (TAC NO. ME2731)
Dear Mr. Skaggs:
I am writing to followup on recent discussions between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives from your staff regarding the resolution of issues arising from the NRC staff's review of your operating license (OL) application for Watts Bar Nuclear Plant (WBN), Unit 2, Specifically, the staff is currently reviewing Tennessee Valley Authority's (TVA's) submittals relating to Section 9.5,1, "Fire Protection Program," of the WBN Unit 2 Final Safety Analysis Report. As part of its review process, the staff identified several issues and held numerous meetings and telephone discussions to resolve the identified issues.
The staff continues to identify additional issues with your submittals.
During a meeting on December 21, 2011, we discussed a number of comments that the staff has raised about the latest revision of the as-designed fire protection report, which TVA submitted on November 30, 2011. In this revision to the report, TVA incorporated changes to implement its responses to a series of requests for additional information from the NRC staff, During the discussions, the staff presented concerns it had with inconsistencies in the information presented in several areas of the report. Further, the staff noted that TVA must specifically describe any deviations from the requirements for fire protection of safe shutdown capability in the report rather than rely only on a proposed method for evaluating the capability of installed fire protection features.
As a result of the staffs issues and concerns, TVA stated that it would determine the specific elements in the program requiring revision and the schedule for providing a revised fire protection report. TVA stated that these actions would be completed by the first week of January 2012. TVA has since stated during a teleconference that the revised fire protection report will be submitted by February 24, 2012.
The accuracy of this assessment and completion of any ensuing revisions to the fire protection documentation supporting the OL review is critical for the NRC staff to complete its review. In particular, it has already impacted the ability for the staff to present the results of its findings to
M. Skaggs
- 2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated.
Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones.
We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule.
Sincerely, L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv
M. Skaggs
- 2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated.
Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones.
We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule.
Sincerely, IRA by P. Milano fori L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPWB Reading File RidsNrrDorlLpwb Resource RidsNrrLABClayton Resource RidsNrrPMWatlsBar2 Resource RidsNrrDraAfpb Resource RidsRgn2MailCenter Resource RidsOgcRp Resource RidsOpaMailCenter RHaag. R-II TNazario. SRI, R-II RidsAcrsAcnw_MailCTR Resource ADAMS Accession No ML12005A228
- 1 LPWB/PM LPWB/LA AFPB/BC OGC NLO LPWB/BC LPWB/PM NAME PMilano BClayton AKlein (wI comments)
DRoth SCampbell LRaghavan
- DATE 01110/12 01/06/12 01/09/12 01/17/12 01/18/12 12130111 OFFICIAL AGENCY RECORD
