Letter Sequence Request |
|---|
TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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 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) Project stage: Other ML1023003622010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29) Project stage: Other ML1023003632010-08-0505 August 2010 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) Project stage: Other ML1023003652010-08-0505 August 2010 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) Project stage: Other 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
1 WBN2Public Resource From:
Poole, Justin Sent:
Tuesday, September 20, 2011 1:50 PM To:
Arent, Gordon; Bryan, Robert H Jr Cc:
Milano, Patrick; WBN2HearingFile Resource
Subject:
Draft RAIs on the Fire Protection Review for WBN 2 Attachments:
WBN FP questions (9-20) revised.docx Gordon/Bob, In reviewing the latest fire protection report, the staff has come up with the attached questions. Please review to ensure that the RAI questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. Please also let me know how much time Tennessee Valley Authority (TVA) needs to respond to the RAI questions.
Justin C. Poole Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov
Hearing Identifier:
Watts_Bar_2_Operating_LA_Public Email Number:
520 Mail Envelope Properties (19D990B45D535548840D1118C451C74DA920282FFE)
Subject:
Draft RAIs on the Fire Protection Review for WBN 2 Sent Date:
9/20/2011 1:49:32 PM Received Date:
9/20/2011 1:49:34 PM From:
Poole, Justin Created By:
Justin.Poole@nrc.gov Recipients:
"Milano, Patrick" <Patrick.Milano@nrc.gov>
Tracking Status: None "WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>
Tracking Status: None "Arent, Gordon" <garent@tva.gov>
Tracking Status: None "Bryan, Robert H Jr" <rhbryan@tva.gov>
Tracking Status: None Post Office:
HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 605 9/20/2011 1:49:34 PM WBN FP questions (9-20) revised.docx 24903 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
Question 1 (II-26.1)
In the response to RAI FPR II-26 (ML11129A158), TVA noted that the frequency of the GL 82-21 annual fire protection audit has been changed to 24 months and refers to an August 28, 2002 letter (ML022460173) to the NRC documenting this change. TVA states in the August 28, 2002 letter that this change was implemented using a performance-based schedule as allowed by the NRC Regulatory Guide 1.189 (section 1.7.10.1 of revision 0).
Provide more detail regarding this change. In particular, A summary of the performance-based process used make the change A summary of how the change is being monitored This summary information would be appropriate to include in the FPR at the correct level of detail.
Question 2 (VII-26)
The text of Part VII, Section 2.4 Intervening Combustibles, indicates that this deviation is for the Auxiliary Building. However, the reviewers have identified two instances of reliance on this deviation for areas outside of the Auxiliary Building.
Table I-1 lists Deviation 2.4 for Fire Area 53, Diesel Generator Building (Page I-12) and Fire Area 60, IPS.
These are also reflected in Part VI, Section 3.59, (Diesel Generator Building) and Section 3.66, (IPS). Section 3.59 was revised to include crediting the deviation for the 8/15/11 version of the FPR.
The deviation should be revised to reflect all of the areas that it is relied upon in.
Question 3 (II-48)
The information used to create the SSER 18 section 3.1.4.2 Internal Conduit Fire Barrier Penetration Seals currently exists only in an RAI response from July 1, 1994 (ML072320559) and not in the FPR.
Additionally, there is a conflict regarding the combustibility of the seal material between the RAI response and the internal conduit seal definition in Part II of the FPR.
In order to achieve a cleaner licensing basis, it would be appropriate to include this information in the FPR.