Letter Sequence RAI |
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TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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
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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)
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ML1022904662010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-3 (Dwg No. 1-47W845-3, R23)
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ML1023003332010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 (Dwg No. 1-47W610-67-1, R27)
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ML1023003342010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 Sh a (Dwg No. 1-47W610-67-1A, R16)
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ML1023003352010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-11 (Dwg No. 1-47W610-67-2, R15)
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ML1023003432010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 Sh a (Dwg No. 1-47W610-67-3A, R7)
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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)
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ML1023003462010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 (Dwg No. 1-47W610-67-3, R12)
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ML1023003472010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5, R14)
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Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5A, R2)
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Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23)
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Final Safety Analysis Report Figure 9.2-17 (Dwg No. 1-47W859-3, R18)
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Final Safety Analysis Report Figure 9.2-18 (Dwg No. 1-47W859-2, R36)
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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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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)
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Final Safety Analysis Report Figure 9.2-25 (Dwg No. 1-47W611-70-3, R4)
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Final Safety Analysis Report Figure 9.2-25A (Dwg No. 1-47W611-70-4, R4)
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Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15)
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Final Safety Analysis Report Figure 9.3-2 (Dwg No. 1-47W610-32-2, R19)
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Final Safety Analysis Report Figure 9.3-6 (Dwg No. 1-47W848-1, R24)
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ML1022903682010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-14B (Dwg No. 1-45W760-82-1, R17)
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Final Safety Analysis Report Figure 8.3-7 (Dwg No. 1-45W760-211-9, R16)
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2010-05-05
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 March 11, 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:
WAITS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSEE'S FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO SECTION 4.2.2," REACTOR VESSEL INTERNAL COMPONENTS" (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letters dated November 24, 2009, December 14, 2009, and January 11, 2010, Tennessee Valley Authority submitted Final Safety Analysis Report (FSAR) Amendments 95,96, and 97, respectively.
The submittals, in Section 4.2.2, "Reactor Vessel Internals (RVI)," includes design bases, design loading conditions, design loading categories and various materials used for the RVI components. The Nuclear Regulatory Commission staff reviewed the portion related to materials used for the RVI components and determined that further information is required to complete its assessment of the licensee's submittals. In the enclosed request for additional information (RAI), the staff has listed the requested information.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerely, J-J,VP oel S. Wiebe, Senior Project Manager atts Bar Special Projects Branch ivision of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFROMATION WATTS BAR NUCLEAR PLANT, UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENTS 95, 96, and 97 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 By letters dated November 24, 2009 (Agencywide Document and Management System (ADAMS) Accession No. ML093370274), December 14, 2009 (ML093570464), and January 11, 2010 (ML100191426), Tennessee Valley Authority submitted Final Safety Analysis Report Amendments 95, 96, and 97, respectively. The following additional information related to Section 4.2.2, "Reactor Vessel Internals (RVI)," is required to proceed with our review.
Previous operating experience in Westinghouse Pressurized-Water Reactor (PWR) RVI components indicates that Nickel Base Alloy X-750 material is susceptible to stress corrosion cracking (SCC) when exposed to reactor coolant system water. Susceptibility to SCC in Nickel Base Alloy X-750 depends on the type of heat treatment that is performed on the alloy. The high temperature heat treatment (HTH) process that is used on Alloy X-750 offers better resistance to SCC than the heat treatment process that uses lower temperature. For example, in a Westinghouse-designed PWR facility, original Alloy X-750 Control Rod Guide Tube split pins were replaced by Alloy X-750 materials that were subjected to the HTH process.
In Table 5.2-12 of Section 5.0 of the Watts Bar, Unit 2 FSAR, TVA indicated that Alloy X-750 bolting is used in its RVI components. In this context, the staff requests that the licensee provide information regarding the type of heat treatment that was performed on Alloy X-750 material.
In a Staff Requirements Memorandum dated July 25, 2007 (ADAMS Accession No. ML093370274), the Commission directed the NRC staff and TVA to look for opportunities to resolve such issues where the unirradiated state of Watts Bar 2 makes the issue easier to resolve. In the context of the Commission's direction, if the HTH process was not used for Alloy X-750 materials, provide information regarding whether these materials should be replaced prior to operation to mitigate the potential for failure due to SCC.
Enclosure
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 LICENSEE'S FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO SECTION 4.2.2," REACTOR VESSEL INTERNAL COMPONENTS" (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letters dated November 24, 2009, December 14, 2009, and January 11, 2010, Tennessee Valley Authority submitted Final Safety Analysis Report (FSAR) Amendments 95, 96, and 97, respectively.
The submittals, in Section 4.2.2, "Reactor Vessel Internals (RVI)," includes design bases, design loading conditions, design loading categories and various materials used for the RVI components. The Nuclear Regulatory Commission staff reviewed the portion related to materials used for the RVI components and determined that further information is required to complete its assessment of the licensee's submittals. In the enclosed request for additional information (RAI), the staff has listed the requested information.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerely, IRA!
Joel S. Wiebe, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsNrrDciCvib Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr ADAMS Accession No ML100550007 OFFICE LPWB/PM LPWB/LA OGC/NLO LPWB/BC NAME JWiebe BClayton DRoth LRaghavan DATE 03/09/10 03/09/10 03/10/10 03/11/10 OFFICIAL AGENCY RECORD
