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TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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)
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)
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Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23)
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ML1023003502010-08-0505 August 2010
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)
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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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
September 28, 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 SECTION 7.3 (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letter dated November 24, 2009 (Agencywide Documents Access and Management System Accession No. ML093370275), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendment No. 95 for Watts Bar Nuclear Plant, Unit 2. The U.S.
Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendment No. 95.
In an effort to complete the NRC staff review, enclosed is a request for additional information regarding FSAR Section 7.3.
A response is required by October 8, 2010.
If you should have any questions, please contact me at 301-415-2048.
Sincerely,
/RA/
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 FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO SECTION 7.3 (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letter dated November 24, 2009 (Agencywide Documents Access and Management System Accession No. ML093370275), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendment No. 95 for Watts Bar Nuclear Plant, Unit 2. The U.S.
Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendment No. 95.
In an effort to complete the NRC staff review, enclosed is a request for additional information regarding FSAR Section 7.3.
A response is required by October 8, 2010.
If you should have any questions, please contact me at 301-415-2048.
Sincerely,
/RA/
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 RidsNrrDeEicb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr SDarbali, NRR ADAMS Accession No. ML102640324
- via memo OFFICE LPWB/PM LPWB/LA EICB/BC OGC LPWB/BC NAME JPoole BClayton TMossman for WKemper*
DRoth SCampbell DATE 09 / 21 /10 09 / 21 /10 9/10/10 09 / 27 /10 09 / 28 /10 OFFICIAL AGENCY RECORD
Enclosure REQUEST FOR ADDITIONAL INFROMATION WATTS BAR NUCLEAR PLANT, UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391
- 1. In Amendment 95, Final Safety Analysis Report (FSAR) Section 7.3.2.3 Further Considerations, the list of signals that would start the auxiliary feedwater motor driven and turbine driven pumps was moved to Table 7.3-1 Item 3, Auxiliary Feedwater.
However, Item (6) AMSAC was not included in Table 7.3-1.
Please explain this omission or state your commitment to correct this in a future amendment to the FSAR.
- 2. In Amendment 95, FSAR Section 7.3.1.1.1 Function Initiation, item (13) was arranged into paragraph form from what used to be a listing of Items (a), (b) and (c).
The second bullet under Item (c) was omitted in the new paragraph.
Initiates Phase B containment isolation of the following:
Closure of the main steam isolation valves (MSIV) to limit reactor coolant system cooldown for breaks downstream of the MSIVs.
Please explain this omission or state your commitment to correct this in a future amendment to the FSAR.
- 3. In Amendment 95, FSAR Section 7.3.1.1.2 Process Protection Circuitry, Item (3) references to Sections 7.6 and 7.7 were removed.
Please explain the reason for removal.
- 4. In Amendment 95, FSAR Section 7.3.1.2.1 Generating Station Conditions, the new paragraph was arranged from what used to be a listing of Items (1.b), (1.c), and (2.b),
leaving out Items (1.a) and (2.a). Even if the paragraph contains the word include, the breaks in Items (1.a) and (2.a) should be listed.
Please explain this omission or state your commitment to correct this in a future amendment to the FSAR.
- 5. In Amendment 95, FSAR Section 7.3.1.2.2 Generating Station Variables, the following sentence was deleted:
Post accident monitoring requirements and variables are given in Tables 7 5-1 and 7.5-2.
Please explain the reason for removal.
- 6. U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement Bulletin 80-06 calls for review of engineered safety features with the objective of ensuring that no device will change position solely because of the reset action.
In Supplement 3 of NUREG-0847, Section 7.3.5, the staff approved the design modifications proposed by the applicant that would allow certain devices to remain unchanged upon an engineered safety feature (ESF) reset. The staff also found acceptable the applicants justification for some safety-related equipment that does not remain in its emergency mode after an ESF reset.
Please confirm whether or not the equipment that was determined in NUREG-0847 and its supplements to remain unchanged upon an ESF reset will still remain unchanged in Unit 2.
