Letter Sequence RAI |
|---|
TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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)
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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 30, 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 SECTION 3.11 (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letters dated November 24, 2009, and January 11, 2010 (Agencywide Documents Access and Management System Accession Nos. ML093370275 and ML100191426), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendments 95 and 97 for Watts Bar Nuclear Plant (WBN), Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendments 95 and 97, respectively.
In an effort to complete the NRC staff review, enclosed is a request for additional information (RAI) regarding Section 3.11 "Environmental Qualification of Mechanical and Electrical Equipment." The NRC staff's RAI seeks information on WBN Unit 2 as it relates to dual operation of the facility.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
Sincerely, 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/enc/: Distribution via Listserv
REQUEST FOR ADDITIONAL INFROMATIOI\\I WATTS BAR NUCLEAR PLANT, UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENTS 95 AND 97 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 Section 3.11-Environmental Qualification of Mechanical and Electrical Equipment
- 1.
On Page 3.11-1 of the Final Safety Analysis Report (FSAR), the licensee stated the following:
Two programs are in place to environmentally qualify safety-related electrical equipment (including cable) and active safety-related mechanical equipment to function or not fail for event mitigation.
These programs involve:
(1) Safety-related electrical equipment within the scope of 10 CFR 50.49.
(2) Active, safety-related mechanical equipment located in a harsh environment.
Confirm that the Environmental Qualification program for Watts Bar Nuclear Plant, Unit 2 includes guidance for qualifying (1) nonsafety-related electric equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions identified in 10 CFR 50.49 and (2) required post-accident monitoring equipment.
- 2.
Confirm that equipment being replaced or refurbished will be qualified as Category 1 as required by 10 CFR 50.49.
- 3.
On Page 3.11-1 of the FSAR, the licensee stated the following:
A mild environment is defined as a room or building zone where, (3) the event radiation is less than or equal to 1E4 rad.
Clarify that a mild environment for electronic components such as semiconductors or electronic components containing organic material is a total integrated dose less than 1E3 rad, and a mild radiation environment for other equipment is less than 1E4 rad.
ENCLOSURE
- 2
- 4.
On page 3.11-2 of the FSAR, the licensee stated the following:
Abnormal operating conditions - The environmental service conditions which result from outside temperature excursions, temporary greater than design heat loads, or degraded environmental control operations.
This condition can exist for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per excursion for non-reactor bUilding spaces and will occur less than 1% of the plant life, unless alternate times and %0+ plant life conditions are specifically approved in reference [4] and its associated environmental data drawings.
- a. Explain the basis for increasing the time from 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. Clarify what is meant by "%0+ plant life conditions."
- 5.
I;xplain the basis for removing the Boron Injection Tank from the list in FSAR Section 3.11.7.1.
- 6.
On page 3.11-5 of the FSAR, the licensee stated the following:
Doses were integrated to determine a equipment exposure for a 100-day period after the accident.
Explain the basis for reducing the period of exposure after an accident from 1 year to 100 days.
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 SECTION 3.11 (TAC NO. ME2731)
Dear Mr. Bhatnagar:
By letters dated November 24, 2009, and January 11, 2010 (Agencywide Documents Access and Management System Accession Nos. ML093370275 and ML100191426), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendments 95 and 97 for Watts Bar Nuclear Plant (WBN), Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendments 95 and 97, respectively.
In an effort to complete the NRC staff review, enclosed is a request for additional information (RAI) regarding Section 3.11 "Environmental Qualification of Mechanical and Electrical Equipment." The NRC staff's RAI seeks information on WBN Unit 2 as it relates to dual operation of the facility.
A response is required within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-2048.
Sincerely, IRA PMilano 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:
RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsNrrDeEeeb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr
- o. ML102020281 via memo d t d M ay 27 2010 ADAMS Accesslon N a e OFFICE LPWB/PM LPWB/LA EEEB/BC OGC LPWB/BC NAME
.IPoole BClayton RMathew*
DRoth nlo SCampbell DATE 07/22/10 07/29/10 05/27/10 07/29/10 07/30/10 OFFICIAL AGENCY RECORD
