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TAC:ME2731, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |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
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 January 13, 2011 10 CFR 50.55a(a)(3)(i)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2. AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, PRESERVICE INSPECTION (PSI) PROGRAM* REQUEST TO USE SUBSEQUENT EDITION AND ADDENDA OF ASME SECTION XI CODE FOR PSI ACTIVITIES
Reference:
TVA letter to NRC dated October 30,2008, "Watts Bar Nuclear Plant (WBN)
Unit 2 - Preservice Inspection Program Plan and Request for Relief No.
WBN-2/PDI-4 [ML083090046]"
Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is submitting the enclosed relief request to allow the use of ASME Section 2001 Edition through 2003 Addenda, subject to the limitations and modifications of 10 CFR 50.55a, for the WBN Unit 2 construction completion project PSI Program Code of Record.
This relief request was discussed between representatives of TVA and the NRC on January 6, 2011. The revised PSI Program document for WBN Unit 2 was submitted to NRC in the referenced letter.
There are no new commitments associated with this submittal. If you have any questions, please contact Bill Crouch at (423) 365-2004.
~p.~~-
Masoud Baj~taVi Watts Bar U~Vice President
U.S. Nuclear Regulatory Commission Page 2 January 13, 2011
Enclosure:
Tennessee Valley Authority, Watts Bar Nuclear Plant (WBN) Unit 2, American Society of Mechanical Engineers (ASME)Section XI Request for Relief WBN-2/PSI-2 cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF WBN-2/PSI-2 E-1 TVA requests approval to use the alternative ASME Section XI Code year and addenda for the completion of WBN Unit 2. The alternate ASME Code for Preservice Inspection (PSI) activities is based on the ASME Section XI Edition and Addenda approved at the time construction was resumed on WBN Unit 2.
EXECUTIVE
SUMMARY
In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief to utilize a later Code of Record for PSI activities during the completion of WBN Unit 2. Section 50.55a(g)(2) requires the PSI Code of Record to be based on the ASME Section XI Code in effect six months prior to the date of issue of the Construction Permit. Because the construction permit for WBN Unit 2, CPPR-92, is dated January 23, 1973, the applicable Code would be the 1971 Edition through Winter 1971 Addenda of ASME Section XI. Since 10 CFR 50.55a(g)(2) also allows the use of subsequent Code Editions/Addenda, which are incorporated by reference in 10 CFR 50.55a(b)(2), TVA identified the 2001 Edition through 2003 Addenda as the applicable Code of Record based on the date associated with resumption of construction activities.
SYSTEM/COMPONENTS FOR WHICH RELIEF IS REQUESTED:
ASME Code Class 1, 2, 3, IWF, and MC components including the applicable Examination Categories and Item Numbers.
APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM:
The ASME Section XI Code Edition and Addenda Code of Record requested for the WBN Unit 2 construction completion project PSI is the 2001 Edition through 2003 Addenda, as amended by 10 CFR 50.55a and those Code Cases either approved for use by Regulatory Guide 1.147 and adopted by WBN Unit 2 or where specific relief has been granted by NRC.
REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:
Permission is requested to adopt a later NRC-approved Code Edition and Addenda as provided in 10 CFR 50.55a(g)(2), in place of the Code of Record as determined by the date of the construction permit.
RELIEF REQUESTED:
Section 50.55a(g)(2) requires the PSI Code of Record to be based on the ASME Section XI Code in effect six months prior to the date of issue of the Construction Permit. Because the construction permit for WBN Unit 2, CPPR-92, is dated January 23, 1973, the applicable Code would be the 1971 Edition through Winter 1971 Addenda of ASME Section XI. Since 10 CFR 50.55a(g)(2) also allows the use of subsequent Code Editions/Addenda, which are incorporated by reference in 10 CFR 50.55a(b)(2), TVA identified the 2001 Edition through 2003 Addenda as
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF WBN-2/PSI-2 E-2 the applicable Code of record based on the date associated with resumption of construction activities.
BASIS FOR RELIEF:
Construction activities at WBN Unit 2 resumed approximately 35 years after the initial construction permit was issued. The 10 CFR 50.55a(g)(2) method for determining the PSI code of record requires the use of the 1971 Edition though Winter 1971 (71/W71) Addenda of ASME Section XI; however, the provision in 10 CFR 50.55a(g)(2) to allow the use of subsequent Code Editions/Addenda, which are incorporated by reference in 10 CFR 50.55a(b)(2), allows the use of a technically superior PSI Code of Record based on 30 years of ASME Code committee knowledge and revisions. For example, Class MC, metal containment, examination was not required in the 71/W71 Section XI code, but it is a requirement of Subsection IWE of the 2001 Edition through 2003 Addenda of ASME Section XI.
PROPOSED ALTERNATIVES:
Utilize the 2001 Edition through 2003 Addenda of ASME Section XI for WBN Unit 2 construction completion activities subject to the modifications and limitations imposed by 10 CFR 50.55a.
JUSTIFICATION FOR GRANTING RELIEF:
The 2001 Edition through 2003 Addenda of ASME Section XI was approved for use in 10 CFR 50.55a(b)(2), and 10 CFR 50.55a(g)(2) allows the use of subsequent Code Editions/Addenda that are incorporated by reference in 10 CFR 50.55a(b)(2). The version of 10 CFR 50.55a(b)(2) in place in 2008 states:
(2) As used in this section, references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, and include the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1)....
The 2001 Edition through 2003 Addenda of ASME Section XI incorporates 30 years of technical lessons learned when compared to the 1971 Edition through Winter 1971 Addenda of the ASME Section XI Code. Thus, the requested relief would permit use of the code that was current at the time construction activities resumed at WBN Unit 2.
IMPLEMENTATION SCHEDULE AND DURATION:
This relief will be utilized for the duration of PSI activities associated with the completion of WBN Unit 2.