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Category:E-Mail
MONTHYEARML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24215A3152024-07-24024 July 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-276-A, Revision 2 TS 3.8.1, AC Sources ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24157A3152024-06-0303 June 2024 2024 Sequoyah Commercial Grade Dedication Inspection Information Request ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24156A0062024-05-22022 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Recapture Low-Power Testing Time ML24130A0132024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.11 for MCR Chiller Completion Time ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24082A0662024-04-17017 April 2024 Email to Stuart Rymer on Exemption Decision for Watts Bar ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24082A0682024-04-10010 April 2024 Email to Stuart Rymer Re_ Availability of EA-FONSI for Watts Bar ML24100A8392024-04-0909 April 2024 Response from State of Tn Regarding Review of Environmental Assessment for Watts Bar Exemption Request ML24100A8402024-04-0808 April 2024 Email to State of Tn Requesting Review of Environmental Assessment for Watts Bar Exemption Request ML24071A0982024-03-0707 March 2024 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate ML24058A0962024-02-26026 February 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant License Amendment Request to Revise UFSAR for Hydrologic Analysis ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24033A0562024-02-0101 February 2024 NRR E-mail Capture - Correction Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-427-A, Revision 2 Regarding Degraded Barriers ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans 2024-09-10
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Text
1 WBN2Public Resource From: Boyd, Desiree L [dlboyd@tva.gov]
Sent: Thursday, October 04, 2012 1:19 PM To: Epperson, Dan; Wilson, George; Poole, Justin Cc: Arent, Gordon; Hamill, Carol L; Boyd, Desiree L
Subject:
TVA letter to NRC_10-04-2012_Bulletin 88-08 Alternative Update Attachments:
10-04-2012_Bulletin 88-08 Alternative Update_Final.pdfPlease see attached TVA letter that was sent to the NRC today.
Thank You, ~*~*~*~*~*~*~*~*~*~*~
Désireé L. Boyd WBN Unit 2 Licensing dlboyd@tva.gov 423-365-8764
Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 747 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF33D04C1C)
Subject:
TVA letter to NRC_10-04-2012_Bulletin 88-08 Alternative Update Sent Date: 10/4/2012 1:18:53 PM Received Date: 10/4/2012 1:22:33 PM From: Boyd, Desiree L Created By: dlboyd@tva.gov Recipients: "Arent, Gordon" <garent@tva.gov>
Tracking Status: None "Hamill, Carol L" <clhamill@tva.gov>
Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov> Tracking Status: None "Epperson, Dan" <Dan.Epperson@nrc.gov> Tracking Status: None "Wilson, George" <George.Wilson@nrc.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov> Tracking Status: None
Post Office: TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 274 10/4/2012 1:22:33 PM 10-04-2012_Bulletin 88-08 Alternative Update_Final.pdf 97157 Options Priority: Standard Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received:
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000
October 4, 2012
10 CFR 50.4 U.S. Nuclear Regulatory Commission
ATTN: Document Control Desk Washington, D.C. 20555-0001
Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - NRC BULLETIN NO. 88-08, THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS (RCS) - CLARIFICATION
References:
- 1. TVA letter dated March 29, 1994, Watts Bar Nuclear Plant (WBN) Units 1 and 2 - NRC Bulletin 88 Thermal Stresses in Piping Connected to
Reactor Coolant Systems (RCS)
- 2. TVA letter dated August 15, 2012, Watts Bar Nuclear Plant (WBN) Unit 2 -
Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 8 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 8 (TAC No. MD8314)
The purpose of this letter is to provide the current WBN Unit 2 plan for addressing NRC Bulletin 88-08. Based on analysis and experience gained from WBN Unit 1, WBN Unit 2 has developed an acoustic monitoring program similar to the one currently used on WBN Unit 1. provides the background and the basis for this action. The Regulatory Framework status for NRC Bulletin 88-08 shown in Reference 2 will be revised to reflect this change in the next update.
provides the new commitment made in this letter.
U.S. Nuclear Regulatory Commission Page 3 October 4, 2012 bcc (Enclosures):
Jessie Quichocho
U.S. Nuclear Regulatory Commission MS 08G9A One White Flint North
11555 Rockville Pike
Rockville, Maryland 20852-2738
Fred Brown, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower
245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257
ENCLOSURE 1 NRC BULLETIN 88-08, THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS (RCS) - CLARIFICATION E1-1 Background The purpose of NRC Bulletin 88-08 was to review the reactor coolant systems (RCS) to identify any connected, non-isolable piping that might be subjected to temperature distributions which result in unacceptable thermal stresses and to take action, where such piping is identified, to ensure that the piping will not be subjected to unacceptable thermal stresses.
In 1987 and 1988, thermal fatigue cracking and leakage in several PWR plants resulted
in the issuance of NRC Bulletin 88-08. In each of those events, the cracking was attributed to thermal cycling mechanisms not considered in initial plant design, and several actions were required of operating plants to assess susceptibility. The cracking was in normally stagnant non-isolable lines attached to RCS piping.
EPRI investigations into these events showed that two of the three cases described in the Bulletin could be attributed to in-leakage of cold water toward the RCS. Interaction of this leakage with turbulence/swirl penetration effects from the reactor coolant piping resulted in cyclic conditions of hot and cold water on the inside of the attached piping, eventually leading to thermal fatigue cracking and leakage. In the third case, the leakage was attributed to cyclic out-leakage past a normally closed valve. These events were summarized in an EPRI Materials Reliability Program (MRP). In none of these cases did the occurrence of thermal fatigue cracking result in a pipe rupture; however, leakage had occurred. For each of the events, the costs associated with evaluation, repair and plant unavailability were significant.
In 1994, Aptech Engineering prepared a response to NRC Bulletin 88-08 for Watts Bar Nuclear Plant (WBN) Unit 2. Similar to Unit 1, RCS branch lines were assessed for
potential thermal fatigue concerns. For Unit 2, the Loop 1, boron safety injection (SI) branch line was identified as the only line requiring future action. One of the recommended actions for this line was for the SI check valve to be physically relocated such that the distance between the RCS connection and the check valve exceeded 25 branch diameters (i.e., an increase in the non-isolable section length). At that time, it was believed that this modification would render this branch line unsusceptible to swirl penetration cyclic stratification.
In March 1999, the EPRI MRP Executive Group and Senior Representatives approved formation of the Thermal Fatigue Issue Task Group. Testing and evaluations were undertaken to better understand the thermal fatigue mechanisms that had been responsible for cracking in the non-isolable normally-stagnant branch lines. This
research culminated in the development of a methodology for evaluation of the phenomena that could lead to thermal cracking. Based on current understanding of the phenomenon and operating experience since 1994, the piping change described above would have no real influence on mitigating possible swirl penetration thermal fatigue.
Thus, this modification is no longer recommended for mitigation of this thermal fatigue
mechanism.
ENCLOSURE 1 NRC BULLETIN 88-08, THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS (RCS) - CLARIFICATION E1-2 WBN Unit 2 Action
In response to the experience gained from WBN Unit 1, the methodology used for WBN Unit 2 was to perform an engineering assessment of the RCS branch piping as described in MRP-146, "Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines." Unit 2 Calculation 1100448.301 entitled "MRP-146 Assessment of Normally Stagnant Non-Isolable Branch Lines" was performed to determine the susceptibility of non-isolable and stagnant branch lines off the RCS to thermal cycling mechanisms. The results of this assessment identified four lines that are susceptible to turbulence/swirl penetration effects that could lead to thermal fatigue cracking and leakage.
In compliance with NRC Bulletin 88-08, a susceptible drain line on each of the RCS Loops 1, 2, and 4 crossover legs was identified. Those three lines have been added to the augmented Pre-service Inspection Program WBN-2 PSI for baseline inspections of those areas deemed most susceptible to thermal fatigue cracking as noted in MRP-146.
The RCS Loop 1 cold leg SI boron injection line is the fourth line identified which will be monitored for in-leakage. Cyclic stratification only occurs when in-leakage is present. Lack of in-leakage could reduce the need for future inspections.
Clarification For WBN Unit 2, TVA will utilize the WBN Unit 1 approach which utilizes an EPRI calculational methodology and an augmented Pre-service Inspection Program for the three Unit 2 drain lines.
In addition, WBN Unit 2 has developed an acoustic monitoring program for the Unit 2 SI boron injection line governed by Procedure 2-TI-305, Acoustic Monitoring to Detect Leakage Through 2-FCV-63-25 & -26, which is similar to that used on WBN Unit 1 for monitoring its susceptible SI boron injection lines for in-leakage.
ENCLOSURE 2 LIST OF COMMITMENTS E2-1 1. The Regulatory Framework status for NRC Bulletin 88-08 shown in Reference 2 will be revised to reflect this change in the next update.