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Category:E-Mail
MONTHYEARML24022A2592024-01-22022 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 ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22081A2222022-03-22022 March 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 1, License Amendment Request to Revise Allowable Value for TS Table 3.3.2-1, Function 6.e(1) ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML22131A1902022-02-23023 February 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Request to Revise the Reactor Vessel Surveillance Capsule Withdrawal Schedule ML22046A0392022-02-15015 February 2022 NRR E-mail Capture - Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22011A0382022-01-10010 January 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A ML21306A2452021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level ML21223A2592021-08-11011 August 2021 Affidavit - Prop Slides - Partially Closed Meeting with TVA Potential Watts Bar, Unit 2 Tube Locking LAR ML21221A2602021-08-0909 August 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary ML21215A1152021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21215A1142021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21197A0452021-07-15015 July 2021 WBN U1 Isi/Sgisi Request for Information (RFI) Letter ML21193A2422021-07-12012 July 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 2 Technical Specifications Related to Steam Generator Inspection/Repair Program Provisions ML21189A0202021-06-29029 June 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specifications 3.3.6 and 3.3.7 Re Radiation Monitor Redundant Unit of Measure 2024-01-22
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Text
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.pdf Please 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 1
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
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.
E1-1
ENCLOSURE 1 NRC BULLETIN 88-08, THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS (RCS) - CLARIFICATION 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.
E1-2
ENCLOSURE 2 LIST OF COMMITMENTS
- 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.
E2-1