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| | number = ML101600488 | | | number = ML101600488 |
| | issue date = 06/03/2010 | | | issue date = 06/03/2010 |
| | title = 001 - Subsection 2.5 Question 1- Feb 6, 1984 Letter | | | title = Subsection 2.5 Question 1- Feb 6, 1984 Letter |
| | author name = | | | author name = |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
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| =Text= | | =Text= |
| {{#Wiki_filter:001 - Subsection 2.5 - Question 1- Feb 6, 1984 Letter UNITBO STATES GOVERNi\lE:N'J' Memorandum TO M.G.Msarsa.Director of Services and TENNESSEE VALLEY AUTHORITYCE B*8402060 0 It Field Operations, 268 401B-C FROM R.W.Cantrell, Manager of Engineering Design (Acting), WI1A9 C-K DATE FEB 6 1984 840209F0116 | | {{#Wiki_filter:001 - Subsection 2.5 - Question 1- Feb 6, 1984 Letter UNITBO STATES GOVERNi\lE:N'J' Memorandum TENNESSEE VALLEY AUTHORITY CEB*84 0 2 0 6 0 0It TO M. G. Msarsa. Director of Services and Field Operations, 268 401B-C FROM R. W. Cantrell, Manager of Engineering Design (Acting), WI1A9 C-K DATE FEB 6 1984 840209F0116 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATTS BAR NUCLEAR PLANT UNITS 1 AND 2-SETTLEMENT STATIONS | | WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 - SETTLEMENT STATIONS |
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| ==References:== | | ==References:== |
| | : 1. M. N. Sprouse's memorandum to you dated June 30. 1980 (COB 800630 001) |
| | : 2. J. C. Standifer's memorandum to R. O. Barnett dated August 30. 1983 (WBP 830830 024), copy attached The Data Services Branch is currently making semiannual readings for the diesel generator building (DGB) and the waste management building (WMB) |
| | (also known as the waste packaging area). The DGB settlement has been recorded for 8 years, and for the last 3 years there has been no perceptible increase in the settlement. The WMB has been monitored for 7 years and for the last 2 years has only had 0.05 inches of settlement. |
| | Based on these settlement readings for the DGB and WMB. the settlement surveys are no longer needed. Therefore, we request that the settlement readings be discontinued on the DGB and the HMB. As preViously stated in the memorandum from J. C. Standifer to R. O. Barnett, the settlement monitoring program for the turbine generators should also be discontinued. |
| | Original Signed By R. G. Domer R. W. Cantrell 1W\l'8~ |
| | ROB:JMR:BSH Owt Attachment \ |
| | J~~ cc: R, O. Barnett, W90224 C-K (2) |
| | ~Det1o C. Bonine. E7B24 C-MEDS WSB63 C-K R, M. Pierce, 104 ESTA-K J. C. Standifer, 204 GB-K G. Wadewitz. Watts Bar Nuclear CONST (3) |
| | Principally Prepared By: J, M. Hoskins, Extension 6905 Buy U.S. Savings Bonds Regularly on the Pa)'ro)l Savings Plan |
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| 1.M.N.Sprouse's memorandum to you dated June 30.1980 (COB 800630 001)2.J.C.Standifer's memorandum to R.O.Barnett dated August 30.1983 (WBP 830830 024), copy attached The Data Services Branch is currently making semiannual readings for the diesel generator building (DGB)and the waste management building (WMB)(also known as the waste packaging area).The DGB settlement has been recorded for 8 years, and for the last 3 years there has been no perceptible increase in the settlement.
| | UNITED STATES GOVERNMENT Memorandum TENNESSEE VALLEY AUTHORITY WBP '83 0830 0 24 TO R. O. Barnett, Chief, Civil Engineering Support Branch, W9D224 C-K FROM J. C. Standifer, Project Manager, Watts Bar Design Project, 204 GB-K S30 902 DATE |
| The WMB has been monitored for 7 years and for the last 2 years has only had 0.05 inches of settlement.
| |
| Based on these settlement readings for the DGB and WMB.the settlement surveys are no longer needed.Therefore, we request that the settlement readings be discontinued on the DGB and the HMB.As preViously stated in the memorandum from J.C.Standifer to R.O.Barnett, the settlement monitoring program for the turbine generators should also be discontinued.
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| Original Signed By R.G.Domer Owt R.W.Cantrell ROB:JMR:BSH Attachment
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| \cc: R, O.Barnett, W90224 C-K (2)C.Bonine.E7B24 C-MEDS WSB63 C-K R, M.Pierce, 104 ESTA-K J.C.Standifer, 204 GB-K G.Wadewitz.Watts Bar Nuclear CONST (3)Principally Prepared By: J, M.Hoskins, Extension 6905 Buy U.S.Savings Bonds Regularly on the Pa)'ro)l Savings Plan UNITED STATES GOVERNMENT Memorandum TO R.O.Barnett, Chief, Civil Engineering TENNESSEE VALLEY AUTHORITY WBP'8308 300 24 Support Branch, W9D224 C-K FROM J.C.Standifer, Project Manager, Watts Bar Design Project, 204 GB-K DATE
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| ==SUBJECT:== | | ==SUBJECT:== |
| AUG 301983 WATTS BAR NUCLEAR PLANT-SETTLEN"T MONITORING"OGWI S 3 0 9 0 2T0176 (j) | | |
| | AUG 301983 WATTS BAR NUCLEAR PLANT - SETTLEN"T MONITORING "OGWI T0176(j) |
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| ==Reference:== | | ==Reference:== |
| | | Your memorandum to me dated July 15, 1983 (CEB 830715 011) |
| Your memorandum to me dated July 15, 1983 (CEB 830715 011)As requelH:ed in the referenced memorandum, we have conducted an extensive investigation and have determined that EN DES has no need to continue monitoring the settlement readings for the turbine generators at Watts Bar based on the following reasons: 1.We have found no licensing commitments in the FSAR to continue settlement readings on non-category I structures of which the turbine building is classified. | | As requelH:ed in the referenced memorandum, we have conducted an extensive investigation and have determined that EN DES has no need to continue monitoring the settlement readings for the turbine generators at Watts Bar based on the following reasons: |
| 2, We have found no requirements in Westinghouse's documents to monitor settlement of the turbine generator fOundation. | | : 1. We have found no licensing commitments in the FSAR to continue settlement readings on non-category I structures of which the turbine building is classified. |
| 3.From a review of the settlement readings over the past eight years, the settlement of the rock-supported turbine generator foundation has been negligible. | | 2, We have found no requirements in Westinghouse's documents to monitor settlement of the turbine generator fOundation. |
| The latest (November 1982)readings have changed only 1/16 inch+/-from the initial readings, 4.From discussions we have had with several people in EN DES and NUC PR, no one knows of any benefit to continue this program.Therefore, we have concluded that the settlement monitoring program for the turbine generators can be discontinued. | | : 3. From a review of the settlement readings over the past eight years, the settlement of the rock-supported turbine generator foundation has been negligible. The latest (November 1982) readings have changed only 1/16 inch +/- from the initial readings, |
| The notes on drawing 10N203-2 will be revised per EeN 4256 on or before October 12, 1983, to discontinue the settlement for the turbine generators. | | : 4. From discussions we have had with several people in EN DES and NUC PR, no one knows of any benefit to continue this program. |
| HDH,ER cc: C.A.Chandley, W7C126 C-K R.M.Pierce, 104 ESTA-K M.N.Sprouse, W11A9 C-K G.Wadewitz, WBN CONST (3)B.W.Whittier, W2D190 C-\AUG 30198.3-H.J.Gteen, 1750 C 2-C MEDS, W5B63 C-K Principally Prepared By: H.D.Hutchinson, Extension 3511 Buy U.S.Savini? | | Therefore, we have concluded that the settlement monitoring program for the turbine generators can be discontinued. |
| on the Pa'yroll Savings Plan}} | | The notes on drawing 10N203-2 will be revised per EeN 4256 on or before October 12, 1983, to discontinue the settlement r~adingg for the turbine generators. |
| | HDH,ER \ |
| | cc: C. A. Chandley, W7C126 C-K AUG 30198.3 - MNS:l\~\ |
| | R. M. Pierce, 104 ESTA-K H. J. Gteen, 1750 C 2-C M. N. Sprouse, W11A9 C-K MEDS, W5B63 C-K G. Wadewitz, WBN CONST (3) |
| | B. W. Whittier, W2D190 C-Principally Prepared By: H. D. Hutchinson, Extension 3511 Buy U.S. Savini? B?~~!~egularly on the Pa'yroll Savings Plan}} |
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Category:Report
MONTHYEARWBL-24-047, Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2024-09-25025 September 2024 Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report WBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) ML21060A9132021-03-17017 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations2017-10-13013 October 2017 Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index2017-05-30030 May 2017 Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit2015-09-21021 September 2015 Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-06-16016 June 2015 Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals2015-04-10010 April 2015 Severe Accident Management Alternatives for Reactor Coolant Pump Seals 2024-09-25
[Table view] Category:Miscellaneous
MONTHYEARWBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule ML14149A1502014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14133A5422014-05-23023 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13246A0222013-08-28028 August 2013 Submittal of Pre-op Test Instruction ML13178A2812013-06-26026 June 2013 10 CFR 50.59 Summary Report Supplement ML13144A5762013-05-22022 May 2013 Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1) ML13126A2942013-04-29029 April 2013 10 CFR 50.59 Summary Report ML13121A0602013-04-29029 April 2013 Commitment Summary Report ML13080A3632013-03-18018 March 2013 Enclosure 3, Summer 2011 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A3662013-03-18018 March 2013 Enclosure 1, Summer 2010 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A0732013-03-12012 March 2013 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation.. ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML12356A3172012-12-17017 December 2012 Submittal of Pre-op Test Instruction, 2-PTI-063-06, Revision 0, Safety Injection System Check Valve Test. ML12335A3402012-11-27027 November 2012 Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of ML13108A2842012-11-12012 November 2012 Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12236A1642012-07-19019 July 2012 Enclosure 1 Evaluation of Proposed Changes Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 ML12223A1832012-03-29029 March 2012 Environmental Protection Agency 2012 - Facility Detail Report - Environmental Facts Warehouse Fii - Moccasin Bend Wwtp ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 ML11341A1572011-11-30030 November 2011 Attachments 7 Through 9, WNA-CN-00157-WBT-NP, Revision 1, CAW-11-3316, and WBT-D-3566 Np, Incore Instrument System Signal Processing System Isolation Requirement ML11326A2842011-11-18018 November 2011 Commitment Summary Report ML11257A0502011-08-31031 August 2011 Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme ML1104003852011-02-0707 February 2011 Enclosure 2, Appendix a, Hydrothermal Effects on the Ichthyhoplankton from the Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir 2024-03-05
[Table view] |
Text
001 - Subsection 2.5 - Question 1- Feb 6, 1984 Letter UNITBO STATES GOVERNi\lE:N'J' Memorandum TENNESSEE VALLEY AUTHORITY CEB*84 0 2 0 6 0 0It TO M. G. Msarsa. Director of Services and Field Operations, 268 401B-C FROM R. W. Cantrell, Manager of Engineering Design (Acting), WI1A9 C-K DATE FEB 6 1984 840209F0116
SUBJECT:
WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 - SETTLEMENT STATIONS
References:
- 1. M. N. Sprouse's memorandum to you dated June 30. 1980 (COB 800630 001)
- 2. J. C. Standifer's memorandum to R. O. Barnett dated August 30. 1983 (WBP 830830 024), copy attached The Data Services Branch is currently making semiannual readings for the diesel generator building (DGB) and the waste management building (WMB)
(also known as the waste packaging area). The DGB settlement has been recorded for 8 years, and for the last 3 years there has been no perceptible increase in the settlement. The WMB has been monitored for 7 years and for the last 2 years has only had 0.05 inches of settlement.
Based on these settlement readings for the DGB and WMB. the settlement surveys are no longer needed. Therefore, we request that the settlement readings be discontinued on the DGB and the HMB. As preViously stated in the memorandum from J. C. Standifer to R. O. Barnett, the settlement monitoring program for the turbine generators should also be discontinued.
Original Signed By R. G. Domer R. W. Cantrell 1W\l'8~
ROB:JMR:BSH Owt Attachment \
J~~ cc: R, O. Barnett, W90224 C-K (2)
~Det1o C. Bonine. E7B24 C-MEDS WSB63 C-K R, M. Pierce, 104 ESTA-K J. C. Standifer, 204 GB-K G. Wadewitz. Watts Bar Nuclear CONST (3)
Principally Prepared By: J, M. Hoskins, Extension 6905 Buy U.S. Savings Bonds Regularly on the Pa)'ro)l Savings Plan
UNITED STATES GOVERNMENT Memorandum TENNESSEE VALLEY AUTHORITY WBP '83 0830 0 24 TO R. O. Barnett, Chief, Civil Engineering Support Branch, W9D224 C-K FROM J. C. Standifer, Project Manager, Watts Bar Design Project, 204 GB-K S30 902 DATE
SUBJECT:
AUG 301983 WATTS BAR NUCLEAR PLANT - SETTLEN"T MONITORING "OGWI T0176(j)
Reference:
Your memorandum to me dated July 15, 1983 (CEB 830715 011)
As requelH:ed in the referenced memorandum, we have conducted an extensive investigation and have determined that EN DES has no need to continue monitoring the settlement readings for the turbine generators at Watts Bar based on the following reasons:
- 1. We have found no licensing commitments in the FSAR to continue settlement readings on non-category I structures of which the turbine building is classified.
2, We have found no requirements in Westinghouse's documents to monitor settlement of the turbine generator fOundation.
- 3. From a review of the settlement readings over the past eight years, the settlement of the rock-supported turbine generator foundation has been negligible. The latest (November 1982) readings have changed only 1/16 inch +/- from the initial readings,
- 4. From discussions we have had with several people in EN DES and NUC PR, no one knows of any benefit to continue this program.
Therefore, we have concluded that the settlement monitoring program for the turbine generators can be discontinued.
The notes on drawing 10N203-2 will be revised per EeN 4256 on or before October 12, 1983, to discontinue the settlement r~adingg for the turbine generators.
HDH,ER \
cc: C. A. Chandley, W7C126 C-K AUG 30198.3 - MNS:l\~\
R. M. Pierce, 104 ESTA-K H. J. Gteen, 1750 C 2-C M. N. Sprouse, W11A9 C-K MEDS, W5B63 C-K G. Wadewitz, WBN CONST (3)
B. W. Whittier, W2D190 C-Principally Prepared By: H. D. Hutchinson, Extension 3511 Buy U.S. Savini? B?~~!~egularly on the Pa'yroll Savings Plan