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| | issue date = 03/25/2010 | | | issue date = 03/25/2010 |
| | title = Preliminary RAIs - Watts Bar Unit 2 FSAR Chapter 12 | | | title = Preliminary RAIs - Watts Bar Unit 2 FSAR Chapter 12 |
| | author name = Wiebe J S | | | author name = Wiebe J |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
| | addressee name = Arent G P, Stockton R A | | | addressee name = Arent G, Stockton R |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000391 | | | docket = 05000391 |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Wiebe, Joel Sent: Thursday, March 25, 2010 8:24 AM To: 'Gordon Arent'; 'Ricky Stockton' | | {{#Wiki_filter:From: Wiebe, Joel Sent: Thursday, March 25, 2010 8:24 AM To: 'Gordon Arent'; 'Ricky Stockton' |
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| ==Subject:== | | ==Subject:== |
| Preliminary RAIs - FSAR Chapter 12 | | Preliminary RAIs - FSAR Chapter 12 |
| : 1. Amendment 95 revised FSAR Section 12.2.1.3 to include incore instrumentation thimble assemblies as important radioactive sources during refueling operations and deleted the incore detectors from this list. Provide an analysis of the impact of the dose rates to areas of the plant with the thimbles stored in the BMI guide tubes, as described. Describe the plant design features that minimize radiation exposure to plant individuals from this radiation source. | | : 1. Amendment 95 revised FSAR Section 12.2.1.3 to include incore instrumentation thimble assemblies as important radioactive sources during refueling operations and deleted the incore detectors from this list. Provide an analysis of the impact of the dose rates to areas of the plant with the thimbles stored in the BMI guide tubes, as described. |
| | Describe the plant design features that minimize radiation exposure to plant individuals from this radiation source. |
| : 2. Amendment 95 revised the estimated airborne radioactivity concentrations listed in Tables 12.2-19 and 12.2-22. Provide a description of what changed in the Watts Bar design that resulted in the revised values of airborne contamination? | | : 2. Amendment 95 revised the estimated airborne radioactivity concentrations listed in Tables 12.2-19 and 12.2-22. Provide a description of what changed in the Watts Bar design that resulted in the revised values of airborne contamination? |
| : 3. Amendment 97 revised the last paragraph of page 12.3-1 to read, "Typically, cleaner areas are exhausted to areas of higher potential airborne radioactivity-" [emphasis added]. List those areas of the plant where this is not the case and describe compensatory measures to minimize the spread of contamination from high to lower airborne areas. | | : 3. Amendment 97 revised the last paragraph of page 12.3-1 to read, Typically, cleaner areas are exhausted to areas of higher potential airborne radioactivity [emphasis added]. List those areas of the plant where this is not the case and describe compensatory measures to minimize the spread of contamination from high to lower airborne areas. |
| : 4. As required by 10 CFR 20.1406, describe the Watts Bar Unit 2 design features and operating procedures that will minimize, to the extent practicable, contamination of the facility and the environment to facilitate decommissioning. | | : 4. As required by 10 CFR 20.1406, describe the Watts Bar Unit 2 design features and operating procedures that will minimize, to the extent practicable, contamination of the facility and the environment to facilitate decommissioning. |
| : 5. Amendment 97, in Section 12.3.1 revised the discussion of the radiation source terms used in the facility design. | | : 5. Amendment 97, in Section 12.3.1 revised the discussion of the radiation source terms used in the facility design. |
| : a. NUREG-0800, "Standard Review Plan," identifies that 0.25% fuel cladding defects is considered an acceptable source term. NUREG-0847, "Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2," Supplement 14, Section 12.3 states that the descriptions of radioactive sources conform to the acceptance criteria of the Standard Review Plan and therefore are acceptable to the staff. The revised text refers to "1/8% failed fuel." Verify that the source term used for the design (normal operation) of the radiation shielding and ventilations system continues to be based on 0.25% fuel cladding defects, consistent with the acceptance criteria of the Standard Review Plan (NUREG 0800) and NUREG-0847, or provide information demonstrating the acceptability of the use of "1/8% failed fuel as the source term." | | : a. NUREG-0800, Standard Review Plan, identifies that 0.25% fuel cladding defects is considered an acceptable source term. NUREG-0847, Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Supplement 14, Section 12.3 states that the descriptions of radioactive sources conform to the acceptance criteria of the Standard Review Plan and therefore are acceptable to the staff. The revised text refers to 1/8% failed fuel. Verify that the source term used for the design (normal operation) of the radiation shielding and ventilations system continues to be based on 0.25% fuel cladding defects, consistent with the acceptance criteria of the Standard Review Plan (NUREG 0800) and NUREG-0847, or provide information demonstrating the acceptability of the use of 1/8% failed fuel as the source term. |
| : b. The last sentence of the revised text indicates that the radiation "accident levels are based on the Oak Ridge National Laboratory ORIGEN computer code." The ORIGEN code calculates the inventory of radionuclides in the reactor core, it does not determine the types and quantities of radioactive materials released into plant systems during the accident. Verify that the accident source term used in the design of the Watts Bar 2 radiation protection design features is consistent with the guidance in TID-14844 and NRREG 0737, Action Item II.B.2. | | : b. The last sentence of the revised text indicates that the radiation accident levels are based on the Oak Ridge National Laboratory ORIGEN computer code. The ORIGEN code calculates the inventory of radionuclides in the reactor core, it does not determine the types and quantities of radioactive materials released into plant systems during the accident. Verify that the accident source term used in the design of the Watts Bar 2 radiation protection design features is consistent with the guidance in TID-14844 and NRREG 0737, Action Item II.B.2. |
| : 6. Provide plant lay out drawings that indicate the radiation zoning for accident conditions in each of the vital areas (listed on pages 12.3-13 and 12.3-14 of the FSAR) and the planned access/egress routes to these vital areas. | | : 6. Provide plant lay out drawings that indicate the radiation zoning for accident conditions in each of the vital areas (listed on pages 12.3-13 and 12.3-14 of the FSAR) and the planned access/egress routes to these vital areas. |
| : 7. The text at the top of page 12.3-3 indicates that the layout drawings provided show the controlled access areas, decontamination areas, onsite laboratories and counting rooms. However, Amendment 97 deleted FSAR Figures 12.3-18 and 19 that contained the drawings of these design features. Provide drawings that indicate the location and arrangement of these radiation protection features. | | : 7. The text at the top of page 12.3-3 indicates that the layout drawings provided show the controlled access areas, decontamination areas, onsite laboratories and counting rooms. However, Amendment 97 deleted FSAR Figures 12.3-18 and 19 that contained the drawings of these design features. Provide drawings that indicate the location and arrangement of these radiation protection features. |
| : 8. Amendment 97 revised the frequency of the radiation monitor channel operability tests. Describe the criteria used in the Technical Specifications, ODCM, and plant procedures to determine the frequency of these tests. Provide a basis for concluding that the operability tests will be performed at a frequency sufficient to detect operability issues with the monitors in a timely manner. | | : 8. Amendment 97 revised the frequency of the radiation monitor channel operability tests. |
| | Describe the criteria used in the Technical Specifications, ODCM, and plant procedures to determine the frequency of these tests. Provide a basis for concluding that the operability tests will be performed at a frequency sufficient to detect operability issues with the monitors in a timely manner. |
| : 9. Provide a description of the radiation monitoring in areas where reactor fuel is handled or stored sufficient to demonstrate compliance with the requirements of 10 CFR 70.24 or 10 CFR 50.68. | | : 9. Provide a description of the radiation monitoring in areas where reactor fuel is handled or stored sufficient to demonstrate compliance with the requirements of 10 CFR 70.24 or 10 CFR 50.68. |
| : 10. Amendment 97 revised the description of the airborne monitoring channels on page 12.3-21 of the FSAR to replace the seven (7) channels of airborne monitors previously indicated for the Auxiliary Building with four (4) portable airborne monitors. | | : 10. Amendment 97 revised the description of the airborne monitoring channels on page 12.3-21 of the FSAR to replace the seven (7) channels of airborne monitors previously indicated for the Auxiliary Building with four (4) portable airborne monitors. |
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| : e. Verify that these monitors alarm locally on high airborne conditions as well as instrument malfunction and high radiation. | | : e. Verify that these monitors alarm locally on high airborne conditions as well as instrument malfunction and high radiation. |
| : 11. Provide a basis for deleting the radiation monitors (listed on table 12.3-4) from the Unit 1 and 2 post accident sample rooms. | | : 11. Provide a basis for deleting the radiation monitors (listed on table 12.3-4) from the Unit 1 and 2 post accident sample rooms. |
| : 12. Amendment 95 revised FSAR Section 12.4, "Dose Assessment." This revised assessment is of insufficient detail to meet the guidance in Regulatory Guide (RG) 8.19. In addition, the 120 person-rem/outage dose estimate in the revised assessment is not consistent with Watts Bar Unit 1 operating history. Provide a revised assessment that meets the criteria in RG 8.19 and describe what measures will be employed in the Unit 2 operations to improve on the annual collective dose experienced in operating Unit 1. | | : 12. Amendment 95 revised FSAR Section 12.4, Dose Assessment. This revised assessment is of insufficient detail to meet the guidance in Regulatory Guide (RG) 8.19. |
| : 13. The first sentence at the top of page 12.5-2 states that the "minimum qualification requirements for the Radiation Protection Manager are stated in Section 13.1.3" of the FSAR. Section 13.1.3 refers to Regulatory Guide 1.8 with the alternatives identified in NUCLEAR QUALITY ASSURANCE PLAN, TVA-NQA-PLN89-A. Clarify which alternatives in TVA-NQA-PLN89A could be applied to the Radiation Protection Manager, if any. 14. The discussion of High Radiation Area controls at the top of page 12.5-5 indicates that High Radiation Areas with dose rates greater than 1.0 rem/hour, but less than 500 rads/hour, will be posted as a Locked High Radiation Area, but does not indicate that they will actually be maintained locked. Clarify the proposed controls for these areas. | | In addition, the 120 person-rem/outage dose estimate in the revised assessment is not consistent with Watts Bar Unit 1 operating history. Provide a revised assessment that meets the criteria in RG 8.19 and describe what measures will be employed in the Unit 2 operations to improve on the annual collective dose experienced in operating Unit 1. |
| | : 13. The first sentence at the top of page 12.5-2 states that the minimum qualification requirements for the Radiation Protection Manager are stated in Section 13.1.3 of the |
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| | FSAR. Section 13.1.3 refers to Regulatory Guide 1.8 with the alternatives identified in NUCLEAR QUALITY ASSURANCE PLAN, TVA-NQA-PLN89-A. Clarify which alternatives in TVA-NQA-PLN89A could be applied to the Radiation Protection Manager, if any. |
| | : 14. The discussion of High Radiation Area controls at the top of page 12.5-5 indicates that High Radiation Areas with dose rates greater than 1.0 rem/hour, but less than 500 rads/hour, will be posted as a Locked High Radiation Area, but does not indicate that they will actually be maintained locked. Clarify the proposed controls for these areas. |
| Typographical Errors | | Typographical Errors |
| : 1. The header to page 12.2-35 of the FSAR indicates that it was revised by Amendment 95; however, it appears no change was made to this page. | | : 1. The header to page 12.2-35 of the FSAR indicates that it was revised by Amendment 95; however, it appears no change was made to this page. |
| : 2. On page 12.3-2, fourth paragraph, ANSI/ANS 18.1 Revision 0 of was dated 1976 not 1984, as stated. | | : 2. On page 12.3-2, fourth paragraph, ANSI/ANS 18.1 Revision 0 of was dated 1976 not 1984, as stated. |
| : 3. On Page 12.5.6, in the middle of the page, "ectering" should read "entering." | | : 3. On Page 12.5.6, in the middle of the page, ectering should read entering. |
| | | E-mail Properties Mail Envelope Properties (F371D08C516DE74F81193E6D891DC4AF304B3F30BF) |
| E-mail Properties Mail Envelope Properties (F371D08C516DE74F81193E6D891DC4AF304B3F30BF) | |
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| ==Subject:== | | ==Subject:== |
| Preliminary RAIs - FSAR Chapter 12 | | Preliminary RAIs - FSAR Chapter 12 Sent Date: 3/25/2010 8:23:45 AM Received Date: 3/25/2010 8:23:00 AM From: Wiebe, Joel Created By: Joel.Wiebe@nrc.gov Recipients: |
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| Sent Date: 3/25/2010 8:23:45 AM Received Date: 3/25/2010 8:23:00 AM From: Wiebe, Joel | |
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| Created By: Joel.Wiebe@nrc.gov | |
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| Recipients: | |
| GArent@tva.gov ('Gordon Arent') | | GArent@tva.gov ('Gordon Arent') |
| Tracking Status: None RAStockton@tva.gov ('Ricky Stockton') | | Tracking Status: None RAStockton@tva.gov ('Ricky Stockton') |
| Tracking Status: None WBN2HearingFile.Resource@nrc.gov (WBN2HearingFile Resource) | | Tracking Status: None WBN2HearingFile.Resource@nrc.gov (WBN2HearingFile Resource) |
| Tracking Status: None | | Tracking Status: None Post Office: |
| | | HQCLSTR02.nrc.gov |
| Post Office: | |
| HQCLSTR02.nrc.gov Files Size Date & Time | |
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| MESSAGE 18196 3/25/2010
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| Priority: olImportanceNormal ReplyRequested: False Return Notification: False
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| Sensitivity: olNormal Recipients received:}} | | Files Size Date & Time MESSAGE 18196 3/25/2010 Options Expiration Date: |
| | Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:}} |
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23030A3512023-01-25025 January 2023 Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information Request 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) 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 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 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 ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar 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 ML21102A1312021-04-19019 April 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 ML21095A0422021-04-0202 April 2021 NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR ML21095A0402021-04-0202 April 2021 NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0412021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0442021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21091A0772021-04-0101 April 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21095A0462021-03-22022 March 2021 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2 ML21039A6402021-02-0808 February 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency ML21012A2032021-01-11011 January 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection ML20350B5592020-12-15015 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML20338A3202020-12-0303 December 2020 Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information ML20322A4412020-11-17017 November 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20322A4392020-11-0505 November 2020 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20308A3512020-11-0202 November 2020 Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19)) ML20253A1782020-09-0909 September 2020 Emergency Preparedness Program Inspection Request for Information ML20266G4592020-08-14014 August 2020 Notification of Inspection and Request for Information ML20196L8622020-07-14014 July 2020 NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology ML20086G4802020-03-26026 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2 ML20085G3572020-03-25025 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20084M1942020-03-24024 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20083J3952020-03-12012 March 2020 NRR E-mail Capture - Draft Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML19340A6842019-12-0505 December 2019 NRR E-mail Capture - Request for Additional Information for WBN2 Request for One-Time Extension of Completion Time for TS 3.7.8 (L-2019-LLA-0020) ML19218A0302019-08-0505 August 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19218A0282019-07-25025 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Draft Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19186A4352019-07-0505 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Correction to Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 ML19169A3592019-06-18018 June 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19106A0462019-04-15015 April 2019 NRR E-mail Capture - Watts BAR, Units 1 and 2 Request for Additional Informatin (RAI) Regarding Changes to Technical Specifications Sections 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML19071A3542019-03-0808 March 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request to Adopt TSTF-425 to Relocate Specific Surveillance Frequency Requirements to Licensee-Controlled Program ML18313A2202018-11-0707 November 2018 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML18282A6372018-10-0909 October 2018 NRR E-mail Capture - RAIs (Final) - LAR to Revise the Steam Generator Technical Specifications for Watts Bar Nuclear Plant, Unit 2 ML18270A2362018-09-26026 September 2018 NRR E-mail Capture - Watts Bar Units 1 and 2 RAIs - Modify TS 3.8.9 Completion Time for Inoperable 120V AC Vital Buses (L-2018-LLA-0050) ML18240A0702018-08-27027 August 2018 NRR E-mail Capture - RAI for Watts Bar Unit 2 Tpbars LAR and Watts Bar Units 1 and 2 LAR Related to Fuel Storage ML18199A1822018-07-17017 July 2018 NRR E-mail Capture - Request for Additional Information Regarding Watts Bar Unit 1 Extension of Surveillance Requirement Intervals ML18123A3942018-05-0303 May 2018 NRR E-mail Capture - Request for Additional Information Unit 2 Cycle 1 Steam Generator Tube Inspection Report ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML18031A6592018-02-0606 February 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1 and Technical Specifications Related to Fuel Storage ML18016A0112018-01-12012 January 2018 Draft Request for Additional Information Exigent Amendment Request for Inoperable Reactor Coolant Temperature Indication ML17226A0032017-08-11011 August 2017 NRR E-mail Capture - Watts Bar, Unit 1 - Final Request for Additional Information Concerning Request to Amend Turbine Trip Low Fluid Oil Pressure Reactor Protection System Trip Setpoint 2023-06-15
[Table view] |
Text
From: Wiebe, Joel Sent: Thursday, March 25, 2010 8:24 AM To: 'Gordon Arent'; 'Ricky Stockton'
Subject:
Preliminary RAIs - FSAR Chapter 12
- 1. Amendment 95 revised FSAR Section 12.2.1.3 to include incore instrumentation thimble assemblies as important radioactive sources during refueling operations and deleted the incore detectors from this list. Provide an analysis of the impact of the dose rates to areas of the plant with the thimbles stored in the BMI guide tubes, as described.
Describe the plant design features that minimize radiation exposure to plant individuals from this radiation source.
- 2. Amendment 95 revised the estimated airborne radioactivity concentrations listed in Tables 12.2-19 and 12.2-22. Provide a description of what changed in the Watts Bar design that resulted in the revised values of airborne contamination?
- 3. Amendment 97 revised the last paragraph of page 12.3-1 to read, Typically, cleaner areas are exhausted to areas of higher potential airborne radioactivity [emphasis added]. List those areas of the plant where this is not the case and describe compensatory measures to minimize the spread of contamination from high to lower airborne areas.
- 4. As required by 10 CFR 20.1406, describe the Watts Bar Unit 2 design features and operating procedures that will minimize, to the extent practicable, contamination of the facility and the environment to facilitate decommissioning.
- 5. Amendment 97, in Section 12.3.1 revised the discussion of the radiation source terms used in the facility design.
- a. NUREG-0800, Standard Review Plan, identifies that 0.25% fuel cladding defects is considered an acceptable source term. NUREG-0847, Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Supplement 14, Section 12.3 states that the descriptions of radioactive sources conform to the acceptance criteria of the Standard Review Plan and therefore are acceptable to the staff. The revised text refers to 1/8% failed fuel. Verify that the source term used for the design (normal operation) of the radiation shielding and ventilations system continues to be based on 0.25% fuel cladding defects, consistent with the acceptance criteria of the Standard Review Plan (NUREG 0800) and NUREG-0847, or provide information demonstrating the acceptability of the use of 1/8% failed fuel as the source term.
- b. The last sentence of the revised text indicates that the radiation accident levels are based on the Oak Ridge National Laboratory ORIGEN computer code. The ORIGEN code calculates the inventory of radionuclides in the reactor core, it does not determine the types and quantities of radioactive materials released into plant systems during the accident. Verify that the accident source term used in the design of the Watts Bar 2 radiation protection design features is consistent with the guidance in TID-14844 and NRREG 0737, Action Item II.B.2.
- 6. Provide plant lay out drawings that indicate the radiation zoning for accident conditions in each of the vital areas (listed on pages 12.3-13 and 12.3-14 of the FSAR) and the planned access/egress routes to these vital areas.
- 7. The text at the top of page 12.3-3 indicates that the layout drawings provided show the controlled access areas, decontamination areas, onsite laboratories and counting rooms. However, Amendment 97 deleted FSAR Figures 12.3-18 and 19 that contained the drawings of these design features. Provide drawings that indicate the location and arrangement of these radiation protection features.
- 8. Amendment 97 revised the frequency of the radiation monitor channel operability tests.
Describe the criteria used in the Technical Specifications, ODCM, and plant procedures to determine the frequency of these tests. Provide a basis for concluding that the operability tests will be performed at a frequency sufficient to detect operability issues with the monitors in a timely manner.
- 9. Provide a description of the radiation monitoring in areas where reactor fuel is handled or stored sufficient to demonstrate compliance with the requirements of 10 CFR 70.24 or 10 CFR 50.68.
- 10. Amendment 97 revised the description of the airborne monitoring channels on page 12.3-21 of the FSAR to replace the seven (7) channels of airborne monitors previously indicated for the Auxiliary Building with four (4) portable airborne monitors.
- a. Verify that these portable monitors will detect a 10 DAC-hour change in airborne levels in the areas monitored.
- b. Describe the controls in place to ensure these portable monitors will not be inadvertently relocated from their intended monitoring areas.
- c. Are these monitors different than the CAMs used to monitor the sample rooms, and waste packing areas?
- d. Verify that the Containment upper and lower monitors are able to detect a 10 DAC-hour change in airborne levels in the areas they monitor.
- e. Verify that these monitors alarm locally on high airborne conditions as well as instrument malfunction and high radiation.
- 11. Provide a basis for deleting the radiation monitors (listed on table 12.3-4) from the Unit 1 and 2 post accident sample rooms.
- 12. Amendment 95 revised FSAR Section 12.4, Dose Assessment. This revised assessment is of insufficient detail to meet the guidance in Regulatory Guide (RG) 8.19.
In addition, the 120 person-rem/outage dose estimate in the revised assessment is not consistent with Watts Bar Unit 1 operating history. Provide a revised assessment that meets the criteria in RG 8.19 and describe what measures will be employed in the Unit 2 operations to improve on the annual collective dose experienced in operating Unit 1.
- 13. The first sentence at the top of page 12.5-2 states that the minimum qualification requirements for the Radiation Protection Manager are stated in Section 13.1.3 of the
FSAR. Section 13.1.3 refers to Regulatory Guide 1.8 with the alternatives identified in NUCLEAR QUALITY ASSURANCE PLAN, TVA-NQA-PLN89-A. Clarify which alternatives in TVA-NQA-PLN89A could be applied to the Radiation Protection Manager, if any.
- 14. The discussion of High Radiation Area controls at the top of page 12.5-5 indicates that High Radiation Areas with dose rates greater than 1.0 rem/hour, but less than 500 rads/hour, will be posted as a Locked High Radiation Area, but does not indicate that they will actually be maintained locked. Clarify the proposed controls for these areas.
Typographical Errors
- 1. The header to page 12.2-35 of the FSAR indicates that it was revised by Amendment 95; however, it appears no change was made to this page.
- 2. On page 12.3-2, fourth paragraph, ANSI/ANS 18.1 Revision 0 of was dated 1976 not 1984, as stated.
- 3. On Page 12.5.6, in the middle of the page, ectering should read entering.
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Subject:
Preliminary RAIs - FSAR Chapter 12 Sent Date: 3/25/2010 8:23:45 AM Received Date: 3/25/2010 8:23:00 AM From: Wiebe, Joel Created By: Joel.Wiebe@nrc.gov Recipients:
GArent@tva.gov ('Gordon Arent')
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