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| | number = ML16053A023 | | | number = ML16053A023 |
| | issue date = 01/14/2016 | | | issue date = 01/14/2016 |
| | title = Arcb RAI Issues for Discussion in Jan 19 Public Meeting | | | title = NRR E-mail Capture - Watts Bar Unit 1 Arcb RAI Issues for Discussion in Jan 19 Public Meeting |
| | author name = Schaaf R | | | author name = Schaaf R |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To:Schrull, Edward Dustin (edschrull@tva.gov) | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To: Schrull, Edward Dustin (edschrull@tva.gov) |
| Cc:Szabo, Clinton William (cwszabo@tva.gov) | | Cc: Szabo, Clinton William (cwszabo@tva.gov) |
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| ==Subject:== | | ==Subject:== |
| Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: | | Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve. |
| Watts Bar Unit 1 ARCB RAI Issu es for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve. | | : Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o) |
| : Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o) Robert.Schaaf@nrc.gov | | Robert.Schaaf@nrc.gov 1 |
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| Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d) | | Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d) |
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| ==Subject:== | | ==Subject:== |
| Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients: "Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov> Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov> Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov | | Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients: |
| | "Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov> |
| | Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov> |
| | Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
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| Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
| | TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 |
| TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 | |
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| ==SUMMARY== | | ==SUMMARY== |
| OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) | | OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) |
| : 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no "undesirable radiological conditions" result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a "realistic" estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits. a. There appears to be a typo in the response. The second sentence refers to "0.01 Ci/ml (i.e., 10 Ci/g) action level" in Table 3.1, "Tritium Action Levels." However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct. b. The last two rows in the 5 th column, "Recommended Action," of Table 3.1 list urinalysis as "recommended" and "requested," respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensee's expectations should clearly be reflected in the program Action Statements. | | : 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no undesirable radiological conditions result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a realistic estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits. |
| : 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a "maximum allowable effluent concentration." This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM. Basically, TVA's answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM). This answer appears to misapply the instantaneous release criteria in the ODCM, which permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a. | | : a. There appears to be a typo in the response. The second sentence refers to 0.01 Ci/ml (i.e., 10 Ci/g) action level in Table 3.1, Tritium Action Levels. However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct. |
| : 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions.
| | : b. The last two rows in the 5th column, Recommended Action, of Table 3.1 list urinalysis as recommended and requested, respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensees expectations should clearly be reflected in the program Action Statements. |
| The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate.
| | : 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a maximum allowable effluent concentration. This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM. |
| | Basically, TVAs answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM). |
| | This answer appears to misapply the instantaneous release criteria in the ODCM, which |
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| 1 NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To:Schrull, Edward Dustin (edschrull@tva.gov)
| | permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a. |
| Cc:Szabo, Clinton William (cwszabo@tva.gov) | | : 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions. |
| | The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate. |
| | |
| | NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To: Schrull, Edward Dustin (edschrull@tva.gov) |
| | Cc: Szabo, Clinton William (cwszabo@tva.gov) |
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| ==Subject:== | | ==Subject:== |
| Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: | | Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve. |
| Watts Bar Unit 1 ARCB RAI Issu es for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve. | | : Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o) |
| : Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o) Robert.Schaaf@nrc.gov | | Robert.Schaaf@nrc.gov 1 |
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| Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d) | | Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d) |
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| ==Subject:== | | ==Subject:== |
| Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients: "Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov> Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov> Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov | | Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients: |
| | "Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov> |
| | Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov> |
| | Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
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| Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
| | TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 |
| TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 | |
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| ==SUMMARY== | | ==SUMMARY== |
| OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) | | OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) |
| : 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no "undesirable radiological conditions" result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a "realistic" estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits. a. There appears to be a typo in the response. The second sentence refers to "0.01 Ci/ml (i.e., 10 Ci/g) action level" in Table 3.1, "Tritium Action Levels." However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct. b. The last two rows in the 5 th column, "Recommended Action," of Table 3.1 list urinalysis as "recommended" and "requested," respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensee's expectations should clearly be reflected in the program Action Statements. | | : 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no undesirable radiological conditions result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a realistic estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits. |
| : 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a "maximum allowable effluent concentration." This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM. Basically, TVA's answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM). This answer appears to misapply the instantaneous release criteria in the ODCM, which permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a. | | : a. There appears to be a typo in the response. The second sentence refers to 0.01 Ci/ml (i.e., 10 Ci/g) action level in Table 3.1, Tritium Action Levels. However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct. |
| : 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions. | | : b. The last two rows in the 5th column, Recommended Action, of Table 3.1 list urinalysis as recommended and requested, respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensees expectations should clearly be reflected in the program Action Statements. |
| | : 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a maximum allowable effluent concentration. This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM. |
| | Basically, TVAs answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM). |
| | This answer appears to misapply the instantaneous release criteria in the ODCM, which |
| | |
| | permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a. |
| | : 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions. |
| The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate.}} | | The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate.}} |
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Category:E-Mail
MONTHYEARML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24215A3152024-07-24024 July 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-276-A, Revision 2 TS 3.8.1, AC Sources ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24157A3152024-06-0303 June 2024 2024 Sequoyah Commercial Grade Dedication Inspection Information Request ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24156A0062024-05-22022 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Recapture Low-Power Testing Time ML24130A0132024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.11 for MCR Chiller Completion Time ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24082A0662024-04-17017 April 2024 Email to Stuart Rymer on Exemption Decision for Watts Bar ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24082A0682024-04-10010 April 2024 Email to Stuart Rymer Re_ Availability of EA-FONSI for Watts Bar ML24100A8392024-04-0909 April 2024 Response from State of Tn Regarding Review of Environmental Assessment for Watts Bar Exemption Request ML24100A8402024-04-0808 April 2024 Email to State of Tn Requesting Review of Environmental Assessment for Watts Bar Exemption Request ML24071A0982024-03-0707 March 2024 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate ML24058A0962024-02-26026 February 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant License Amendment Request to Revise UFSAR for Hydrologic Analysis ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24033A0562024-02-0101 February 2024 NRR E-mail Capture - Correction Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-427-A, Revision 2 Regarding Degraded Barriers ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans 2024-09-10
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23166A1142023-06-15015 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 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) ML21095A0422021-04-0202 April 2021 NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR 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 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) 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) 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 2024-09-10
[Table view] |
Text
NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To: Schrull, Edward Dustin (edschrull@tva.gov)
Cc: Szabo, Clinton William (cwszabo@tva.gov)
Subject:
Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve.
- Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o)
Robert.Schaaf@nrc.gov 1
Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d)
Subject:
Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients:
"Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov>
Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov>
Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1
SUMMARY
OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050)
- 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no undesirable radiological conditions result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a realistic estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits.
- a. There appears to be a typo in the response. The second sentence refers to 0.01 Ci/ml (i.e., 10 Ci/g) action level in Table 3.1, Tritium Action Levels. However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct.
- b. The last two rows in the 5th column, Recommended Action, of Table 3.1 list urinalysis as recommended and requested, respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensees expectations should clearly be reflected in the program Action Statements.
- 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a maximum allowable effluent concentration. This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM.
Basically, TVAs answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM).
This answer appears to misapply the instantaneous release criteria in the ODCM, which
permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a.
- 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions.
The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate.
NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, January 14, 2016 2:18 PM To: Schrull, Edward Dustin (edschrull@tva.gov)
Cc: Szabo, Clinton William (cwszabo@tva.gov)
Subject:
Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Attachments: Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf Ed, See the attached file for the issues to be discussed at Tuesday's public meeting. The agenda is set up for Roger to take 10-15 minutes to expand on the attached and then to have an open dialog among Roger, DORL and technical division management, and TVA attendees regarding these issues to reach common understanding of path to resolve.
- Regards, Bob Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 301-415-6020 (o)
Robert.Schaaf@nrc.gov 1
Hearing Identifier: NRR_PMDA Email Number: 2667 Mail Envelope Properties (6672685481004b7983a0b0ffa24ac21d)
Subject:
Watts Bar Unit 1 ARCB RAI Issues for Discussion in Jan 19 Public Meeting.pdf Sent Date: 1/14/2016 2:17:38 PM Received Date: 1/14/2016 2:17:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients:
"Szabo, Clinton William (cwszabo@tva.gov)" <cwszabo@tva.gov>
Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov>
Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 665 1/14/2016 2:17:00 PM Watts Bar Unit 1 ARCB RAI Issues for 160119 public meeting.pdf 102095 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1
SUMMARY
OF UNRESOLVED RAI QUESTIONS REGARDING PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050)
- 1. ARCB Request for Additional Information (RAI) 1b Issue: The proposed amendment revises the previous commitment in Watts Bar Unit 1 Amendment 40 to control the concentration of tritium in the reactor coolant to 9.0 Ci/g. The original Tritium Production Topical Report was based on a 3.5 Ci/g reactor coolant control level so that no undesirable radiological conditions result from the tritium buildup in plant liquid systems. In the proposed amendment, TVA estimates that the Design Basis equilibrium tritium concentration in the reactor coolant could be as high as 29.8 Ci/g, with a realistic estimate of 12 Ci/g. Therefore, TVA needs to demonstrate that its tritium control and monitoring are adequate to ensure onsite exposures will not result in occupational doses above 10 CFR Part 20 limits.
- a. There appears to be a typo in the response. The second sentence refers to 0.01 Ci/ml (i.e., 10 Ci/g) action level in Table 3.1, Tritium Action Levels. However, 0.01 Ci/ml does not equal 10 Ci/g of water. Since both values are in the table, it is unclear which reference is correct.
- b. The last two rows in the 5th column, Recommended Action, of Table 3.1 list urinalysis as recommended and requested, respectively. This wording implies that these actions are optional, which is somewhat contradicted by Note 2 to the table and the text in the paragraph following the table. This response needs clarification. The licensees expectations should clearly be reflected in the program Action Statements.
- 2. ARCB RAI 6b Issue: TVA demonstrates that the effluent releases under design basis assumptions will not exceed the dose limit to a member of the public by demonstrating that the sum of the fractional effluent concentration limits (ECLs) from 10 CFR Part 20, Appendix B, are < 1.0, as allowed by 10 CFR Part 20. However, the tables provided only demonstrate this if the tritium releases from TPBAR operations are less than a maximum allowable effluent concentration. This maximum value in the tables was back calculated from the assumption that aggregate concentration(C)/ECLs = 1.0, but the amount of tritium this represents is only about half of the tritium that would be released from the TPBARS annually under the design basis assumptions. The response to the RAI on how TVA will insure effluent concentrations do not exceed the maximum allowable demonstrates some confusion about the ECL criteria in the Watts Bar ODCM.
Basically, TVAs answer to the question of how it will ensure that the annual effluent releases will not exceed C/ECL = 1.0 is that they will control effluent concentrations within the C/ECL < 10.0 (i.e., the instantaneous release criteria in the WBN ODCM).
This answer appears to misapply the instantaneous release criteria in the ODCM, which
permit instantaneous releases of 10 times the effluent concentration limits of Appendix B, to demonstrate that effluent releases will not exceed the design criteria in 10 CFR Part 50, Appendix I, per 10 CFR 50.36a.
- 3. ARCB RAI 6c Issue: The response appears to accept that TVA will not be able to meet the ECL limit by releasing the full design basis source term annual TPBAR release. It states that 45% of the annual TPBAR source term (equivalent to 413,000 gal. of effluent) will have to be held onsite. Since this is on an annual basis, there would appear to be no opportunity for future release if the plant is operated at the design basis assumptions.
The response to this RAI does not seem technically feasible unless the licensee intends to build additional onsite storage tanks to support continued operation at the design basis tritium release rate.