|
|
(6 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML14191A758 | | | number = ML14191A758 |
| | issue date = 07/07/2014 | | | issue date = 07/07/2014 |
| | title = 2014/07/07 NRR E-mail Capture - Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators | | | title = NRR E-mail Capture - Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators |
| | author name = Miernicki M J | | | author name = Miernicki M |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
| | addressee name = Arent G P | | | addressee name = Arent G |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000391 | | | docket = 05000391 |
Line 15: |
Line 15: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm Resource From:Miernicki, Michael Sent:Monday, July 07, 2014 9:28 AM To:garent@tva.gov; rhbryan@tva.gov Cc:Quichocho, Jessie; Poole, Justin | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Miernicki, Michael Sent: Monday, July 07, 2014 9:28 AM To: garent@tva.gov; rhbryan@tva.gov Cc: Quichocho, Jessie; Poole, Justin; Kulesa, Gloria; Johnson, Andrew |
| ; Kulesa, Gloria; Johnson, Andrew | |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Attachments: | | Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Attachments: RAI WBN2 Stm Gen T.S. 7-7-14docx..docx Attached please find RAIs from the Steam Generator Branch regarding Watts Bar 2 Developmental Technical Specifications Revision I. Please provide your responses within 30 days. |
| RAI WBN2 Stm Gen T.S. 7-7-14docx..docxAttached please find RAIs from the Steam Generator Branch regarding Watts Bar 2 Developmental Technical Specifications Revision I. Please provide your responses within 30 days. | | Mike Michael J. Miernicki Sr. Project Manager NRC/NRR/DORL/LP-WB 301-415-2304 1 |
|
| |
|
| Mike Michael J. Miernicki
| | Hearing Identifier: NRR_PMDA Email Number: 1418 Mail Envelope Properties (Michael.Miernicki@nrc.gov20140707092700) |
| | |
| Sr. Project Manager NRC/NRR/DORL/LP-WB 301-415-2304
| |
| | |
| Hearing Identifier: NRR_PMDA Email Number: 1418 Mail Envelope Properties (Michael.Miernicki@nrc.gov20140707092700) | |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Sent Date: 7/7/2014 9:27:38 AM Received Date: 7/7/2014 9:27:00 AM From: Miernicki, Michael Created By: Michael.Miernicki@nrc.gov Recipients: "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov> | | Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Sent Date: 7/7/2014 9:27:38 AM Received Date: 7/7/2014 9:27:00 AM From: Miernicki, Michael Created By: Michael.Miernicki@nrc.gov Recipients: |
| Tracking Status: None "Kulesa, Gloria" <Gloria.Kulesa@nrc.gov> Tracking Status: None "Johnson, Andrew" <Andrew.Johnson@nrc.gov> Tracking Status: None "garent@tva.gov" <garent@tva.gov> | | "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> |
| Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov> Tracking Status: None | | Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov> |
| | Tracking Status: None "Kulesa, Gloria" <Gloria.Kulesa@nrc.gov> |
| | Tracking Status: None "Johnson, Andrew" <Andrew.Johnson@nrc.gov> |
| | Tracking Status: None "garent@tva.gov" <garent@tva.gov> |
| | Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 288 7/7/2014 9:27:00 AM RAI WBN2 Stm Gen T.S. 7-7-14docx..docx 20968 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
|
| |
|
| Post Office: Files Size Date & Time MESSAGE 288 7/7/2014 9:27:00 AM RAI WBN2 Stm Gen T.S. 7-7-14docx..docx 20968 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
| | REQUEST FOR ADDITIONAL INFORMATION REVIEW OF DEVELOPMENTAL TECHNICAL SPECIFICATIONS REV. I WATTS BAR NUCLEAR PLANT UNIT 2 DOCKET NUMBER 50-391 BACKGROUND By letter dated June 16, 2014 (Agencywide Documents Access and Management System Accession No. ML14169A525), Tennessee Valley Authority (the licensee) submitted developmental Revision I of the Watts Bar Unit 2 Technical Specifications, for review and licensing by the U.S. Nuclear Regulatory Commission (NRC). |
| REQUEST FOR ADDITIONAL INFORMATION REVIEW OF DEVELOPMENTAL TECHNICAL SPECIFICATIONS REV. I WATTS BAR NUCLEAR PLANT UNIT 2 DOCKET NUMBER 50-391 BACKGROUND By letter dated June 16, 2014 (Agencywide Documents Access and Management System Accession No. ML14169A525), Tennessee Valley Authority (the licensee) submitted developmental Revision I of the Watts Bar Unit 2 Technical Specifications, for review and licensing by the U.S. Nuclear Regulatory Commission (NRC). | | The NRC staff has reviewed sections 3.4.17 Steam Generator (SG) Tube Integrity, B 3.4.17 Steam Generator (SG) Tube Integrity Bases, 5.7.2.12 Steam Generator (SG) |
| The NRC staff has reviewed sections 3.4.17 "Steam Generator (SG) Tube Integrity," B 3.4.17 "Steam Generator (SG) Tube Integrity Bases," 5.7.2.12 "Steam Generator (SG) Program," and 5.9.9 "Steam Generator Tube Inspection Report," which the licensee provided, and determined that additional information is required in order to complete the review. In order for the NRC staff to complete its review of the document listed above, please provide the following additional information: | | Program, and 5.9.9 Steam Generator Tube Inspection Report, which the licensee provided, and determined that additional information is required in order to complete the review. In order for the NRC staff to complete its review of the document listed above, please provide the following additional information: |
| QUESTION 1 On page B 3.4-90, the "Applicable Safety Analyses" section of B 3.4.17, "Steam Generator (SG) Tube Integrity Bases" does not adequately identify the leakage rates associated with the faulted and non-faulted SGs. The described leakage rates do not appear to be consistent with Section 15 of the Final Safety Analysis Report (Amendment 106). Please clarify which leakage rates are associated with the appropriate SGs. | | QUESTION 1 On page B 3.4-90, the Applicable Safety Analyses section of B 3.4.17, Steam Generator (SG) Tube Integrity Bases does not adequately identify the leakage rates associated with the faulted and non-faulted SGs. The described leakage rates do not appear to be consistent with Section 15 of the Final Safety Analysis Report (Amendment 106). Please clarify which leakage rates are associated with the appropriate SGs. |
| QUESTION 2 On page B 3.4-95, the "Surveillance Requirements" section of B 3.4.17, "Steam Generator (SG) Tube Integrity Bases" contains an extraneous paragraph. The second paragraph on this page is an optional paragraph from Technical Specification Task Force 510 (TSTF-510) that is only used when approved repair methods are contained in the Technical Specification 5.7.2.12, "Steam Generator (SG) Program." Since Watts Bar Unit 2 has no approved repair methods, please confirm that this paragraph will be removed. | | QUESTION 2 On page B 3.4-95, the Surveillance Requirements section of B 3.4.17, Steam Generator (SG) Tube Integrity Bases contains an extraneous paragraph. The second paragraph on this page is an optional paragraph from Technical Specification Task Force 510 (TSTF-510) that is only used when approved repair methods are contained in the Technical Specification 5.7.2.12, Steam Generator (SG) Program. |
| QUESTION 3 On pages 5.0-14 and 5.0-15, in Technical Specification 5.7.2.12, "Steam Generator (SG) Program," the incorporated wording is inconsistent with the wording in TSTF-510. In TSTF-510, at the end of the opening paragraph, the word "provisions" was deleted because it is repeated at the beginning of paragraph 5.7.2.12.a. The closing parenthesis in paragraph 5.7.2.12.b.1 was moved, because not all of the anticipated transients in the design specification are considered part of normal operating conditions. Finally, in paragraph 5.7.2.12.d, the phrase, "An assessment of degradation" was replaced with, "A degradation assessment" so that the wording would be consistent with that used in industry SG program documents. Please revise these pages to be consistent with TSTF-510. | | Since Watts Bar Unit 2 has no approved repair methods, please confirm that this paragraph will be removed. |
| QUESTION 4
| | QUESTION 3 On pages 5.0-14 and 5.0-15, in Technical Specification 5.7.2.12, Steam Generator (SG) Program, the incorporated wording is inconsistent with the wording in TSTF-510. In TSTF-510, at the end of the opening paragraph, the word provisions |
|
| |
|
| In Technical Specification 5.7.2.12, "Steam Generator (SG) Program," the most restrictive SG inspection periods were chosen from TSTF-510 (i.e., inspect 100% of the tubes at sequential periods of 60 effective full power months). Please confirm that the SGs at Watts Bar Unit 2 contain mill annealed Alloy 600 tubes. Also, please provide the model designation of the Watts Bar Unit 2 SGs.}} | | was deleted because it is repeated at the beginning of paragraph 5.7.2.12.a. The closing parenthesis in paragraph 5.7.2.12.b.1 was moved, because not all of the anticipated transients in the design specification are considered part of normal operating conditions. Finally, in paragraph 5.7.2.12.d, the phrase, An assessment of degradation was replaced with, A degradation assessment so that the wording would be consistent with that used in industry SG program documents. Please revise these pages to be consistent with TSTF-510. |
| | QUESTION 4 In Technical Specification 5.7.2.12, Steam Generator (SG) Program, the most restrictive SG inspection periods were chosen from TSTF-510 (i.e., inspect 100% of the tubes at sequential periods of 60 effective full power months). Please confirm that the SGs at Watts Bar Unit 2 contain mill annealed Alloy 600 tubes. Also, please provide the model designation of the Watts Bar Unit 2 SGs.}} |
|
---|
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] |
Text
NRR-PMDAPEm Resource From: Miernicki, Michael Sent: Monday, July 07, 2014 9:28 AM To: garent@tva.gov; rhbryan@tva.gov Cc: Quichocho, Jessie; Poole, Justin; Kulesa, Gloria; Johnson, Andrew
Subject:
Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Attachments: RAI WBN2 Stm Gen T.S. 7-7-14docx..docx Attached please find RAIs from the Steam Generator Branch regarding Watts Bar 2 Developmental Technical Specifications Revision I. Please provide your responses within 30 days.
Mike Michael J. Miernicki Sr. Project Manager NRC/NRR/DORL/LP-WB 301-415-2304 1
Hearing Identifier: NRR_PMDA Email Number: 1418 Mail Envelope Properties (Michael.Miernicki@nrc.gov20140707092700)
Subject:
Watts Bar 2 - RAIs - Developmental Tech Specs Rev I - Steam Generators Sent Date: 7/7/2014 9:27:38 AM Received Date: 7/7/2014 9:27:00 AM From: Miernicki, Michael Created By: Michael.Miernicki@nrc.gov Recipients:
"Quichocho, Jessie" <Jessie.Quichocho@nrc.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "Kulesa, Gloria" <Gloria.Kulesa@nrc.gov>
Tracking Status: None "Johnson, Andrew" <Andrew.Johnson@nrc.gov>
Tracking Status: None "garent@tva.gov" <garent@tva.gov>
Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 288 7/7/2014 9:27:00 AM RAI WBN2 Stm Gen T.S. 7-7-14docx..docx 20968 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REVIEW OF DEVELOPMENTAL TECHNICAL SPECIFICATIONS REV. I WATTS BAR NUCLEAR PLANT UNIT 2 DOCKET NUMBER 50-391 BACKGROUND By letter dated June 16, 2014 (Agencywide Documents Access and Management System Accession No. ML14169A525), Tennessee Valley Authority (the licensee) submitted developmental Revision I of the Watts Bar Unit 2 Technical Specifications, for review and licensing by the U.S. Nuclear Regulatory Commission (NRC).
The NRC staff has reviewed sections 3.4.17 Steam Generator (SG) Tube Integrity, B 3.4.17 Steam Generator (SG) Tube Integrity Bases, 5.7.2.12 Steam Generator (SG)
Program, and 5.9.9 Steam Generator Tube Inspection Report, which the licensee provided, and determined that additional information is required in order to complete the review. In order for the NRC staff to complete its review of the document listed above, please provide the following additional information:
QUESTION 1 On page B 3.4-90, the Applicable Safety Analyses section of B 3.4.17, Steam Generator (SG) Tube Integrity Bases does not adequately identify the leakage rates associated with the faulted and non-faulted SGs. The described leakage rates do not appear to be consistent with Section 15 of the Final Safety Analysis Report (Amendment 106). Please clarify which leakage rates are associated with the appropriate SGs.
QUESTION 2 On page B 3.4-95, the Surveillance Requirements section of B 3.4.17, Steam Generator (SG) Tube Integrity Bases contains an extraneous paragraph. The second paragraph on this page is an optional paragraph from Technical Specification Task Force 510 (TSTF-510) that is only used when approved repair methods are contained in the Technical Specification 5.7.2.12, Steam Generator (SG) Program.
Since Watts Bar Unit 2 has no approved repair methods, please confirm that this paragraph will be removed.
QUESTION 3 On pages 5.0-14 and 5.0-15, in Technical Specification 5.7.2.12, Steam Generator (SG) Program, the incorporated wording is inconsistent with the wording in TSTF-510. In TSTF-510, at the end of the opening paragraph, the word provisions
was deleted because it is repeated at the beginning of paragraph 5.7.2.12.a. The closing parenthesis in paragraph 5.7.2.12.b.1 was moved, because not all of the anticipated transients in the design specification are considered part of normal operating conditions. Finally, in paragraph 5.7.2.12.d, the phrase, An assessment of degradation was replaced with, A degradation assessment so that the wording would be consistent with that used in industry SG program documents. Please revise these pages to be consistent with TSTF-510.
QUESTION 4 In Technical Specification 5.7.2.12, Steam Generator (SG) Program, the most restrictive SG inspection periods were chosen from TSTF-510 (i.e., inspect 100% of the tubes at sequential periods of 60 effective full power months). Please confirm that the SGs at Watts Bar Unit 2 contain mill annealed Alloy 600 tubes. Also, please provide the model designation of the Watts Bar Unit 2 SGs.