ML12030A013: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| (2 intermediate revisions by the same user not shown) | |||
| Line 2: | Line 2: | ||
| number = ML12030A013 | | number = ML12030A013 | ||
| issue date = 01/24/2012 | | issue date = 01/24/2012 | ||
| title = | | title = OL - Draft Questions on Technical Specifications | ||
| author name = | | author name = | ||
| author affiliation = NRC/NRR | | author affiliation = NRC/NRR | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:WBN2Public Resource From: Poole, Justin Sent: Tuesday, January 24, 2012 8:14 AM To: Arent, Gordon Cc: Bryan, Robert H Jr; WBN2HearingFile Resource | ||
==Subject:== | ==Subject:== | ||
Draft Questions on Technical Specifications Attachments: | Draft Questions on Technical Specifications Attachments: Watts Bar 2 Technical Specifications RAI.docx | ||
Watts Bar 2 Technical Specifications RAI.docx Gordon, In reviewing | : Gordon, In reviewing TVAs proposed TS for WBN 2, the staff has come up with the attached questions. Please review to ensure that the RAI questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. If further clarification is needed, and you would like to discuss the questions in a conference call, let us know. Please also let me know how much time Tennessee Valley Authority (TVA) needs to respond to the RAI questions. | ||
This email does not convey a formal NRC staff position, and it does not formally request for additional information. | This email does not convey a formal NRC staff position, and it does not formally request for additional information. | ||
Justin C. Poole Sr. Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)415-2048 | Justin C. Poole Sr. Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov 1 | ||
Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 640 Mail Envelope Properties (19D990B45D535548840D1118C451C74DC8B74C363D) | |||
Hearing Identifier: | |||
==Subject:== | ==Subject:== | ||
Draft Questions on Technical Specifications | Draft Questions on Technical Specifications Sent Date: 1/24/2012 8:14:06 AM Received Date: 1/24/2012 8:14:09 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients: | ||
Tracking Status: None | "Bryan, Robert H Jr" <rhbryan@tva.gov> | ||
Tracking Status: None | Tracking Status: None "WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov> | ||
Tracking Status: None "Arent, Gordon" <garent@tva.gov> | |||
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 833 1/24/2012 8:14:09 AM Watts Bar 2 Technical Specifications RAI.docx 28154 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received: | |||
In reviewing the following sections of the proposed Watts Bar Unit 2 Technical Specifications (Development Revision F), the staff has determined that additional information is needed to complete its review. | In reviewing the following sections of the proposed Watts Bar Unit 2 Technical Specifications (Development Revision F), the staff has determined that additional information is needed to complete its review. | ||
1.1, Definitions - LEAKAGE 3.4.13, RCS [Reactor Coolant System] Operational LEAKAGE 3.4.17, Steam Generator (SG) Tube Integrity 5.7.2.12, Steam Generator (SG) Program 5.9.9, Steam Generator Tube Inspection Report | 1.1, Definitions - LEAKAGE 3.4.13, RCS [Reactor Coolant System] Operational LEAKAGE 3.4.17, Steam Generator (SG) Tube Integrity 5.7.2.12, Steam Generator (SG) Program 5.9.9, Steam Generator Tube Inspection Report Please provide a response to the following questions/comments: | ||
: 1. Section 5.7.2.12.d.1 indicates that 100% of the tubing will be inspected in the first refueling outage. Since Watts Bar Unit 2 may replace steam generators (i.e., have a first refueling outage without replacing steam generators and may have a first refueling outage following steam generator replacement), please discuss your plans to modify this requirement to ensure both conditions are addressed (e.g., during the first refueling outage following steam generator installation.). | |||
Please provide a response to the following questions/comments: | : 2. Since your proposed technical specifications were prepared, the NRC staff has approved Technical Specification Task Force Traveler 510 (TSTF-510), Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (ML110610350). The staffs review is summarized in a Notice of Availability dated October 19, 2011 (ML112101604). Since this TSTF Traveler addresses implementation issues associated with the inspections periods and addresses other administrative changes and clarifications which improve the technical specifications, please discuss your plans to incorporate the TSTF-510, Revision 2, changes into your proposed technical specifications. | ||
: 1. Section 5.7.2.12.d.1 indicates that 100% of the tubing will be inspected in the first refueling outage. Since Watts Bar Unit 2 may replace steam generators (i.e., have a first refueling outage without replacing steam generators and may have a first refueling outage following steam generator replacement), please discuss your plans to modify this requirement to ensure both conditions are addressed (e.g., | : 3. On page B 3.4-73, the applicable safety analyses for operational leakage is provided. In this discussion, you indicate that the pre-accident primary-to-secondary leakage for a main steam line break is 1 gallon per minute from one steam generator. The standard technical specification wording indicates that the leakage may increase to this value during the accident. Please confirm that your accident analysis assumes that the leakage prior to a main steam line break is 1 gallon per minute (in which case the actual rate of leakage during the accident would be greater than 1 gallon per minute due to the higher differential pressure during the accident). | ||
: 2. Since your proposed technical specifications were prepared, the NRC staff has approved Technical Specification Task Force Traveler 510 (TSTF-510), Revision 2, | : 4. On page B 3.4-73, the applicable safety analyses for operational leakage is provided. | ||
: 3. On page B 3.4-73, the applicable safety analyses for operational leakage is provided. In this discussion, you indicate that the pre-accident primary-to-secondary leakage for a main steam line break is 1 gallon per minute from one steam generator. The standard technical specification wording indicates that the leakage may increase to this value during the accident. Please confirm that your accident analysis assumes that the leakage prior to a main steam line break is 1 gallon per minute (in which case the actual rate of leakage during the accident would be greater than 1 gallon per minute due to the higher differential pressure during the accident). | There are two paragraphs from the standard technical specifications that are not included in this section for Watts Bar Unit 2. These paragraphs address other accidents that involve secondary steam release to the atmosphere and the assumptions for a steam generator tube rupture accident. Please discuss why these paragraphs were not included in your Bases. | ||
: 4. On page B 3.4-73, the applicable safety analyses for operational leakage is provided. There are two paragraphs from the standard technical specifications that are not included in this section for Watts Bar Unit 2. These paragraphs address other accidents that involve secondary steam release to the atmosphere and the assumptions for a steam generator tube rupture accident. Please discuss why these paragraphs were not included in your Bases. | : 5. On page B 3.4-97, the applicable safety analyses for steam generator tube integrity is provided. Please clarify the following sentence: In these analyses, the steam discharge to the atmosphere is based on the total primary to secondary LEAKAGE from 150 gallons per day (gpd) per steam generator and 1 gallon per minute (gpm) in the faulted steam generator. In addition, the standard technical specifications make it clear that the leakage may increase as a result of accident induced conditions to a specific value. This thought is not captured in your proposal. Please clarify why this was not included in your Bases.}} | ||
: 5. On page B 3.4-97, the applicable safety analyses for steam generator tube integrity is provided. Please clarify the following sentence: | |||
Latest revision as of 00:13, 6 December 2019
| ML12030A013 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 01/24/2012 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Division of Operating Reactor Licensing |
| References | |
| Download: ML12030A013 (4) | |
Text
WBN2Public Resource From: Poole, Justin Sent: Tuesday, January 24, 2012 8:14 AM To: Arent, Gordon Cc: Bryan, Robert H Jr; WBN2HearingFile Resource
Subject:
Draft Questions on Technical Specifications Attachments: Watts Bar 2 Technical Specifications RAI.docx
- Gordon, In reviewing TVAs proposed TS for WBN 2, the staff has come up with the attached questions. Please review to ensure that the RAI questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. If further clarification is needed, and you would like to discuss the questions in a conference call, let us know. Please also let me know how much time Tennessee Valley Authority (TVA) needs to respond to the RAI questions.
This email does not convey a formal NRC staff position, and it does not formally request for additional information.
Justin C. Poole Sr. Project Manager NRR/DORL/LPWB U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov 1
Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 640 Mail Envelope Properties (19D990B45D535548840D1118C451C74DC8B74C363D)
Subject:
Draft Questions on Technical Specifications Sent Date: 1/24/2012 8:14:06 AM Received Date: 1/24/2012 8:14:09 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:
"Bryan, Robert H Jr" <rhbryan@tva.gov>
Tracking Status: None "WBN2HearingFile Resource" <WBN2HearingFile.Resource@nrc.gov>
Tracking Status: None "Arent, Gordon" <garent@tva.gov>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 833 1/24/2012 8:14:09 AM Watts Bar 2 Technical Specifications RAI.docx 28154 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
In reviewing the following sections of the proposed Watts Bar Unit 2 Technical Specifications (Development Revision F), the staff has determined that additional information is needed to complete its review.
1.1, Definitions - LEAKAGE 3.4.13, RCS [Reactor Coolant System] Operational LEAKAGE 3.4.17, Steam Generator (SG) Tube Integrity 5.7.2.12, Steam Generator (SG) Program 5.9.9, Steam Generator Tube Inspection Report Please provide a response to the following questions/comments:
- 1. Section 5.7.2.12.d.1 indicates that 100% of the tubing will be inspected in the first refueling outage. Since Watts Bar Unit 2 may replace steam generators (i.e., have a first refueling outage without replacing steam generators and may have a first refueling outage following steam generator replacement), please discuss your plans to modify this requirement to ensure both conditions are addressed (e.g., during the first refueling outage following steam generator installation.).
- 2. Since your proposed technical specifications were prepared, the NRC staff has approved Technical Specification Task Force Traveler 510 (TSTF-510), Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (ML110610350). The staffs review is summarized in a Notice of Availability dated October 19, 2011 (ML112101604). Since this TSTF Traveler addresses implementation issues associated with the inspections periods and addresses other administrative changes and clarifications which improve the technical specifications, please discuss your plans to incorporate the TSTF-510, Revision 2, changes into your proposed technical specifications.
- 3. On page B 3.4-73, the applicable safety analyses for operational leakage is provided. In this discussion, you indicate that the pre-accident primary-to-secondary leakage for a main steam line break is 1 gallon per minute from one steam generator. The standard technical specification wording indicates that the leakage may increase to this value during the accident. Please confirm that your accident analysis assumes that the leakage prior to a main steam line break is 1 gallon per minute (in which case the actual rate of leakage during the accident would be greater than 1 gallon per minute due to the higher differential pressure during the accident).
- 4. On page B 3.4-73, the applicable safety analyses for operational leakage is provided.
There are two paragraphs from the standard technical specifications that are not included in this section for Watts Bar Unit 2. These paragraphs address other accidents that involve secondary steam release to the atmosphere and the assumptions for a steam generator tube rupture accident. Please discuss why these paragraphs were not included in your Bases.
- 5. On page B 3.4-97, the applicable safety analyses for steam generator tube integrity is provided. Please clarify the following sentence: In these analyses, the steam discharge to the atmosphere is based on the total primary to secondary LEAKAGE from 150 gallons per day (gpd) per steam generator and 1 gallon per minute (gpm) in the faulted steam generator. In addition, the standard technical specifications make it clear that the leakage may increase as a result of accident induced conditions to a specific value. This thought is not captured in your proposal. Please clarify why this was not included in your Bases.