Letter Sequence RAI |
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TAC:MD0209, Steam Generator Tube Integrity (Approved, Closed) TAC:MD0210, Steam Generator Tube Integrity (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24185A0912024-07-0101 July 2024 Acceptance of LAR to Revise TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A1502024-02-15015 February 2024 Verbal Authorization for Alternative Relief Request-09 ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23207A1962023-07-26026 July 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions ML23075A2802023-03-16016 March 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda ML23065A0592023-02-27027 February 2023 NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) ML22167A0452022-06-16016 June 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277 ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22045A4972022-02-14014 February 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21302A1252021-10-29029 October 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0152021-09-0202 September 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21133A2502021-05-13013 May 2021 NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20253A2782020-09-0909 September 2020 E-Mail Submitting Proposed New License Condition ML20254A1162020-09-0909 September 2020 Draft License Transmittal E-Mail ML20223A0632020-08-10010 August 2020 Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20163A4282020-06-10010 June 2020 Email from MPCA Comment Letter - Prairie Island ISFSI ML20154K7632020-06-0202 June 2020 NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20135G8212020-05-14014 May 2020 NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20112F4582020-04-21021 April 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection ML20083F4202020-03-20020 March 2020 NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20052C7582020-02-21021 February 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05 ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML20022A1762020-01-22022 January 2020 NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML20021A1832020-01-21021 January 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2 ML19316A0172019-11-0101 November 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request ML19253B9642019-09-10010 September 2019 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3 ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19193A0142019-07-0909 July 2019 NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals) ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML19057A4212019-02-26026 February 2019 NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request ML19008A3562019-01-0707 January 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69 ML18351A0142018-12-14014 December 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment ML18347A3282018-12-12012 December 2018 E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018) ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request 2024-07-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23096A3082023-04-0707 April 2023 Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 ML23053A1432023-02-22022 February 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment IR 05000282/20224022022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21147A5232021-06-0303 June 2021 Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21131A0752021-05-10010 May 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004 ML21099A0972021-04-0909 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012 ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant ML21033A6112021-02-0101 February 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010 ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 ML20133K0692020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20077K6242020-04-13013 April 2020 License Amendment Request - Request for Additional Information ML20052F4102020-02-21021 February 2020 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18264A1912018-09-19019 September 2018 NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg) ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18169A4202018-06-25025 June 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18025C0152018-01-24024 January 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop) ML17277B3332017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) ML17235A9982017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change ML17221A3892017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17219A0762017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17038A5132017-02-0707 February 2017 NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01 ML17018A4272017-01-18018 January 2017 NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action ML16326A3532016-11-18018 November 2016 NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) ML16189A2052016-07-0707 July 2016 Notification of NRC Inspection and Request for Information ML16113A1612016-04-21021 April 2016 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2 2024-07-15
[Table view] |
Text
From: Mahesh ChawlaTo:Dale.Vincent@nmcco.comDate: 08/29/2006 1:08:30 PM
Subject:
Request for Additional Information - SG Tube Integrity - TSTF 449 -MD0209/MD0210By letter dated February 16, 2006, (ML060480440), Nuclear Management Company (thelicensee) submitted a license amendment request regarding Prairie Island Nuclear Generating Plant Units 1 and 2 steam generator (SG) tube integrity technical specifications (TS).The proposed amendment would revise the SG tube integrity TSs to be consistent with theNuclear Regulatory Commission approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, "Steam Generator Tube Integrity,"Revision 4 (ML051090200). Additional information was provided by the licensee in letter dated July 21, 2006 (ADAMS Accession No. ML062370052).The staff has reviewed the information the licensee provided and determined that additionalinformation is required in order to complete the evaluation. The additional information being requested is enclosed. Let me know if you need a teleconference to discuss the questionslisted below:1. In your proposed Structural Integrity Performance Criteria (SIPC) in Technical Specification(TS) 5.5.8.b.1, you stated the following: "For Unit 2, when tubes are left in service withpredominantly axially oriented stress corrosion cracking at the tube support plate (TSP)elevations, the probability of burst (POB) under main steam line break conditions shall bemaintained below 1E-02 in accordance with the requirements of NRC Generic Letter (GL)95-05." As currently proposed, once tubes are left in service with predominantly axially oriented stress corrosion cracking at the tube support plate elevations, the probability of burst for allindications (even those that are not axially oriented stress corrosion cracking at TSP locations) is limited to 1x10-2. In addition, since NRC GL 95-05 does not contain any "requirements," thelast portion of this statement is not accurate. If it was not your intent to have the 1x10-2 criteria apply to all forms of degradation, please discuss your plans to modify your submittal.Please discuss your plans to address the above. The proposed TS may be modified by usingsomething similar to the following:For Unit 2, when alternate repair criteria discussed in Specification 5.5.8.c.2(c) are applied toaxially oriented outside diameter stress corrosion cracking indications at tube support plate locations, the probability that one or more of these indications in a SG will burst underpostulated main steam line break conditions shall be less than 1x10-2.Please note that your Bases may also need to be revised to clarify this issue.
2.A safety factor of 1.4 against burst applied to the design basis accident primary-to-secondarypressure differentials was indicated in TS Section 5.5.8.b.1. GL 95-05 indicated that there is apossibility that a tube may have a burst pressure less than 1.4 times the steam line breakpressure differential (given the uncertainties associated with the various correlations), therefore, the GL 95-05 alternate repair criteria (ARC) imposed a limit on the POB of 1x10-2. As currently proposed, the flaws to which the voltage-based ARC is applied must maintain a safety factor of 1.4 against burst during design basis accidents. Since this is inconsistent with the staff's original approval (as evidenced by the probability of burst criteria), please verify that this wasyour intent. If this was not your intent, please discuss your plans to modify your submittal to address this issue. Discuss your plans to clarify your proposal, for example: "This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary to secondary pressure differential and, except for flaws addressed through application of the alternate repair criteria discussed in Specification 5.5.8.c.2(c), a safety factor of 1.4against burst applied to the design basis accident primary to secondary pressure differentials."
- 3. Regarding TS 5.5.8.b.2, you reference the "voltage-based repair criteria." Since thisreference isn't specific, it could be misinterpreted to apply to any flaws to which a voltage-based sizing method is applied. As a result, discuss your plans to clarify your proposed TS to indicate that the "voltage-based repair criteria" that you are referring to is the one in TS 5.5.8.c.2(c).4. As currently written, it is not clear whether all of the criteria listed under TS 5.5.8.c.2 must bemet in order to require plugging or repair. In addition, the criteria under TS 5.5.8.c.2 not only discuss the criteria for plugging and repair, but also criteria for leaving flaws in service. As a result, please discuss your plans to modify your submittal to address this issue. For example:
"Unit 2 steam generator tubes found by inservice inspection to contain flaws shall be dispositioned as follows:"5. It appears that TS 5.5.8.c.2(a)(1) and TS 5.5.8.c.2(a)(2) are intended to address the repaircriteria for the non-sleeved and sleeved region of the tube, respectively. In your current proposal (and TSTF-449), a "tube" is considered to include the tube wall and any repairs to it.
As a result, it would appear that there are two different set of repair limits for the sleeves (since TS 5.5.8.c.2(a)(1) and TS 5.5.8.c.2(a)(2) apply to the sleeve). Please discuss your plans toclarify that TS 5.5.8.c.2(a)(1) addresses the non-sleeved region of the tube and TS5.5.8.c.2(a)(2) addresses the sleeved region of the tube.6. In proposed TS 5.5.8.c.2(a)(2), you indicated that the repair criteria for the original tube wallin the sleeve to tube joint is 25-percent of the nominal sleeve wall thickness. This does not appear to be consistent with your current technical specifications (and it probably is not consistent with the design and licensing basis for the sleeves). The staff believes that youintended to indicate that the repair criteria for the sleeve is 25-percent of the sleeve wallthickness and that the repair criteria for the parent tube at the sleeve-to-tube joint is to plug ondetection. Please discuss your plans to modify your proposal to address this issue.In addition, as currently written, proposed TS 5.5.8.c.2(a)(2) would permit tubes to be eitherplugged or repaired in the event that flaws exceeded the repair criteria. Please discuss your plans to indicate that flaws that exceed these repair limits must be plugged.7. In proposed TS 5.5.8.c.2(b), it would appear that the following phrase is not needed since itis also contained in proposed TS 5.5.8.c.2(b)(1) and (2): "Flaws may be left in service when they are located below F* or EF* [region] defined below:." Please discuss your plans to remove this phrase.8. In several instances, the term "defect" is used in your proposed TS (e.g., 5.5.8.c.2(b)(1), proposed TS 5.5.8.c.2(b)(2), and proposed TS 5.6.7.a.10). Since a "defect" is not defined inyour proposed TS, please discuss your plans to replace this term with "flaw" which is the term used in TSTF-449. In addition, the term "degradation" is used in your proposed TS (e.g.,
5.5.8.c.2(c)(1) and 5.5.8.c.2(c)(2)). Since "degradation" is not defined in your proposed TS,please discuss your plans to replace this term with "flaw" which is the term used in TSTF-449.9. Please discuss your plans to indicate in TS 5.5.8.d that: "In tubes repaired by sleeving, theportion of the original tube wall between the sleeve's joints is not an area requiring re-inspection."10. In proposed TS 5.5.8.d.3(a), you indicate that the region of the tube below the F* and EF*regions may be excluded from the inspection requirements. In addition, in your response to question 4c in your July 21, 2006 letter (MLXXXX), you indicate that full depth tubesheet sleeves are installed at the lower end of the parent tube (presumably this is near the tube-to-tubesheet weld). Since this latter region is below the F* and EF* region, it would appear that a tube in which a full depth tubesheet sleeve is installed may not require an inspection nearthe lower end of the sleeve (depending on exactly where the sleeve is installed with respect to the F* and EF* region). As a result, please discuss your plans to modify your proposal to ensure that full depth tubesheet sleeves require an inspection.
- 11. In proposed TS 5.5.8.d.3(a), you reference a "refueling outage inspection." Under theproposed TS, inspections need not be performed during a refueling outage. They only need to be performed at intervals not to exceed 24 effective full power months or one operating interval between refueling outages (whichever is less). As a result, if you were to elect to perform inspections at times other than refueling outages, the F* and EF* region may not be inspected for multiple cycles. Since this is inconsistent with your current requirements (and thedesign/licensing basis), discuss your plans to modify your submittal to indicate that the "F* and EF* tubes" will be inspected in the F* and EF* regions every 24 effective full power months orone refueling outage (whichever is less). A similar comment applies to proposed TS 5.5.8.d.3(c) which references inspections during refueling outages.12. In proposed TS 5.5.8.d.3(b) and (c), you refer to the repair criteria discussed in proposedTS 5.5.8.c.2(c) using different terminology. This can cause confusion on what is being referred to (since neither of these sections match the "title" in 5.5.8.c.2(c). As a result, please discuss your plans to modify these two sections to simply reference the "alternate repair criteria discussed in TS 5.5.8.c.2(c)." A similar comment applies to proposed TS 5.6.7.b.13. In proposed TS 5.5.8.f.2, you indicate that hardroll expanding portions of tubes in thetubesheet is an acceptable tube repair method. Since a tube may includes a sleeve, pleasediscuss your plans to clarify that this repair criteria is only applicable to tubes that do not have sleeves installed in the tubesheet region. For example, "Hardroll expanding non-sleeved portions of tubes in the tubesheet in order to apply the F* and EF* criteria."14. Regarding proposed TS 5.6.7.b.4, you indicated that removing this reporting requirementwould constitute a change in your licensing basis (refer to your response to question 2 in the July 21, 2006 letter). The staff notes that by incorporating the 1x10-2 probability of burst criteriainto TS 5.5.8.b.1, you will not be able to operate under the condition where the burst probabilityexceeds 10-2. As a result, providing a safety assessment is not needed. As a result, the reporting requirement is not needed. The staff also notes that you are required per 10 CFR 50.73 to report if the performance criteria are not maintained. As a result of the above, discuss your plans to remove the subject reporting requirement.15. In your July 21, 2006 response to question 3, you stated (see item 2) that the F* and EF*criteria could be applied to the cold-leg side of the tubesheet. At the time the F* and EF*
criteria were approved, your technical specification only addressed the hot-leg portion of the tubesheet (i.e., no inspections were required by the technical specifications in the cold-leg). At the time of these F* and EF* proposals, no modifications were made to the technical specifications to require cold-leg inspections. As a result, the staff reviewed your proposal to incorporate technical specification inspection and repair criteria for the hot-leg. As a result of the above, discuss your plans to submit for review and approval, the structural and leakage integrity analysis for application of the F* and EF* criteria to the cold-leg or alternatively discuss your plans to clarify that the F* and EF* criteria apply to the hot-leg.16. In the Limiting Condition for Operation section of B 3.4.19, you indicate that the F* and EF*distances are not considered part of the tube. Since these distances are no longer defined in your proposed TS, please discuss your plans to modify this phrase to indicate that the region of tube below the F* and EF* regions is not considered part of the tube. In addition, discuss yourplans to indicate that the parent tube (original tube wall) between sleeve joints is also notconsidered part of the tube.17. Observation - In the second part of your July 21, 2006 response to question 8, you implythat the reporting guidance in Section 6b of Attachment 1 of GL 95-05 is not performance based. The staff disagrees with this assessment. The staff believes that this reporting guidance is, in fact, performance based. That is, the purpose of the report is to monitor the performance of the empirical approach discussed in GL 95-05.
CC:Kenneth Karwoski; Martin Murphy; Yamir Diaz-Cast illoMail Envelope Properties(44F4748E.3B3 : 2 : 35476)
Subject:
Request for Additional Information - SG Tube Integrity - TSTF 449 -MD0209/MD0210 Creation Date 08/29/2006 1:08:30 PMFrom: Mahesh ChawlaCreated By:MLC@nrc.govRecipientsActionDate & Timenmcco.comTransferred08/29/2006 1:08:54 PM Dale.Vincent (Dale.Vincent@nmcco.com)nrc.gov OWGWPO03.HQGWDO01Delivered08/29/2006 1:08:30
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