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Category:Letter
MONTHYEARIR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 2024-08-05
[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 ML22145A4152022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 18, 2013 Mr. James E. Lynch Site Vice President Northern States Power Company -Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch,'MN 55089-9642 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO REACTOR VESSEL INTERNALS PROGRAM SUBMITTAL FOR FULFILLMENT OF LICENSE RENEWAL COMMITMENT 25 (TAC NOS. MF0052 AND MF0053)
Dear Mr. Lynch:
By letter dated October 1, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12276A041), as supplemented by letters dated March 7, 2013, March 22, 2013, and June 24,2013 (ADAMS Accession Nos. ML13067A284, ML13084A378, and ML13175A333, respectively), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted an aging management program (AMP) for the reactor vessel internals at Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. Materials Reliability Program-227-A report, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," and its supporting reports were used as technical bases for developing the PINGP AMP. The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information reques.ted is addressed in the enclosureto this letter. On August 27,2013, a draft version of this request for additional information (RAI) was discussed between the licensee and the NRC staff to clarify the request. Following the teleconference, it was agreed that you would provide a response to this request within 30 days of the date of this letter. The NRC staff acknowledged that the licensee may not be able to respond to RAI 2-1 until that issue-is resolved on an industry-wide basis. Therefore, the schedule for the licensee's response to RAJ 2-1 will be determined at a later date. The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
J. Lynch -2 If circumstances result in the need to revise the requested response date, please contact me at (301)415-4037.
Sincerely.
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION ) PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated October 1, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12276A041), as supplemented by letters dated March 7,2013, March 22,2013, and June 24,2013 (ADAMS Accession Nos. ML13067A284, ML13084A378, and ML13175A333, respectively), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted an aging management program (AMP) for the reactor vessel internals (RVI) at Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. MRP-227-A report, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," and its supporting reports were used as the technical bases for developing the PINGP AMP. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed this report and issued a final safety evaluation (SE) on December 16, 2011. Based on the review of PINGP's AMP conducted thus far,the staff has developed a second round of requests for additional information (RAI), as addressed below. The NRC staff may, however, issue additional RAls based on the resolution of Action Items 1 and 2 addressed in the staff's SE for the MRP-227 -A report. RAI2-1: As discussed in References 1 and 2 below, provide the following information related to verification of the applicability of MRP-227-A to PINGP, Units 1 and 2: Do the PINGP, Units 1 and 2, RVI have non-weld or bolting austenitic stainless steel components with 20 percent cold work or greater and, if so, do the affected components have operating stresses greater than 30 ksi? If so, perform a plant-specific evaluation to determine the aging management requirements for the affected components. Have PINGP, Units 1 and 2, ever utilized atypical fuel design or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representative for that plant, including power changes/uprates?
If so, describe how the differences were reconciled with the assumptions of MRP-227 -A, or provide a specific aging management program for the affected components, as appropriate.
References Meeting Summary Electric Power Research Institute (EPRI) -Westinghouse January 22-23, 2013, dated February 21, 2013 (ADAMS Accession No. ML13042A048) February 25,2013 Summary of Teleconference with EPRI and Westinghouse Electric Company, dated March 15, 2013 (ADAMS Accession No. ML13067A262)
Enclosure
-2 RAI.2-2: In the licensee's March 22, 2013, submittal it is not evident which of the RVI components in the PINGP design are specifically defined in the current licensing basis (CLB) as ASME Section XI, Examination Category B-N-3 removable core support structure components, or how these components relate to the four inspection categories that are defined for Westinghouse-designed . RVI components in Technical Report (TR) No. MRP-227-A (Le., as MRP-defined "Primary Category," "Expansion Category," "Existing Program," or "No Additional Measures" com ponents).
Part (a) -Identify all RVI components in the PINGP plant design that are defined in the CLB as ASME Section XI, Examination Category B-N-3 core support structure components.
For each of these components, identify which of the four inspection categories in MRP-227 -A is applicable to the component.
Part (b) -If a component identified in the reply to Part (a) is defined as either a "Primary Category" or "Expansion Category" component, identify any differences between the inspections that would be performed on the components under MRP-227 -A versus the plant's ASME Section XI inservice inspection (lSI) program. For each of these components identified in Part (b), clarify how the differences in inspection bases for these components will be reconciled consistent with the CLB for the facility.
RAI2-3: By letter dated March 7,2013, the licensee provided a response to Action Item 3 that was addressed in the NRC staff's SE for the MRP-227-A.
In its response to Action Item 3, the licensee provided its basis for why the replacement control rod guide tube (CRGT) assembly support pins (i.e., split pins) at PINGP (which are made from Type 316 cold-worked austenitic stainless steel) would not need to be inspected under the augmented inspection basis in TR MRP-227-A.
However, Updated Safety Analysis Report (USAR) Section 3.6.2.2 establishes the following bases with respect to the design of the CRGT assemblies:
The guide tube assemblies, shown on Figure 3.6-3, sheath and guide the control rod drive shafts and control rods and provide no other mechanical functions.
They are fastened to the upper support plate and are guided by pins in the upper core plate for proper orientation and support. Additional guidance for the control rod drive shafts is provided by the upper guide tube which is bolted to the upper 'support plate and guide tube. Based on this USAR information, it is not evident why the replacement CRGT split pins not need to be inspected in accordance with the ASME Section XI, Table Examination Category S-N-3 lSI requirements, as invoked by the lSI requirements *10 CFR 50.55a. Part (a) -Clarify whether the CRGT split pins are defined as ASME Section XI, Examination Category B-N-3 components for the PINGP CLB. If the CRGT split pins are defined in the CLB as ASME Section XI, Examination Category B-N-3 core support structure components, justify why the CRGT split pins would not need to be inspected as a part of the "Existing Program"
-bases of the PWR Vessel Internals Program or alternatively in accordance with the aging management program (AMP) for the facility that corresponds to GALL AMP XI.Ml, "ASME Section Xllnservice Inspection, Subsections IWB, IWC, and IWD" Program. Part (b) -Justify why the response to Applicant/Licensee Action Item #3 did not specifically address whether the ASME Section XI "Existing Program" bases in the CLBfor the CRGT split pins is sufficient for ensuring adequate aging management of the split pins during the period of extended operation.
Otherwise, amend the submittal to provide a response to the AI LA I that specifically addresses the adequacy of ASME Section XI lSI bases for the CRGT split pins and whether these bases are sufficient to manage aging in the components during the period of extended operation.
RAI2-4: The NRC staff requests that the licensee address the following issues: Pages 43 -45 of Attachment 1 of the licensee's March 22, 2013, submittal includes the "Expansion Category" components.
Clarify whether the "Expansion Link" column for that "Expansion Coniponent" Table should be interpreted as a "Primary Link" column for the table. Page 46 of Attachment 1 of the licensee's March 22, 2013, submittal includes the "Existing Program" components.
Clarify whether the "Expansion Link" col.umn for that "Existing Program Component" Table should be interpreted as an "Existing Program Reference" column for the table. .
J. E. Lynch -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, IRA! Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 .
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
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