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Category:Note to File incl Telcon Record
MONTHYEARML20213B2212020-11-20020 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Constellation and Exelon'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Nine Mile Point Unit ML18022A0692018-01-30030 January 2018 Review of Updated Final Safety Analysis Report, Revision 25 ML17108A4562017-05-26026 May 2017 Clarification to License Renewal Safety Evaluation for Nine Mile Point Nuclear Station, Units 1 and 2 (CAC Nos. MC3272 and MC3273) ML0610900642006-04-18018 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC No'S. MC3272 and MC3273) ML0609405772006-04-0404 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0605906442006-02-24024 February 2006 2/24/2006 - Docketing of Documents Sent to the NRC by Linda Bond-Clark Related to Nine Mile Point Nuclear Station ML0502404242005-01-13013 January 2005 Request for Additional Information - Nine Mile Point Nuclear Station, Units 1 and 2, Fire Protection Open Items ML0502103762005-01-13013 January 2005 Request for Additional Information on Open Items for Balance of Plant Section ML18018B1861986-04-10010 April 1986 Letter Referring to Generic Letter 83-28 Concerning Required Actions Based on Generic Implications of Salem ATWS Events and Requesting That GE Provide a Response by April 15, 1986 ML17037B9421976-12-13013 December 1976 Letter Confirming September 7, 1976 and Early October Telephone Conversations Concerning Features in the Reheater Bay Area and a December 2, 1976 Call to Inform of More Recent Observations Which May Suggest Possible Post ... ML17037B9041976-12-13013 December 1976 Letter Confirming Telephone Conversations Relating to Certain Geologic Features and a December 2, 1976 Call to Inform of More Recent Observations Which May Suggest Possible Post-Glacial Vertical Displacement of Sediments .. ML17037C1891975-09-30030 September 1975 Letter Regarding a Telephone Conversation on August 15, 1975 Requesting Informing Concerning Potential Operational Limitations of the Onsite Standby Emergency Diesel Engines ML17037B5791975-09-0303 September 1975 Letter Confirming a 09/02/1975 Telephone Discussion Relative to the Meeting to Be Held 09/04/1975 ML17037C2061974-10-0404 October 1974 Letter Acknowledging Receipt of the Analysis on ATWS with Letter of September 25, 1974 and Requesting Submittal of Additional Analysis, an Explanation for the Delay, and a Schedule of the Detailed Plan within Two Weeks .. ML17037C2511973-12-18018 December 1973 Letter Regarding Letters Dated November 28 and December 3, 1973 Reporting Failures of Eleven and Fifteen Control Rods to Insert to Position Oo Following a Reactor Scram and Confirming That a More Complete Report Will Be ... ML17037B7681965-04-21021 April 1965 Letter Requesting More Information Concerning the Recent AEC License Awarded to Niagara Mohawk ML17037C1561964-02-21021 February 1964 Letter Regarding a Geological Report and a Request for Examination and Submittal of an Independent Opinion 2020-11-20
[Table view] Category:Verbal Comm
MONTHYEARML20213B2212020-11-20020 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Constellation and Exelon'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Nine Mile Point Unit ML18022A0692018-01-30030 January 2018 Review of Updated Final Safety Analysis Report, Revision 25 ML17108A4562017-05-26026 May 2017 Clarification to License Renewal Safety Evaluation for Nine Mile Point Nuclear Station, Units 1 and 2 (CAC Nos. MC3272 and MC3273) ML0610900642006-04-18018 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC No'S. MC3272 and MC3273) ML0609405772006-04-0404 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0605906442006-02-24024 February 2006 2/24/2006 - Docketing of Documents Sent to the NRC by Linda Bond-Clark Related to Nine Mile Point Nuclear Station ML0502404242005-01-13013 January 2005 Request for Additional Information - Nine Mile Point Nuclear Station, Units 1 and 2, Fire Protection Open Items ML0502103762005-01-13013 January 2005 Request for Additional Information on Open Items for Balance of Plant Section ML18018B1861986-04-10010 April 1986 Letter Referring to Generic Letter 83-28 Concerning Required Actions Based on Generic Implications of Salem ATWS Events and Requesting That GE Provide a Response by April 15, 1986 ML17037B9421976-12-13013 December 1976 Letter Confirming September 7, 1976 and Early October Telephone Conversations Concerning Features in the Reheater Bay Area and a December 2, 1976 Call to Inform of More Recent Observations Which May Suggest Possible Post ... ML17037B9041976-12-13013 December 1976 Letter Confirming Telephone Conversations Relating to Certain Geologic Features and a December 2, 1976 Call to Inform of More Recent Observations Which May Suggest Possible Post-Glacial Vertical Displacement of Sediments .. ML17037C1891975-09-30030 September 1975 Letter Regarding a Telephone Conversation on August 15, 1975 Requesting Informing Concerning Potential Operational Limitations of the Onsite Standby Emergency Diesel Engines ML17037B5791975-09-0303 September 1975 Letter Confirming a 09/02/1975 Telephone Discussion Relative to the Meeting to Be Held 09/04/1975 ML17037C2061974-10-0404 October 1974 Letter Acknowledging Receipt of the Analysis on ATWS with Letter of September 25, 1974 and Requesting Submittal of Additional Analysis, an Explanation for the Delay, and a Schedule of the Detailed Plan within Two Weeks .. ML17037C2511973-12-18018 December 1973 Letter Regarding Letters Dated November 28 and December 3, 1973 Reporting Failures of Eleven and Fifteen Control Rods to Insert to Position Oo Following a Reactor Scram and Confirming That a More Complete Report Will Be ... ML17037B7681965-04-21021 April 1965 Letter Requesting More Information Concerning the Recent AEC License Awarded to Niagara Mohawk ML17037C1561964-02-21021 February 1964 Letter Regarding a Geological Report and a Request for Examination and Submittal of an Independent Opinion 2020-11-20
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
[Table view] |
Text
NINE MILE POINT NUCLEAR STATION UNITS 1 AND 2 FIRE PROTECTION OPEN ITEMS (Open Item 2.3.3.A.9-7)
(Open Item 2.3.3.B.13-1)
(Open Item 2.3.3.B.13-23)
(Open Item 2.3.3.B.13-25)
(Open Item 2.3.3.B.13-26)
RAI 2.3.3.A.9-7 (Open Item 2.3.3.A.9-7)
The scoping and screening LRA table associated with the fire detection and protection system includes the following component types as being subject to an AMR: filters/strainers, flow elements, and orifices. However, the intended function assigned to these components is NSR Functional Support. LRA Table 2.0-1, Intended Functions Abbreviations & Definitions identifies intended functions applicable to these component types that are not identified in the LRA table associated with the fire detection and protection system. Aging management to ensure that the component level intended functions can be performed is necessary to ensure that the system level intended functions can be maintained. The intended functions include filtration and flow restriction.
The staff requested that the applicant describe how the intended functions for these components were assigned and evaluated.
Applicants Response and Staffs Evaluation In its response dated December 17, 2004, the applicant stated that because a component performs a particular function, such as filtration for a filter or flow restriction for a flow orifice, it does not mean that the function is an intended function for license renewal. A component function would only be considered an intended function (IF) if failure of that component would cause the failure of a system IF. Failure of the filtration or flow restriction functions for the above mentioned components would not prevent the NMP Unit 1 fire detection and protection system from performing its IF. Therefore, the only IF credited for these components is NSR Functional Support as identified in LRA Table 2.3.3.A.9-1.
Based on its review, the staff is not able to find the applicant's response to RAI 2.3.3.A.9-7 acceptable because it does not adequately explain what intended functions, NSR Functional Support represent and how it is applied to all the component types in the fire detection and protection system including piping, valves, strainers, pumps, and orifices. Therefore, the staff's concern described in RAI 2.3.3.A.9-7 remains an open issue. (Open Item 2.3.3.A.9-7)
RAI 2.3.3.B.13-1 (Open Item 2.3.3.B.13-1)
The GALL Report section for the fire water system, describes the requirements for aging management of the fire protection water system. It requires that an AMP be established to evaluate the aging effects of corrosion, MIC, biofouling of carbon steel and cast iron components in fire protection systems exposed to water.
The LRA discusses requirements for the fire detection and protection program but does not
mention trash racks and traveling screens for the fire pump suction water supply. Trash racks and traveling screens are mentioned in the LRA section for the service water system, but are not listed in the associated LRA table for that system which contains the list of components that require aging management. They are not mentioned in the LRA.
The NMP2 UFSAR states that the trash racks and traveling screens are located upstream of the fire pump suctions to remove any major debris from the water. The staff asked the applicant to explain the apparent exclusion of the trash racks and traveling screens that are located upstream of the fire pump suctions from the scope of license renewal and from being subject to an AMR.
Applicants Response and Staffs Evaluation In its response dated December 17, 2004, the applicant stated that although the trash racks and traveling screens are addressed in NMP Unit 2 UFSAR Section 9.2.5 as preventing large debris from reaching the service water pumps, and, therefore, the fire pumps as well, the collection of debris on the trash racks and/or the traveling screens such that blockage could occur is not a license renewal intended function and are not credited under 10 CFR 50.48. If such a blockage were to occur, bypass valves automatically open to bypass the blockage and continue to supply water to the pump suctions.
Additionally, the fire pump suction headers have their own strainers in-line such that the loss of the trash racks or traveling screens would not challenge the operation of these pumps until repair/replacement of the damaged component could be performed.
The applicant further stated that the supports of the trash racks are within the scope of license renewal and subject to an AMR.
Based on its review, the staff is not able to find the applicant's response to RAI 2.3.3.B.13-1 acceptable because although it explains that the trash racks and traveling screens are addressed in the NMP Unit 2 UFSAR, they perform no intended function. The staff finds this contrary to the NMP Unit 2 UFSAR which includes the original NMP Unit 2 fire protection SER as CLB. Therefore, the staff's concern described in RAI 2.3.3.B.13-1 remains an open item.
(Open Item 2.3.3.B.13-1)
RAI 2.3.3.B.13-23 (Open Item 2.3.3.B.13-23)
A license renewal drawing for the fire detection and protection system depicts a portion of the dry pipe sprinkler system for the reactor building railroad access bay as being excluded from the scope of license renewal and from being subject to an AMR. The applicant was asked to explain the apparent exclusion of this portion of the fire detection and protection system from the from requiring an AMR in accordance with 10 CFR 54.21(a).
Applicants Response and Staffs Evaluation In its response dated December 17, 2004, the applicant stated that the identified license renewal drawing, LR-43C-0 is correct and properly shows the components in question excluded from the scope of license renewal and from being subject to an AMR. The dry-pipe sprinkler system in the railroad access bay is not credited to meet the requirements of 10 CFR 50.48, and therefore not within the scope of license renewal in accordance with 10 CFR 54.4(a)(3)
because it has no license renewal intended functions. The dry-pipe sprinkler system in question is correctly depicted on its license renewal drawing and is not subject to an AMR.
Based on its review, the staff is not able to find the applicant's response to RAI 2.3.3.B.13-23 acceptable because although it explains that the dry-pipe sprinkler system in question is not credited to meet the requirements of 10 CFR 50.48, the staff finds this contrary to the UFSAR which includes the original NMP Unit 2 fire protection SER as CLB. The NMP Unit 2 UFSAR includes a description of this sprinkler system. Therefore, the staff's concern described in RAI 2.3.3.B.13-23 remains an open issue. (Open Item 2.3.3.B.13-23)
RAI 2.3.3.B.13-25 (Open Item 2.3.3.B.13-25)
The NMP2 UFSAR describes criteria for fire resistance of interior finishes. It is not clear from review of the LRA, that interior finishes are included within the scope of license renewal. The applicant was asked to confirm that interior finishes are within the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a) or to explain their exclusion.
Applicants Response and Staffs Evaluation In its response dated December 17, 2004, the applicant explained that the UFSAR states that noncombustible and fire-resistive building and interior finish materials are used wherever practical throughout the plant, particularly in structures containing safety-related systems and components. The interior finishes, which consist of paint and floor coverings, serve no intended function and are not in scope for license renewal. The materials used to seal structural gaps and joints, that do have an intended function for 10 CFR 50.48, fire protection, can be found in the NMP LRA section for, fire stops and seals.
Based on its review, the staff is not able to find the applicant's response to RAI 2.3.3.B.13-25 acceptable because although it explains that the interior finishes in question are not credited to meet the requirements of 10 CFR 50.48, the staff finds this contrary to the UFSAR which includes the original NMP Unit 2 fire protection SER as CLB. The NMP Unit 2 UFSAR includes a description of the fire resistance of interior finishes. Therefore, the staff's concern described in RAI 2.3.3.B.13-25 remains an open item. (Open Item 2.3.3.B.13-25)
RAI 2.3.3.B.13-26 (Open Item 2.3.3.B.13-26)
The LRA identifies structures that are included within the scope of license renewal. The UFSAR identifies structures that are included in the fire protection licensing basis and thus should be considered within the scope of license renewal. However, the LRA does not include the condensate storage tank structure and the normal switchgear building that are included in UFSAR as structures within the scope of license renewal in accordance with 10 CFR 54.4(a).
Because these structures support fire protection intended functions, the applicant was asked to explain their apparent exclusion from requiring an AMR.
Applicants Response and Staffs Evaluation In its response dated December 17, 2004, the applicant explained that the normal switchgear building and the condensate storage building are located in the protected area and are considered to be non-essential yard structures. Further the applicant explained that these
structures do not meet any of the three criteria of 10 CFR 54.4, nor do they contain safety-related equipment, and do not house equipment required for safe plant shutdown, or radioactive material. Therefore, fire protection equipment in these structures is for asset protection only. Neither of these buildings is credited for 10 CFR 50.48, fire protection.
Based on its review, the staff is not able to find the applicant's response to RAI 2.3.3.B.13-26 acceptable because although it explains that the normal switchgear building and the condensate storage buildings are not credited to meet the requirements of 10 CFR 50.48, the staff finds this contrary to the UFSAR which includes the original NMP Unit 2 fire protection SER as CLB. The NMP Unit 2 UFSAR includes a description of these structures. Therefore, the staff's concern described in RAI 2.3.3.B.13-26 remains an open item.
(Open Item 2.3.3.B.13-26)