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| | number = ML17272A011 | | | number = ML17272A011 |
| | issue date = 10/10/2017 | | | issue date = 10/10/2017 |
| | title = Nine Mile Point Nuclear Station, Unit 2 - Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357) | | | title = Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control |
| | author name = Marshall M L | | | author name = Marshall M |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000410 | | | docket = 05000410 |
| | license number = NPF-069 | | | license number = NPF-069 |
| | contact person = Marhsall M L, NRR/DORL/LPL, 415-2871 | | | contact person = Marhsall M, NRR/DORL/LPL, 415-2871 |
| | case reference number = CAC MF9357 | | | case reference number = CAC MF9357 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 October 10, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 10, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNIT 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357) | | NINE MILE POINT NUCLEAR STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML 17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information. The request for additional information was discussed with your staff on October 3, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2871 or Michael.Marshall@nrc.gov. Docket No. 50-410 | | |
| | By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review. |
| | Enclosed is the NRC staff's request for additional information. The request for additional information was discussed with your staff on October 3, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. |
| | If you have any questions, please contact me at 301-415-2871 or Michael.Marshall@nrc.gov. |
| | Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/ | | Request for Additional Information cc w/ |
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| ==Enclosure:== | | ==Enclosure:== |
| Distribution via Listserv Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML 17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications (TSs) by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel (RPV) water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel. The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed to complete its review of the request. Requests for Additional Information (1) In Table 3.3.5.2-1 (page 2 of 2), "RPV Water Inventory Control Instrumentation,'' of the TS markup, the "Manual Initiation" Function is designated "3.f." In the last sub-bullet on page 5 of the application, it is implied that the "Manual Initiation" Function should be designated as "3.e." Clarify whether the designation for the "Manual Initiation" Function in Table 3.3.5.2-1 of the TS markup is "3.e" or "3.f ." (2) In TS markup, the Limiting Condition for Operation 3.3.5.2, "RPV Water Inventory Control instrumentation," Condition E has two Required Actions. The first Required Action is designated "E.1." The other Required Action, which states, "Restore channel to OPERABLE status," does not have a designation. What is the designation of the second required action? (3) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 2.a is "1 per pump." In the current version of the table in Nine Mile Point, Unit 2, TSs and the second bullet on page 4 of the application, the licensee states that the required channels per function for Function 2.a is "1 per valve." Also, "1 per pump" is an apparent variation from the TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." In the TS markup for TSTF-542, the required channels per function is "1." Clarify whether the required channels per function for Function 2.a in Table 3.3.5.2-1 of the TS markup is "1 per pump," "1 per valve," or "1." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF. Enclosure | | Distribution via Listserv |
| -2-(4) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 1.d is "1." In TS markup for TST-542, the required channels per function is "1 per pump." The required channels per function of "1" is an apparent variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Clarify whether the required channels per function for Function 1.d in Table 3.3.5.2-1 of the TS markup is "1" or "1 per pump." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF. (5) In Table 3.3.6.2 (page 1 of 1 ), "Secondary Containment Isolation Instrumentation," of the TS markup, the third function is "Reactor Building Above the Refuel Floor Exhaust Radiation -High." In the TS markup for TSTF-542, the third function is "Reactor Building Exhaust Radiation -High." The third function in the TS markup appears to be a variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Provide a discussion whether the apparent variation affects the applicability of the TSTF.
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| | REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications (TSs) by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel (RPV) water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel. |
| | The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed to complete its review of the request. |
| | Requests for Additional Information (1) In Table 3.3.5.2-1 (page 2 of 2), "RPV Water Inventory Control Instrumentation,'' of the TS markup, the "Manual Initiation" Function is designated "3.f." In the last sub-bullet on page 5 of the application, it is implied that the "Manual Initiation" Function should be designated as "3.e." Clarify whether the designation for the "Manual Initiation" Function in Table 3.3.5.2-1 of the TS markup is "3.e" or "3.f ." |
| | (2) In TS markup, the Limiting Condition for Operation 3.3.5.2, "RPV Water Inventory Control instrumentation," Condition E has two Required Actions. The first Required Action is designated "E.1." The other Required Action, which states, "Restore channel to OPERABLE status," does not have a designation. What is the designation of the second required action? |
| | (3) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 2.a is "1 per pump." In the current version of the table in Nine Mile Point, Unit 2, TSs and the second bullet on page 4 of the application, the licensee states that the required channels per function for Function 2.a is "1 per valve." Also, "1 per pump" is an apparent variation from the TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." In the TS markup for TSTF-542, the required channels per function is "1." Clarify whether the required channels per function for Function 2.a in Table 3.3.5.2-1 of the TS markup is "1 per pump," "1 per valve," or "1." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF. |
| | Enclosure |
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| | (4) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 1.d is "1." In TS markup for TST-542, the required channels per function is "1 per pump." The required channels per function of "1" is an apparent variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Clarify whether the required channels per function for Function 1.d in Table 3.3.5.2-1 of the TS markup is "1" or "1 per pump." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF. |
| | (5) In Table 3.3.6.2 (page 1 of 1), "Secondary Containment Isolation Instrumentation," of the TS markup, the third function is "Reactor Building Above the Refuel Floor Exhaust Radiation - |
| | High." In the TS markup for TSTF-542, the third function is "Reactor Building Exhaust Radiation - High." The third function in the TS markup appears to be a variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Provide a discussion whether the apparent variation affects the applicability of the TSTF. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNIT 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357) DATED OCTOBER 10, 2017 DISTRIBUTION: Public RidsNrrDorlLpl1 RidsRgn1 MailCenter RidsACRS _MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDssStsb Resource RGrover, NRR DWarner, NRR ADAMS A ccess1on N b ML 17272A011 um er: OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/STSB/BC* NAME MMarshall LRonewicz JWhitman DATE 10/02/2017 10/02/2017 08/30/2017 *b *1 1y e-ma1 DORL/LPL 1 /BC DORL/LPL 1/PM JDanna MMarshall 10/10/2017 10/10/2017 OFFICIAL RECORD COPY | | NINE MILE POINT NUCLEAR STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357) |
| }} | | DATED OCTOBER 10, 2017 DISTRIBUTION: |
| | Public RidsNrrDorlLpl1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDssStsb Resource RGrover, NRR DWarner, NRR ADAMS Access1on N um ber: ML17272A011 *b1y e-ma1*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/STSB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz JWhitman JDanna MMarshall DATE 10/02/2017 10/02/2017 08/30/2017 10/10/2017 10/10/2017 OFFICIAL RECORD COPY}} |
Letter Sequence RAI |
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CAC:MF9357, Reactor Pressure Vessel Water Inventory Control, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) |
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MONTHYEARNMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017
License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
Project stage: Request
ML17081A0532017-03-27027 March 2017
Summary of March 9, 2017, Meeting with Exelon Generation Company, LLC, Regarding License Amendment Request to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-542
Project stage: Meeting
ML17087A1452017-03-31031 March 2017
Acceptance of Requested Licensing Action Amendment to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
Project stage: Acceptance Review
ML17272A0112017-10-10010 October 2017
Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control
Project stage: RAI
NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017
Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water
Project stage: Response to RAI
NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017
Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
Project stage: Supplement
NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018
Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
Project stage: Supplement
NMP2L2667, Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-02-0606 February 2018
Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
Project stage: Supplement
ML18073A3642018-03-28028 March 2018
Issuance of Amendment No. 168 to Revise Technical Specifications to Adopt TS Traveler Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357; EPID L-2017-LLA-0178)
Project stage: Approval
2017-03-27
[Table View] |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
ML23264A7992023-09-21021 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)
ML18067A1482018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation)
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
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 10, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357)
Dear Mr. Hanson:
By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review.
Enclosed is the NRC staff's request for additional information. The request for additional information was discussed with your staff on October 3, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter.
If you have any questions, please contact me at 301-415-2871 or Michael.Marshall@nrc.gov.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
Request for Additional Information cc w/
Enclosure:
Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 By letter dated February 28, 2017 (Agencywide Documents Access and Management System Accession No. ML17059C963), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would revise the Nine Mile Point Nuclear Station, Unit 2, Technical Specifications (TSs) by replacing existing requirements related to "operations with a potential for draining the reactor vessel" with new requirements on reactor pressure vessel (RPV) water inventory control to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor pressure vessel water level to be greater than the top of active irradiated fuel.
The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed to complete its review of the request.
Requests for Additional Information (1) In Table 3.3.5.2-1 (page 2 of 2), "RPV Water Inventory Control Instrumentation, of the TS markup, the "Manual Initiation" Function is designated "3.f." In the last sub-bullet on page 5 of the application, it is implied that the "Manual Initiation" Function should be designated as "3.e." Clarify whether the designation for the "Manual Initiation" Function in Table 3.3.5.2-1 of the TS markup is "3.e" or "3.f ."
(2) In TS markup, the Limiting Condition for Operation 3.3.5.2, "RPV Water Inventory Control instrumentation," Condition E has two Required Actions. The first Required Action is designated "E.1." The other Required Action, which states, "Restore channel to OPERABLE status," does not have a designation. What is the designation of the second required action?
(3) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 2.a is "1 per pump." In the current version of the table in Nine Mile Point, Unit 2, TSs and the second bullet on page 4 of the application, the licensee states that the required channels per function for Function 2.a is "1 per valve." Also, "1 per pump" is an apparent variation from the TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." In the TS markup for TSTF-542, the required channels per function is "1." Clarify whether the required channels per function for Function 2.a in Table 3.3.5.2-1 of the TS markup is "1 per pump," "1 per valve," or "1." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF.
Enclosure
(4) In Table 3.3.5.2-1 (page 1 of 2), "RPV Water Inventory Control Instrumentation," of the TS markup, the required channels per function for Function 1.d is "1." In TS markup for TST-542, the required channels per function is "1 per pump." The required channels per function of "1" is an apparent variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Clarify whether the required channels per function for Function 1.d in Table 3.3.5.2-1 of the TS markup is "1" or "1 per pump." If the required channels per function is a variation from the TSTF, provide a discussion whether the variation affects the applicability of the TSTF.
(5) In Table 3.3.6.2 (page 1 of 1), "Secondary Containment Isolation Instrumentation," of the TS markup, the third function is "Reactor Building Above the Refuel Floor Exhaust Radiation -
High." In the TS markup for TSTF-542, the third function is "Reactor Building Exhaust Radiation - High." The third function in the TS markup appears to be a variation from TSTF-542, Revision 2, and no discussion concerning the applicability of the TSTF is included in the application. Provide a discussion whether the apparent variation affects the applicability of the TSTF.
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT CONCERNING REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL (CAC NO. MF9357)
DATED OCTOBER 10, 2017 DISTRIBUTION:
Public RidsNrrDorlLpl1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDssStsb Resource RGrover, NRR DWarner, NRR ADAMS Access1on N um ber: ML17272A011 *b1y e-ma1*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/STSB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz JWhitman JDanna MMarshall DATE 10/02/2017 10/02/2017 08/30/2017 10/10/2017 10/10/2017 OFFICIAL RECORD COPY
