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| ==SUBJECT:== | | ==SUBJECT:== |
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| NINE MILE POINT NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 (CAC NO. MF6061) | | NINE MILE POINT NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 (CAC NO. MF6061) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232), Exelon Generation Company, LLC (the licensee) requested an amendment to the Nine Mile Point Nuclear Station, Unit 1 (NMP1) Renewed Facility Operating License. The proposed license amendment would adopt Technical Specification Task Force Traveler-425 (TSTF-425), Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642). The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220 | | By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232), |
| | Exelon Generation |
| | : Company, LLC (the licensee) requested an amendment to the Nine Mile Point Nuclear Station, Unit 1 (NMP1) Renewed Facility Operating License. |
| | The proposed license amendment would adopt Technical Specification Task Force Traveler-425 (TSTF-425), |
| | Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642). |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAI cc w/encl: Distribution via Listserv Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION. UNIT 1 LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232), Exelon Generation Company, LLC (the licensee) submitted a License Amendment Request (LAR) to revise the technical specifications (TS) for Nine Mile Point, Unit 1 (NMP-1). The LAR proposed to adopt the Technical Specification Task Force traveler (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk-Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642). During the application review, the Nuclear Regulatory Commission (NRC) staff identified the following requests for additional information (RAls): Technical Specifications Branch (STSB) RAl-1 As part of this LAR submittal, several surveillance requirement (SR) frequency changes were proposed in Table 4.6.2a, "INSTRUMENTATION THAT INITIATES SCRAM," (page 201) of the NMP-1 TS. The proposed SR frequency revisions for parameters two through four have a superscript of (1 ). The NRC staff was unable to locate this note in the TS. As discussed during the clarification call held on October 26, 2015, provide the supporting note for the proposed change, and modify the submittal as needed to correct the superscript. STSB RAl-2 As part of this LAR submittal, SR frequency changes were proposed for two channel calibrations in Item (9)(b)(i) from Table 4.6.2a of the NMP-1 TS. The NRC staff was unable to tell the difference between the two calibrations that are being performed on different intervals (i.e., per week and per month). When the calibration frequencies are moved to the surveillance frequency control program (SFCP), generic wording will replace these two frequencies, which will potentially remove the ability of a reader of the TS to discern that this item contains two discrete calibrations. Since the SRs are both linked to item (9)(b)(i) from Table 4.6.2a, explain (1) how the SRs are different, (2) how this difference will be tracked in the SFCP, and (3) how it will be clear in the Enclosure TS that this item pertains to two discrete calibrations. If necessary, modify the submittal as appropriate to address these concerns. STSB RAl-3 On TS bases page 98 submitted by the licensee, the following is stated, "Reactor water samples are analyzed daily to ensure that reactor water quality remains within the BWR water chemistry guidelines." The NRC staff could not determine whether these reactor water samples were the same ones referenced in SR 4.2.3, "COOLANT CHEMISTRY." Explain the difference between the SR 4.2.3 frequency and this bases description. If necessary, modify the submittal as appropriate. STSB RAl-4 In Attachment-3, "Proposed Technical Specification and Bases Page Changes," of the LAR submittal, the licensee requests to incorporate control of the SR 4.2. 7.d frequency (page 109) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "At least once per plant cold shutdown;" therefore, the event driving the SR performance is a cold shutdown. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a justification for deviating from the TSTF-425 requirements or, if necessary, modify the submittal as appropriate. STSB RAl-5 On TS bases page 158 submitted by the licensee, it is indicated that the frequency for SR 4.3.6.b(4) [i.e., the leak rate test between the drywell and suppression chamber] is being transferred to the control of the SPCP, but, in contrast, TS page 154 of the LAR does not indicate that the frequency for this SR is being revised. Provide a justification for this difference or if necessary, modify the submittal as appropriate. STSB RAl-6 For TS tables 4.6.2a through 4.6.21 of the NMP-1 TS, there is a common note associated with this series of tables that appears several times. The note reads, "Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2[a-1], the primary sensor will be calibrated and tested once per operating cycle." The LAR proposes to delete this note as part of the TSTF-425 adoption. The note provides an SR for the primary sensor along with a frequency, which will potentially not be accounted for if the note is deleted. Explain how the primary sensor SR will be accounted for in the proposed revision of the TS or if necessary, modify the submittal as appropriate. STSB RAl-7 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the SR 4.6.5.3 frequency (page 266) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "within 31 days prior to being subjected to core flux;" therefore, the event driving the SR performance is the start-up sources being subjected to core flux. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a technical justification for deviating from the TSTF-425 requirements or if necessary, modify the submittal as appropriate. STSB RAl-8 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the following SR frequencies into the SFCP:
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| * Frequencies associated with individual SRs 4.1.3.e, 4.1.4.a, 4.2.5.b(1 ), 4.3.2.b, 4.3.6.c(2), 4.6.3.a, 4.6.12.b, 4.6.13.b and
| |
| * SR frequencies listed in the following tables: 4.6.2b (parameters: 2, 6, 7, 8), 4.6.2g (parameters: 6, 7), 4.6.2i (parameters: a, b), 4.6.11 (parameters: 3, 4, 5, 7, 8), 4.6.13-1 (parameters: Reactor Water Temperature, Torus Water Temperature, Emergency Condenser Water Level, Drywell Temperature, and "All Rods In" Light). These SR frequencies contain verbiage (e.g., refueling outage, major refueling outage, refueling cycle), which indicates that SR performance is based on a refueling outage event. In the licensee's submission it was unclear whether or not all of these SRs were frequency based or, possibly, purely event driven. For example, if performance of an SR is mandated every time the unit is transitioned to a plant shutdown condition during an operating cycle (i.e., not during a major refueling outage), then this SR would be considered purely event driven. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, address each of the aforementioned SR frequencies and indicate whether they are frequency based or purely event driven. If the SRs are purely event driven, justify their inclusion into the SFCP or if necessary, modify the submittal as appropriate.
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| ML090850642). The 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 (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220 | | RAI cc w/encl: Distribution via Listserv Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION |
| | : COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION. |
| | UNIT 1 LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232), |
| | Exelon Generation |
| | : Company, LLC (the licensee) submitted a License Amendment Request (LAR) to revise the technical specifications (TS) for Nine Mile Point, Unit 1 (NMP-1). |
| | The LAR proposed to adopt the Technical Specification Task Force traveler (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk-Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642). |
| | During the application review, the Nuclear Regulatory Commission (NRC) staff identified the following requests for additional information (RAls): Technical Specifications Branch (STSB) RAl-1 As part of this LAR submittal, several surveillance requirement (SR) frequency changes were proposed in Table 4.6.2a, "INSTRUMENTATION THAT INITIATES SCRAM," (page 201) of the NMP-1 TS. The proposed SR frequency revisions for parameters two through four have a superscript of (1 ). The NRC staff was unable to locate this note in the TS. As discussed during the clarification call held on October 26, 2015, provide the supporting note for the proposed change, and modify the submittal as needed to correct the superscript. |
| | STSB RAl-2 As part of this LAR submittal, SR frequency changes were proposed for two channel calibrations in Item (9)(b)(i) from Table 4.6.2a of the NMP-1 TS. The NRC staff was unable to tell the difference between the two calibrations that are being performed on different intervals (i.e., per week and per month). When the calibration frequencies are moved to the surveillance frequency control program (SFCP), generic wording will replace these two frequencies, which will potentially remove the ability of a reader of the TS to discern that this item contains two discrete calibrations. |
| | Since the SRs are both linked to item (9)(b)(i) from Table 4.6.2a, explain (1) how the SRs are different, (2) how this difference will be tracked in the SFCP, and (3) how it will be clear in the Enclosure TS that this item pertains to two discrete calibrations. |
| | If necessary, modify the submittal as appropriate to address these concerns. |
| | STSB RAl-3 On TS bases page 98 submitted by the licensee, the following is stated, "Reactor water samples are analyzed daily to ensure that reactor water quality remains within the BWR water chemistry guidelines." |
| | The NRC staff could not determine whether these reactor water samples were the same ones referenced in SR 4.2.3, "COOLANT CHEMISTRY." |
| | Explain the difference between the SR 4.2.3 frequency and this bases description. |
| | If necessary, modify the submittal as appropriate. |
| | STSB RAl-4 In Attachment-3, "Proposed Technical Specification and Bases Page Changes," |
| | of the LAR submittal, the licensee requests to incorporate control of the SR 4.2. 7.d frequency (page 109) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "At least once per plant cold shutdown;" |
| | therefore, the event driving the SR performance is a cold shutdown. |
| | The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a justification for deviating from the TSTF-425 requirements or, if necessary, modify the submittal as appropriate. |
| | STSB RAl-5 On TS bases page 158 submitted by the licensee, it is indicated that the frequency for SR 4.3.6.b(4) |
| | [i.e., the leak rate test between the drywell and suppression chamber] |
| | is being transferred to the control of the SPCP, but, in contrast, TS page 154 of the LAR does not indicate that the frequency for this SR is being revised. |
| | Provide a justification for this difference or if necessary, modify the submittal as appropriate. |
| | STSB RAl-6 For TS tables 4.6.2a through 4.6.21 of the NMP-1 TS, there is a common note associated with this series of tables that appears several times. The note reads, "Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2[a-1], |
| | the primary sensor will be calibrated and tested once per operating cycle." The LAR proposes to delete this note as part of the TSTF-425 adoption. |
| | The note provides an SR for the primary sensor along with a frequency, which will potentially not be accounted for if the note is deleted. |
| | Explain how the primary sensor SR will be accounted for in the proposed revision of the TS or if necessary, modify the submittal as appropriate. STSB RAl-7 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the SR 4.6.5.3 frequency (page 266) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "within 31 days prior to being subjected to core flux;" therefore, the event driving the SR performance is the start-up sources being subjected to core flux. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a technical justification for deviating from the TSTF-425 requirements or if necessary, modify the submittal as appropriate. |
| | STSB RAl-8 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the following SR frequencies into the SFCP: |
| | * Frequencies associated with individual SRs 4.1.3.e, 4.1.4.a, 4.2.5.b(1 |
| | ), 4.3.2.b, 4.3.6.c(2), |
| | 4.6.3.a, 4.6.12.b, 4.6.13.b and |
| | * SR frequencies listed in the following tables: 4.6.2b (parameters: |
| | 2, 6, 7, 8), 4.6.2g (parameters: |
| | 6, 7), 4.6.2i (parameters: |
| | a, b), 4.6.11 (parameters: |
| | 3, 4, 5, 7, 8), 4.6.13-1 (parameters: |
| | Reactor Water Temperature, Torus Water Temperature, Emergency Condenser Water Level, Drywell Temperature, and "All Rods In" Light). These SR frequencies contain verbiage (e.g., refueling outage, major refueling outage, refueling cycle), which indicates that SR performance is based on a refueling outage event. In the licensee's submission it was unclear whether or not all of these SRs were frequency based or, possibly, purely event driven. For example, if performance of an SR is mandated every time the unit is transitioned to a plant shutdown condition during an operating cycle (i.e., not during a major refueling outage), |
| | then this SR would be considered purely event driven. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, address each of the aforementioned SR frequencies and indicate whether they are frequency based or purely event driven. If the SRs are purely event driven, justify their inclusion into the SFCP or if necessary, modify the submittal as appropriate. |
| | Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 November 9, 2015 |
| | |
| | ==SUBJECT:== |
| | |
| | NINE MILE POINT NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER 425 (CAC NO. MF6061) |
| | |
| | ==Dear Mr. Hanson:== |
| | By letter dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232), |
| | Exelon Generation |
| | : Company, LLC (the licensee) requested an amendment to the Nine Mile Point Nuclear Station, Unit 1 (NMP1) Renewed Facility Operating License. |
| | The proposed license amendment would adopt Technical Specification Task Force Traveler-425 (TSTF-425), |
| | Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642). |
| | The 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 (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| RAI Sincerely, /RAJ Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLl-1 R/F RidsNrrDorlDpr W. Satterfield, NRR ADAMS Accession No.: RidsNrrDorlLpll-1 RidsNrrLAKGoldstein RidsRgn1 MailCenter ML1 5301 A021 RidsNrrPMNineMilePoint RidsACRS_MailCTR RidsNrrDssStsb *t . db d d ransm1tte ,y ate memo OFFICE DORL/LPLl-1 /PM DORL/LPLl-1 /LA DSS/STSB/BC* DORL/LPLl-1 /BC DORL/LPLl-1 /PM NAME AChereskin KGoldstein RElliot TTate AChereskin DATE 11/03/2015 10/28/2015 11/02/2015 11/09/2015 11/09/2015}} | | |
| | RAI Sincerely, |
| | /RAJ Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPLl-1 R/F RidsNrrDorlDpr W. Satterfield, NRR ADAMS Accession No.: RidsNrrDorlLpll-1 RidsNrrLAKGoldstein RidsRgn1 MailCenter ML1 5301 A021 RidsNrrPMNineMilePoint RidsACRS_MailCTR RidsNrrDssStsb |
| | *t . db d d ransm1tte |
| | ,y ate memo OFFICE DORL/LPLl-1 |
| | /PM DORL/LPLl-1 |
| | /LA DSS/STSB/BC* |
| | DORL/LPLl-1 |
| | /BC DORL/LPLl-1 |
| | /PM NAME AChereskin KGoldstein RElliot TTate AChereskin DATE 11/03/2015 10/28/2015 11/02/2015 11/09/2015 11/09/2015 OFFICIAL RECORD COPY}} |
Letter Sequence RAI |
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CAC:MF6061, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed) |
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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
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
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
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
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
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
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
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
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
05000410/LER-2024-001, 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))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
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
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24312A1662024-11-0707 November 2024
Request for Additional Information (11/7/2024 E-mail) - LAR to Revise TSs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3
ML24197A0162024-07-12012 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
ML20213A9352020-07-30030 July 2020
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
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)
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
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 9, 2015
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 (CAC NO. MF6061)
Dear Mr. Hanson:
By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232),
Exelon Generation
- Company, LLC (the licensee) requested an amendment to the Nine Mile Point Nuclear Station, Unit 1 (NMP1) Renewed Facility Operating License.
The proposed license amendment would adopt Technical Specification Task Force Traveler-425 (TSTF-425),
Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642).
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220
Enclosure:
RAI cc w/encl: Distribution via Listserv Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION
- COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION.
UNIT 1 LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER-425 By application dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232),
Exelon Generation
- Company, LLC (the licensee) submitted a License Amendment Request (LAR) to revise the technical specifications (TS) for Nine Mile Point, Unit 1 (NMP-1).
The LAR proposed to adopt the Technical Specification Task Force traveler (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk-Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642).
During the application review, the Nuclear Regulatory Commission (NRC) staff identified the following requests for additional information (RAls): Technical Specifications Branch (STSB) RAl-1 As part of this LAR submittal, several surveillance requirement (SR) frequency changes were proposed in Table 4.6.2a, "INSTRUMENTATION THAT INITIATES SCRAM," (page 201) of the NMP-1 TS. The proposed SR frequency revisions for parameters two through four have a superscript of (1 ). The NRC staff was unable to locate this note in the TS. As discussed during the clarification call held on October 26, 2015, provide the supporting note for the proposed change, and modify the submittal as needed to correct the superscript.
STSB RAl-2 As part of this LAR submittal, SR frequency changes were proposed for two channel calibrations in Item (9)(b)(i) from Table 4.6.2a of the NMP-1 TS. The NRC staff was unable to tell the difference between the two calibrations that are being performed on different intervals (i.e., per week and per month). When the calibration frequencies are moved to the surveillance frequency control program (SFCP), generic wording will replace these two frequencies, which will potentially remove the ability of a reader of the TS to discern that this item contains two discrete calibrations.
Since the SRs are both linked to item (9)(b)(i) from Table 4.6.2a, explain (1) how the SRs are different, (2) how this difference will be tracked in the SFCP, and (3) how it will be clear in the Enclosure TS that this item pertains to two discrete calibrations.
If necessary, modify the submittal as appropriate to address these concerns.
STSB RAl-3 On TS bases page 98 submitted by the licensee, the following is stated, "Reactor water samples are analyzed daily to ensure that reactor water quality remains within the BWR water chemistry guidelines."
The NRC staff could not determine whether these reactor water samples were the same ones referenced in SR 4.2.3, "COOLANT CHEMISTRY."
Explain the difference between the SR 4.2.3 frequency and this bases description.
If necessary, modify the submittal as appropriate.
STSB RAl-4 In Attachment-3, "Proposed Technical Specification and Bases Page Changes,"
of the LAR submittal, the licensee requests to incorporate control of the SR 4.2. 7.d frequency (page 109) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "At least once per plant cold shutdown;"
therefore, the event driving the SR performance is a cold shutdown.
The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a justification for deviating from the TSTF-425 requirements or, if necessary, modify the submittal as appropriate.
STSB RAl-5 On TS bases page 158 submitted by the licensee, it is indicated that the frequency for SR 4.3.6.b(4)
[i.e., the leak rate test between the drywell and suppression chamber]
is being transferred to the control of the SPCP, but, in contrast, TS page 154 of the LAR does not indicate that the frequency for this SR is being revised.
Provide a justification for this difference or if necessary, modify the submittal as appropriate.
STSB RAl-6 For TS tables 4.6.2a through 4.6.21 of the NMP-1 TS, there is a common note associated with this series of tables that appears several times. The note reads, "Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2[a-1],
the primary sensor will be calibrated and tested once per operating cycle." The LAR proposes to delete this note as part of the TSTF-425 adoption.
The note provides an SR for the primary sensor along with a frequency, which will potentially not be accounted for if the note is deleted.
Explain how the primary sensor SR will be accounted for in the proposed revision of the TS or if necessary, modify the submittal as appropriate. STSB RAl-7 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the SR 4.6.5.3 frequency (page 266) into the SFCP. The current verbiage of this SR indicates that its performance is event driven. Specifically, it is performed "within 31 days prior to being subjected to core flux;" therefore, the event driving the SR performance is the start-up sources being subjected to core flux. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, provide a technical justification for deviating from the TSTF-425 requirements or if necessary, modify the submittal as appropriate.
STSB RAl-8 In Attachment-3 of the LAR submittal, the licensee proposed to incorporate control of the following SR frequencies into the SFCP:
- Frequencies associated with individual SRs 4.1.3.e, 4.1.4.a, 4.2.5.b(1
), 4.3.2.b, 4.3.6.c(2),
4.6.3.a, 4.6.12.b, 4.6.13.b and
- SR frequencies listed in the following tables: 4.6.2b (parameters:
2, 6, 7, 8), 4.6.2g (parameters:
6, 7), 4.6.2i (parameters:
a, b), 4.6.11 (parameters:
3, 4, 5, 7, 8), 4.6.13-1 (parameters:
Reactor Water Temperature, Torus Water Temperature, Emergency Condenser Water Level, Drywell Temperature, and "All Rods In" Light). These SR frequencies contain verbiage (e.g., refueling outage, major refueling outage, refueling cycle), which indicates that SR performance is based on a refueling outage event. In the licensee's submission it was unclear whether or not all of these SRs were frequency based or, possibly, purely event driven. For example, if performance of an SR is mandated every time the unit is transitioned to a plant shutdown condition during an operating cycle (i.e., not during a major refueling outage),
then this SR would be considered purely event driven. The licensee states that this LAR submission is in accordance with TSTF-425, Revision 3, which explicitly excludes purely event driven SRs from being eligible for incorporation into the SFCP. Based on the above discussion, address each of the aforementioned SR frequencies and indicate whether they are frequency based or purely event driven. If the SRs are purely event driven, justify their inclusion into the SFCP or if necessary, modify the submittal as appropriate.
Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 November 9, 2015
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER 425 (CAC NO. MF6061)
Dear Mr. Hanson:
By letter dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15134A232),
Exelon Generation
- Company, LLC (the licensee) requested an amendment to the Nine Mile Point Nuclear Station, Unit 1 (NMP1) Renewed Facility Operating License.
The proposed license amendment would adopt Technical Specification Task Force Traveler-425 (TSTF-425),
Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk Informed TSTF] Initiative Sb," dated March 18, 2009 (ADAMS Accession No. ML090850642).
The 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 (RAI). The RAI was discussed with your staff on October 16, 2015, and October 26, 2015, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket No. 50-220
Enclosure:
RAI Sincerely,
/RAJ Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLl-1 R/F RidsNrrDorlDpr W. Satterfield, NRR ADAMS Accession No.: RidsNrrDorlLpll-1 RidsNrrLAKGoldstein RidsRgn1 MailCenter ML1 5301 A021 RidsNrrPMNineMilePoint RidsACRS_MailCTR RidsNrrDssStsb
,y ate memo OFFICE DORL/LPLl-1
/PM DORL/LPLl-1
/LA DSS/STSB/BC*
DORL/LPLl-1
/BC DORL/LPLl-1
/PM NAME AChereskin KGoldstein RElliot TTate AChereskin DATE 11/03/2015 10/28/2015 11/02/2015 11/09/2015 11/09/2015 OFFICIAL RECORD COPY
