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| {{#Wiki_filter:}} | | {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 11, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: TECHNICAL SPECIFICATION REVIEW FOR EXTENSION OF COMPLETION TIME FOR INOPERABLE DIESEL GENERATOR (TAC NO. ME3736) |
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| | ==Dear Mr. Belcher:== |
| | By letter dated March 30, 2010, as supplemented on June 1, 2010, December 29, 2010, January 14, 2011, February 25, 2011, and April 27, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment would modify NMP2 Technical Specification (TS) Section 3.8.1, !lAC Sources -Operating," to extend the Completion Time for an inoperable Division 1 or Division 2 diesel generator from 72 hours to 14 days. The proposed amendment represents a informed licensing change. The Nuclear Regulatory Commission staff is reviewing the information provided in those letters and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on June 15 and July 6, 2011, and it was agreed that your response would be provided within 30 days of the date of this letter. Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST RE: EXTENSION OF COMPLETION TIME INOPERABLE DIESEL TECHNICAL SPECIFICATIONS NINE MILE POINT NUCLEAR STATION, NINE MILE POINT NUCLEAR STATION, UNIT DOCKET NO. By letter dated March 30, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 100900460), as supplemented by letters dated June 1, 2010 (ML 101600452), December 29,2010 (ML 110110165), January 14,2011 (ML 110250271), February 25, 2011 (ML 110670424), and April 27, 2011 (ML 11119A 137), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point Nuclear Station, Unit No.2 (NMP2) requesting changes to the Technical Specifications (TSs) to extend the allowable completion time (CT) from 72 hours to 14 days when one emergency diesel generator (DG) is inoperable. |
| | The NRC staff is reviewing the LAR and has determined that additional information as requested below will be needed to complete its review. Based on the NRC staff's review of the LAR and the supplemental information, the NRC staff has identified areas for which additional information is needed to complete its review. In your response to the NRC staff's request for additional information (RAI) dated January 14, 2011, the following statements were provided, in part, in response to RAI-1: As noted in the March 30, 2010 NMPNS submittal, prior to utilizing the extended DG CT (greater than 72 hours and up to 14 days), operability of the HPCS [High Pressure Core Spray] system and the Division 3 (HPCS) DG will be confirmed, with no planned maintenance or testing activities scheduled (Emphasis added). This confirmation is a prerequisite for entering the extended DG CT. The response to RAI-1 also states: ... As specified in TS 3.8.1, if the HPCS DG became inoperable during the time that the Division 1 or Division 2 DG was already inoperable, Required Action E.1 would require that the HPCS DG be restored to operable status within 24 hours. At the end of this 24-hour period, the HPCS system could be declared inoperable in accordance with the Applicability Note for TS 3.8.1, and Condition E could be exited with only one required DG remaining inoperable |
| | ...." Emphasis added). Enclosure |
| | -2 Regarding the following RAI, it should be noted that the NMP2 TSs, Section 1.1, defines OPERABLE-OPERABILITY as follows: A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). |
| | RAI-1.a Please explain how and why the OPERABLE HPCS could be intentionally declared inoperable given that no planned maintenance or testing activities will be scheduled during the extended CT. RAI-1.b Please explain why the HPCS could be made intentionally inoperable given the above stated assurance that the OPERABILITY of the HPCS system and the Division 3 (HPCS) DG will be confirmed as a prerequisite for entering the extended DG CT. RAI-1.c Please explain how it is possible to declare the HPCS system inoperable given the scenario described above when the system has been verified as OPERABLE, no work has been performed on the system and the system is OPERABLE per the NMP2 TS definition. |
| | RAI-1.d Please explain the safety benefit(s) of intentionally causing an OPERABLE HPCS to be TS inoperable in order to extend the TS LCO 3.8.1.b non-compliance time, by an additional 4 hours, when operating in a mode where the HPCS is required to be OPERABLE. |
| | RAI-1.e As identified in the above January 14, 2011, response to RAI -1, it is stated that: " ... prior to utilizing the extended DG CT (greater than 72 hours and up to 14 days), operability of the HPCS system and the Division 3 (HPCS) DG will be confirmed, with no planned maintenance or testing activities scheduled." However, in the LAR dated March 30,2010, Attachment 1, List of Regulatory Commitments, and Attachment 3, Changes to Technical Specifications Bases, it is stated that: "The HPCS system is available and no planned maintenance or testing activities are scheduled." Please explain/provide (1) any difference(s) between "operability" and "available" as used in the above statements, (2) the definition of "available," and identify where in the NMP2 TS the |
| | -3 definition of "available" can be found, (3) provide an example of how an "available" HPCS, or other safety-related system, structure or component (SSC), differs from a TS "OPERABLE/OPERABILITY" HPCS or SSC. The NMP2 TS LCO 3.0.2 Bases states, in part: The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. |
| | The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. |
| | Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. |
| | Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead .... Please explain how the intentional removal of the OPERABLE HPCS system from service (Le., declared TS inoperable per the above definition of OPERABLE-OPERABILITY): Does not compromise safety, Does not result in redundant equipment being inoperable, Is not being done for operational convenience (i.e., provide additional time to operate while the requirements of TS LCO 3.8.1 are not being met). The requirements for TS LCOs are established in 10 CFR 50.36, which states: Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. |
| | When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. The definition of "remedial actions" is described in the Standard Technical Specifications (NUREG-1434) as follows: ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under deSignated Conditions within specified Completion Times. Regarding the above background, please explain how NMP2 TS 3.8.1, Required Action E.1, "Restore one required inoperable DG to OPERABLE status" is met, with either Division 1 or Division 2 DG inoperable and the Division 3 DG inoperable by intentionally placing the TS OPERABLE HPCS in an inoperable Condition per the TS 3.8.1 "Note." |
| | July 11, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: TECHNICAL SPECIFICATION REVIEW FOR EXTENSION OF COMPLETION TIME FOR INOPERABLE DIESEL GENERATOR (TAC NO. ME3736) |
| | |
| | ==Dear Mr. Belcher:== |
| | By letter dated March 30, 2010, as supplemented on June 1, 2010, December 29, 2010, January 14, 2011, February 25, 2011, and April 27, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment would modify NMP2 Technical Specification (TS) Section 3.8.1, !lAC Sources -Operating, to extend the Completion Time for an inoperable Division 1 or Division 2 n diesel generator from 72 hours to 14 days. The proposed amendment represents a informed licensing change. The Nuclear Regulatory Commission staff is reviewing the information provided in those letters and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on June 15 and July 6, 2011, and it was agreed that your response would be provided within 30 days of the date of this letter. Sincerely, IRA! Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
| | |
| | ==Enclosure:== |
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| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrPMNineMilePoint RidsNrrLASLittle RidsNrrDorlLpl1-1 LPLI-1 R/F RidsOGCRp RidsRgn1 MailCenter RidsNrrDraApla RidsN rrDeEeeb RidsNrrDirsltsb RidsNrrAcrsAcnw&mMailCenter ADAMS Accession No .. ML 111660388 |
| | *RAI provided by memo. No substantial changes made. OFFICE LPL 1-1/PM LPL1-1/LA ITSS/SC' LPL 1-1/SC INAME RGuzman SUttle RElliott NSalgado IDATE 7/11/11 7/11/11 06/09/11 7/11/11 OFFICIAL RECORD COPY}} |
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MONTHYEARML1009004602010-03-30030 March 2010 Submittal of License Amendment Request, Extension of Completion Time for an Inoperable Diesel Generator - Technical Specification 3.8.1, AC Sources - Operating Project stage: Request ML1011803792010-04-28028 April 2010 Unit No.2 - E-mail from R. Guzman to J. Dosa Acceptance Review for LAR - Inoperable DG 14-Day Completion Time Extension Project stage: Acceptance Review ML1012601662010-05-0606 May 2010 E-mail from R. Guzman to J. Dosa Acceptance Review Revised Questions for License Amendment Requesting 14 Day Completion Time Extension for Inoperable EDG Project stage: Acceptance Review ML1012307272010-05-11011 May 2010 Acceptance Review Determination of License Amendment Request Extension of Completion Time for Inoperable Diesel Generator Project stage: Acceptance Review ML1016004522010-06-0101 June 2010 Submittal of Supplemental Information in Support of License Amendment Extension of Completion Time for an Inoperable Diesel Generator Project stage: Supplement ML1016003832010-06-11011 June 2010 Acceptance Review of License Amendment Request and Supplemental Information Extension of Completion Time for an Inoperable Diesel Generator Project stage: Acceptance Review ML1031302612010-11-0909 November 2010 Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Electrical Engineering Review Project stage: RAI ML1031303272010-12-15015 December 2010 Request for Additional Information Extension of Allowed Outage Time for Inoperable Diesel Generator, Probabilistic Risk Assessment Project stage: RAI ML1101101652010-12-29029 December 2010 Response to NRC Request for Additional Information on License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator Project stage: Response to RAI ML1102502712011-01-14014 January 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Response to NRC Request for Additional Information Project stage: Response to RAI ML1103906562011-02-0808 February 2011 E-mail from R.Guzman to D.Vandeputte - Request for Additional Information Div 3 EDG CT Extension LAR - PRA Review Project stage: RAI ML1105305442011-02-22022 February 2011 E-mail from R. Guzman to D. Vandeputte - Supplemental Request for Additional Information Extension of Completion Time for Inoperable DG Project stage: RAI ML1106704242011-02-25025 February 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Supplemental Information Responding to NRC Follow-up Probabilistic Risk Assessment Review Question Project stage: Supplement ML1107006342011-03-11011 March 2011 E-mail from R. Guzman to S. Som Regarding Supplemental Information from Licensee Regarding License Amendment Request for Completion Time Extension - Division 3 DG Project stage: Other ML1106910202011-03-15015 March 2011 Supplemental Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Electrical Engineering Review Project stage: RAI ML11119A1372011-04-27027 April 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of Completion Time for Inoperable Diesel Generator-Supplemental Information Responding to NRC Follow-up Electrical Engineering Branch Review Questions Project stage: Supplement ML1117414582011-06-23023 June 2011 E-mail from R. Guzman to J. Dosa Requesting Supplemental Information Boral Monitoring Program NMP2 Extended Power Uprate LAR Project stage: Other ML1116603882011-07-11011 July 2011 Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Technical Specifications Review Project stage: RAI ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information Project stage: Response to RAI ML1122200812011-08-0909 August 2011 E-mail from Alyse Peterson to Richard Guzman NRC Request for State Consultation for Proposed Amendment Regarding Allowed Outage Time Extension for Division 1 or Division 2 Diesel Generator Inoperable Project stage: Request ML1130400692011-10-31031 October 2011 E-mail from R. Guzman to A. Peterson NRC Response to State Comments for Proposed Amendment Regarding Allowed Outage Time Extension for Division 1 or Division 2 Diesel Generator Inoperable Project stage: Other ML1122001552011-10-31031 October 2011 Issuance of Amendment Regarding Extension of Completion Time for Inoperable Division 1 or Division 2 Diesel Generator Project stage: Approval 2011-10-31
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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 - 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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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 11, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: TECHNICAL SPECIFICATION REVIEW FOR EXTENSION OF COMPLETION TIME FOR INOPERABLE DIESEL GENERATOR (TAC NO. ME3736)
Dear Mr. Belcher:
By letter dated March 30, 2010, as supplemented on June 1, 2010, December 29, 2010, January 14, 2011, February 25, 2011, and April 27, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment would modify NMP2 Technical Specification (TS) Section 3.8.1, !lAC Sources -Operating," to extend the Completion Time for an inoperable Division 1 or Division 2 diesel generator from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The proposed amendment represents a informed licensing change. The Nuclear Regulatory Commission staff is reviewing the information provided in those letters and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on June 15 and July 6, 2011, and it was agreed that your response would be provided within 30 days of the date of this letter. Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST RE: EXTENSION OF COMPLETION TIME INOPERABLE DIESEL TECHNICAL SPECIFICATIONS NINE MILE POINT NUCLEAR STATION, NINE MILE POINT NUCLEAR STATION, UNIT DOCKET NO. By letter dated March 30, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 100900460), as supplemented by letters dated June 1, 2010 (ML 101600452), December 29,2010 (ML 110110165), January 14,2011 (ML 110250271), February 25, 2011 (ML 110670424), and April 27, 2011 (ML 11119A 137), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for Nine Mile Point Nuclear Station, Unit No.2 (NMP2) requesting changes to the Technical Specifications (TSs) to extend the allowable completion time (CT) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days when one emergency diesel generator (DG) is inoperable.
The NRC staff is reviewing the LAR and has determined that additional information as requested below will be needed to complete its review. Based on the NRC staff's review of the LAR and the supplemental information, the NRC staff has identified areas for which additional information is needed to complete its review. In your response to the NRC staff's request for additional information (RAI) dated January 14, 2011, the following statements were provided, in part, in response to RAI-1: As noted in the March 30, 2010 NMPNS submittal, prior to utilizing the extended DG CT (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), operability of the HPCS [High Pressure Core Spray] system and the Division 3 (HPCS) DG will be confirmed, with no planned maintenance or testing activities scheduled (Emphasis added). This confirmation is a prerequisite for entering the extended DG CT. The response to RAI-1 also states: ... As specified in TS 3.8.1, if the HPCS DG became inoperable during the time that the Division 1 or Division 2 DG was already inoperable, Required Action E.1 would require that the HPCS DG be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. At the end of this 24-hour period, the HPCS system could be declared inoperable in accordance with the Applicability Note for TS 3.8.1, and Condition E could be exited with only one required DG remaining inoperable
...." Emphasis added). Enclosure
-2 Regarding the following RAI, it should be noted that the NMP2 TSs, Section 1.1, defines OPERABLE-OPERABILITY as follows: A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RAI-1.a Please explain how and why the OPERABLE HPCS could be intentionally declared inoperable given that no planned maintenance or testing activities will be scheduled during the extended CT. RAI-1.b Please explain why the HPCS could be made intentionally inoperable given the above stated assurance that the OPERABILITY of the HPCS system and the Division 3 (HPCS) DG will be confirmed as a prerequisite for entering the extended DG CT. RAI-1.c Please explain how it is possible to declare the HPCS system inoperable given the scenario described above when the system has been verified as OPERABLE, no work has been performed on the system and the system is OPERABLE per the NMP2 TS definition.
RAI-1.d Please explain the safety benefit(s) of intentionally causing an OPERABLE HPCS to be TS inoperable in order to extend the TS LCO 3.8.1.b non-compliance time, by an additional 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, when operating in a mode where the HPCS is required to be OPERABLE.
RAI-1.e As identified in the above January 14, 2011, response to RAI -1, it is stated that: " ... prior to utilizing the extended DG CT (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), operability of the HPCS system and the Division 3 (HPCS) DG will be confirmed, with no planned maintenance or testing activities scheduled." However, in the LAR dated March 30,2010, Attachment 1, List of Regulatory Commitments, and Attachment 3, Changes to Technical Specifications Bases, it is stated that: "The HPCS system is available and no planned maintenance or testing activities are scheduled." Please explain/provide (1) any difference(s) between "operability" and "available" as used in the above statements, (2) the definition of "available," and identify where in the NMP2 TS the
-3 definition of "available" can be found, (3) provide an example of how an "available" HPCS, or other safety-related system, structure or component (SSC), differs from a TS "OPERABLE/OPERABILITY" HPCS or SSC. The NMP2 TS LCO 3.0.2 Bases states, in part: The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally.
The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems.
Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience.
Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead .... Please explain how the intentional removal of the OPERABLE HPCS system from service (Le., declared TS inoperable per the above definition of OPERABLE-OPERABILITY): Does not compromise safety, Does not result in redundant equipment being inoperable, Is not being done for operational convenience (i.e., provide additional time to operate while the requirements of TS LCO 3.8.1 are not being met). The requirements for TS LCOs are established in 10 CFR 50.36, which states: Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. The definition of "remedial actions" is described in the Standard Technical Specifications (NUREG-1434) as follows: ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under deSignated Conditions within specified Completion Times. Regarding the above background, please explain how NMP2 TS 3.8.1, Required Action E.1, "Restore one required inoperable DG to OPERABLE status" is met, with either Division 1 or Division 2 DG inoperable and the Division 3 DG inoperable by intentionally placing the TS OPERABLE HPCS in an inoperable Condition per the TS 3.8.1 "Note."
July 11, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -RE: TECHNICAL SPECIFICATION REVIEW FOR EXTENSION OF COMPLETION TIME FOR INOPERABLE DIESEL GENERATOR (TAC NO. ME3736)
Dear Mr. Belcher:
By letter dated March 30, 2010, as supplemented on June 1, 2010, December 29, 2010, January 14, 2011, February 25, 2011, and April 27, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment for Nine Mile Point, Unit No.2 (NMP2). The proposed amendment would modify NMP2 Technical Specification (TS) Section 3.8.1, !lAC Sources -Operating, to extend the Completion Time for an inoperable Division 1 or Division 2 n diesel generator from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The proposed amendment represents a informed licensing change. The Nuclear Regulatory Commission staff is reviewing the information provided in those letters and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on June 15 and July 6, 2011, and it was agreed that your response would be provided within 30 days of the date of this letter. Sincerely, IRA! Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMNineMilePoint RidsNrrLASLittle RidsNrrDorlLpl1-1 LPLI-1 R/F RidsOGCRp RidsRgn1 MailCenter RidsNrrDraApla RidsN rrDeEeeb RidsNrrDirsltsb RidsNrrAcrsAcnw&mMailCenter ADAMS Accession No .. ML 111660388
- RAI provided by memo. No substantial changes made. OFFICE LPL 1-1/PM LPL1-1/LA ITSS/SC' LPL 1-1/SC INAME RGuzman SUttle RElliott NSalgado IDATE 7/11/11 7/11/11 06/09/11 7/11/11 OFFICIAL RECORD COPY