Letter Sequence Draft Request |
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TAC:ME1476, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: ML092460553, ML092460595, ML092460596, ML100190073, ML100190074, ML100190075, ML100190076, ML100190077, ML101300006, ML101900448, ML101900449, ML101900450, ML101950497, ML101950498, ML103050187, ML110460160, ML110880302, ML11171A060, ML111920326, ML111950133, ML112031112, ML112081701, ML112160736, ML11221A013, ML112450479, ML112460008, ML112460009, ML113340186, ML120050150, ML120250137, ML12313A203, ML12313A204, ML12313A206, NRC-2010-0117, Final Environmental Assessment and Finding of No Significant Impact - Federal Register Notice - Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level
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MONTHYEARML1001900772004-03-31031 March 2004 GE-NE-0000-0024-6517-R0, Safer/Gestr Loss-of-Coolant Accident Analysis for GE14 Fuel. Project stage: Other ML0916101032009-05-27027 May 2009 License Amendment Request (LAR) Pursuant to 10 CFR 50.90: Extended Power Uprate Project stage: Request ML0918906662009-07-0808 July 2009 E-mail from R. Guzman to J. Dosa Acceptance Review Results of NMP2 Extended Power Uprate Application Project stage: Acceptance Review ML0919402542009-07-15015 July 2009 Acceptance Review of License Amendment Request Extended Power Uprate Project stage: Acceptance Review ML0924605502009-08-28028 August 2009 Response to Acceptance Review Comments License Amendment Request for Extended Power Uprate Project stage: Request ML0924605962009-08-28028 August 2009 Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 2 of 2 Project stage: Other ML0924605952009-08-28028 August 2009 Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 1 of 2 Project stage: Other ML0924605532009-08-28028 August 2009 Attachment 3 - CDI Report 08-08NP, Revision 2, (Non-Proprietary) Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz Project stage: Other ML0924502742009-09-0202 September 2009 Acceptance Review Determination of Amendment Request and Supplemental Information Extended Power Uprate Project stage: Acceptance Review ML1019704202009-09-18018 September 2009 E-mail from R. Guzman to J. Dosa Request for Additional Information - Clarification of Applicability of GEH Methods Project stage: RAI ML0928100032009-10-0808 October 2009 Request for Additional Information Nine Mile Point Unit 2 (NMP2) Extended Power Uprate Application License Amendment Request Project stage: RAI ML0930800012009-11-13013 November 2009 Request for Additional Information Extended Power Uprate Project stage: RAI ML0931900032009-11-18018 November 2009 Request for Additional Information the License Amendment Request for Extended Power Uprate Project stage: RAI ML0934300032009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated August 28, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0932706132009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0934106852009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0935110252009-12-23023 December 2009 Request for Additional Information Extended Power Uprate License Amendment Request Project stage: RAI ML1001900722009-12-23023 December 2009 Response to Request for Additional Information, Regarding License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1001900732009-12-31031 December 2009 C.D.I. Technical Note No. 09-17NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Nine Mile Point, Unit 2, Revision 0 Project stage: Other ML1001900742009-12-31031 December 2009 C.D.I. Report No. 08-08NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz, Revision 3 Project stage: Other ML1001900752009-12-31031 December 2009 CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Cover to Page 62, Revision 1 Project stage: Other ML1001900762009-12-31031 December 2009 CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Page 63 Through 130, Revision 1 Project stage: Other ML1019704362010-01-12012 January 2010 E-mail from R. Guzman to T. Darling Request for Additional Information - Extended Power Uprate LAR Standby Liquid Control System Project stage: RAI ML1019704452010-01-27027 January 2010 E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate - Clarification for Piping NDE Review Project stage: RAI ML1019704532010-02-0101 February 2010 E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate LAR - Clarification in Fire Protection Review RAI D1, D3 Project stage: RAI ML1005505992010-02-19019 February 2010 Response to Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1006301122010-03-10010 March 2010 Request for Additional Information - Extended Power Uprate License Amendment Request Mechanical & Civil Engineering Review Project stage: RAI ML1006902762010-03-10010 March 2010 E-mail from R.Guzman to T.Darling Request for Additional Information - Containment & Ventilation Branch - Extended Power Uprate Project stage: RAI ML1006301082010-03-10010 March 2010 Request for Additional Information Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation Project stage: RAI ML1005508412010-03-16016 March 2010 Letter Transmitting the Draft Environmental Assessment for Nine Mile Point Nuclear Station Extended Power Uprate for Unit No. 2 Project stage: Draft Other ML1006804292010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated December 23, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1006804412010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement December 23,2 009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1006804482010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement February 19, 2010 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1008500412010-04-0202 April 2010 Summary of Audit Related to the Review of the Extended Power Uprate License Amendment Request of Nine Mile Point Nuclear Station, Unit No. 2 Project stage: Approval ML1008500512010-04-0202 April 2010 Correction Notice to Draft Environmental Assessment for Nine Mile Point Nuclear Station Proposed Extended Power Uprate Amendment for Unit No. 2 Project stage: Draft Other ML1008501072010-04-0202 April 2010 Letter Transmitting Correction to the Notice for the Draft Environmental Assessment and Finding of No Significant Impact for Nine Mile Point Nuclear Station, Unit No. 2 Project stage: Draft Other ML1013000062010-04-14014 April 2010 Follow-Up Questions - EPU Vessels and Integrity Review Project stage: Other ML1011206582010-04-16016 April 2010 Response to Request for Additional Information Re License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1013803072010-05-0707 May 2010 Response to Request for Additional Information Regarding Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1013200242010-05-10010 May 2010 E-mail from R. Guzman to T. Darling/J. Dosa Request for Additional Information - LOCA Analysis, Extended Power Uprate Project stage: RAI ML1012504242010-05-11011 May 2010 Request for Additional Information Extended Power Uprate License Amendment Request - Reactor System Review Project stage: RAI ML1016101682010-06-0303 June 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation- Reactor Systems Review Project stage: Response to RAI ML1015908092010-06-0808 June 2010 Request for Additional Information Extended Power Uprate - Probabilistic Risk Assessment Review Project stage: RAI ML1015906522010-06-10010 June 2010 Review of Extended Power Uprate Application and Revised Review Schedule Project stage: Approval ML1019604812010-06-15015 June 2010 E-mail from R.Guzman to T.Darling Request for Additional Information Follow-up RAI - Reactor Systems/Criticality Analysis Project stage: RAI ML1019004492010-06-30030 June 2010 C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1 Project stage: Other ML1019004502010-06-30030 June 2010 Calculation SIA 100632.301, Revision 0, May 2010 Nine Mile Point Unit 2 Main Steam Line Strain Gage Data Reduction. Project stage: Other ML1019004482010-06-30030 June 2010 C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary) Project stage: Other ML1019004472010-06-30030 June 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation - Steam Dryer and Probabilistic Risk Assessment Project stage: Response to RAI ML1019504952010-07-0909 July 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation, Non-Proprietary Version of Continuum Dynamics, Inc. Report 10-11 Project stage: Response to RAI 2010-02-01
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Category:Letter
MONTHYEARNMP1L3570, 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
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This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment 2.Mark D. Flaherty P.O. Box 63 Plant General Manager Lycoming, New York 13093 315.349.5205 315.349.1321 Fax CENG.a joint venture of 0ConstellaMion Ene l eDF NINE MILE POINT NUCLEAR STATION September 23, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Response to Request for Review of the Draft NRC Safety Evaluation Regarding Nine Mile Point Nuclear Station, Unit No. 2 -Re: The License Amendment Request for Extended Power Uprate Operation (TAC No. ME1476)
REFERENCES:
(a) Letter from K. J. Polson (NMPNS) to Document Control Desk (NRC), dated May 27, 2009, License Amendment Request (LAR) Pursuant to 10 CFR 50.90: Extended Power Uprate (b) Letter from R. V. Guzman (NRC) to T. A. Lynch (NMPNS), dated September 7, 2011, Nine Mile Point Nuclear Station, Unit No. 2 -Transmittal of Draft Safety Evaluation
-Extended Power Uprate (TAC No. ME1476)By letter dated May 27, 2009 (Reference a), as supplemented, Nine Mile Point Nuclear Station, LLC (NMPNS) proposed an amendment to Nine Mile Point Unit 2 (NMP2) Renewed Operating License (OL)NPF-69 that would increase the power level authorized by OL Section 2.C.(l), Maximum Power Level, from 3467 megawatts-thermal (MWt) to 3988 MWt.As requested in the NRC letter dated September 7, 2011 (Reference b), NMPNS has reviewed the draft Safety Evaluation (SE) prepared by the NRC staff to support the proposed license amendment.
Attachment 1 provides NMPNS comments regarding information in the draft SE, and Attachment 2 provides pages of the draft SE that have been highlighted to identify information that should be marked as proprietary, in addition to the text that is already shown enclosed in double brackets.This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment
- 2.
Document Control Desk September 23, 2011 Page 2 Attachment 2 is considered to contain proprietary information exempt from disclosure pursuant to 10 CFR 2.390. Applications to withhold the proprietary information in this attachment from public disclosure in accordance with 10 CFR 2.390(b)(1) have been submitted in previous correspondence (identified in Reference b); therefore, this letter does not represent a new request for withholding from public disclosure.
Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.Very truly yours, STATE OF NEW YORK TO WIT: COUNTY OF OSWEGO I, Mark'D. Flaherty, being duly sworn, state that I am the Nine Mile Point Plant General Manager, and that I am duly authorized to execute and file this supplemental information on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants.
Such information has been reviewed in accordance with company practice and I believe it to be reliable.Subscribed and sworn before me, a Not ry P blic in and for the State of New York and County of 6-4 &Q _,this i~j day of 'ý 2011.WITNESS my Hand and Notarial Seal: -Totr'lblic-My Commission Expires: J lI b TONYALJOWE 7 Date N1t W eofNowYdA OsVwg 004*Ivi .No. 01 A MDF/DEV My CorniýWii~n Expf tLt ,Lt7 Document Control Desk September 23, 2011 Page 3 Attachments:
- 1. Comments Regarding Information in the Draft NRC Safety Evaluation
- 2. Pages of the Draft NRC Safety Evaluation Highlighted to Identify Information that Should Be Marked as Proprietary cc: NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager A. L. Peterson, NYSERDA (w/o Attachment
- 2)
-A.ATTACHMENT 1 COMMENTS REGARDING INFORMATION IN THE DRAFT NRC SAFETY EVALUATION Nine Mile Point Nuclear Station, LLC September 23, 2011 ATTACHMENT 1 COMMENTS REGARDING INFORMATION IN THE DRAFT NRC SAFETY EVALUATION The following table provides comments prepared by Nine Mile Point Nuclear Station, LLC (NMPNS)regarding information in the draft Safety Evaluation (SE) prepared by the NRC staff to support the proposed extended power uprate (EPU) license amendment for Nine Mile Point Unit 2 (NMP2).Note: The term "PUSAR" refers to NEDC-33351P, Safety Analysis Report for Nine Mile Point Nuclear Station Unit 2 Constant Pressure Power Uprate.Comment f Draft SE Section No. Draft SE Comment No. and Title Page 2.4.1, Suitability of 63 Table 2.4-2 of the PUSAR originally indicated that for the Existing Instruments Main Steam Line (MSL) High Flow parameter, respan of the transmitters and associated loop components and revised setpoints were required to support operation at EPU conditions.
Subsequent evaluation has determined that respan of the transmitters and associated loop components is not necessary.
Only the setpoint change is required.
The NRC staff is requested to revise the table on page 63 of the draft SE to indicate that the change for the MSL High Flow parameter is to revise setpoints.
2 2.4.1, Suitability of Existing Instruments 63 Table 2.4-2 of the PUSAR originally indicated that for the Moisture Separator Reheater (MSR) Outlet Pressure parameter, replacement of transmitters, respan of the associated loop instruments, and revised alarm setpoints were required to support operation at EPU conditions.
Subsequent evaluation has determined that transmitter replacement is not necessary.
The NRC staff is requested to revise the table on page 63 of the draft SE to indicate that the change for the MSR Outlet Pressure parameter is to respan the associated loop instruments and revise alarm setpoints.
2.4.1, Suitability of Existing Instruments Table 2.4-2 of the PUSAR originally indicated that for the Condensate Polisher Low Flow Alarm parameter, revised setpoints were required to support operation at EPU conditions.
Subsequent evaluation has determined that a setpoint revision is not required.
The NRC staff is requested to revise the table on page 63 of the draft SE to remove the Condensate Polisher Low Flow Alarm parameter entry.2.4.1, Suitability of Existing Instruments 63 Table 2.4-2 of the PUSAR originally indicated that for .the Condensate Polisher and Strainer AP parameter, revised setpoints were required to support operation at EPU conditions.
Subsequent evaluation has determined that a setpoint revision is not required.
The NRC staff is requested to revise the table on page 63 of the draft SE to remove the Condensate Polisher and Strainer AP parameter entry.1 of 2 ATTACHMENT 1 COMMENTS REGARDING INFORMATION IN THE DRAFT NRC SAFETY EVALUATION Comment Draft SE Section No. Draft SE Comment No. and Title Page 5 2.4.1, Suitability of 64 Table 2.4-2 of the PUSAR originally indicated that for the Existing Instruments Main Steam Inlet Header Pressure parameter, replacement of transmitters, respan of the associated loop components, and a revised alarm setpoint were required to support operation at EPU conditions.
Subsequent evaluation has determined that these changes are not necessary.
The NRC staff is requested to revise the table on page 64 of the draft SE to remove the Main Steam Inlet Header Pressure parameter entry.6 2.5.1.4, Fire Protection 76, 77 In the December 23, 2009 letter from NMPNS to the NRC, the NMPNS response to NRC staff Request for Additional Information RAI D1 indicated that there were no plant modifications that represented physical changes to plant fire protection equipment or systems to support EPU conditions.
Subsequent installation scoping activities for two EPU modifications have identified the need for ancillary changes to fire protection systems. These are: (1) extending an existing sprinkler system to cover a new cable tray associated with the feedwater pump motor cable replacement modification; and (2) a minor relocation of existing sprinkler system piping to accommodate interferences associated with installation of the main transformer cooling upgrade modification.
The NRC staff is requested to consider revising the SE to reflect these fire protection system changes.7 2.5.2.3, Turbine Gland 84 Section 2.5.2.3 of the PUSAR originally stated that no Sealing System Turbine Gland Sealing System (TGSS) hardware changes were required to support operation at EPU conditions.
A recent evaluation has determined that the calibrated span of the normal gland seal supply pressure indication instrument loop will need to be increased and the alarm setpoint revised. Section 2.5.2.3 of the draft SE states that no modifications are needed to support EPU conditions.
The NRC staff is requested to consider revising the SE to reflect this instrumentation change.8 2.8.4.4, Residual Heat 143 Section 2.8.4.4 of the PUSAR originally described the steam Removal System condensing mode (SCM) of operation of the residual heat removal (RHR) system. Subsequently, a plant modification has retired the SCM of RHR system operation, and the SCM is no longer available.
The NRC staff is requested to revise the SE to reflect retirement of the SCM.2 of 2