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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
[Table view] Category:Safety Evaluation Report
MONTHYEARML0628901292006-09-30030 September 2006 NUREG-1900, Vol 1 Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station Units 1 & 2 ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application ML17037B5881978-05-26026 May 1978 Letter Regarding a Request for Evaluation of the Effect on Unit 1 Containment of Multiple Subsequent Actuations of Safety/Relief Valves Following a Postulated Isolation Event ML17037B9231977-08-22022 August 1977 Letter Regarding a Report Describing the Unit 2 Reactor Building Polar Crane and a Review of the Information Provided in a July 20, 1977 Letter ML17037B6251977-06-0202 June 1977 Letter Regarding a Review of Licensee Responses to Previous Generic Request for Information Relative to the Electrical Power Distribution Systems and an Enclosed Safety Evaluation and Statement of Staff Positions ML17037B9601976-03-0505 March 1976 Letter Regarding a Review of the Design and Analysis Methods for the Revetment-Ditch System and Requesting a First Review and Approval of Section 4, Physical Model Study. ML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C0291973-06-15015 June 1973 Letter Regarding the Safety Evaluation of Niagara Mohawk Power Corporation Application for a Permit to Construct the Nine Mile Point Nuclear Station Unit 2 2006-09-30
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Text
Docket Ho. 50-410 JUN I6 19l3 Hr. Harold G. tfangelsdorf Chairman, Advisory Comittee on Reactor Safeguards U. S. Atomic Energy Commission Washington, D. C., 20545
Dear Hr. Nangelsdorf:
Sixteen copies of our Safety Evaluation of, Hiagara Mohawk Power Corpora-tion application for a permit to construct the Nine ttile Point Huclear Station Unit 2 are enclosed for review by the Committee atits Duly meeting. Copies of this evaluation are being sent to the applicant and are being placed in the AEC and Local Public Document Rooms.
lie consider this phase of our radiological safety review of the Nine Nile Point-2 facility to be complete. In completing this review, we have elected to defer final conclusions on a number of matters that are generic in nature and need current resolution for General Electric boiling water reactors. In certain areas we have not agreed with the applicant's submittal, and in these cases, we have directed the applicant to make the improvements in his design that are necessary to meet our safety requirements. Each of the generic matters will be addressed in a supplement to this Safety Evaluation prior to our final determination on the issuance of a construction permit. The generic items and the areas that required improvements in design are outlined below. References are provided to indicate the section and page number where the subject is discussed in the Safety Evaluation Report. In addition, for the generic matters a brief statement of status is given.
Gener ic I%ms
- 1. Fuel Densification 4.2.1 Pa e 4-6 The staff review of fuel densi+'ication effects in 8tJR's is in progress.
Completion of this review is scheduled for Duly 15, 1973.
- 2. Rod Se uence Control S stem 4.2.3 Pa e 4.11. 7.8 Pa e 7-6; and 5.3. Pa e The staff and its consultant are reviewing the approach, proposed for mitigating the consequences of the rod drop accident. For Nine Mile Point-2, we will require and the applicant has agreed to implement the finally approved generic resolution of this concern.
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Mr. Harold G.- Hang'elsdorf 3~ Power Distribution Within the Core 4.3 Pa e 4-14 The staff has some concerns relative to ensuring that the operating limits for linear power density and critical heat flux rates are not exceeded. General Electric has committed to provide for our review a topical report discussing the power distribution in BWR's in the fall of 1973.
Pressure Relief Valves 5.2.2 -Pa e 5-4 Operating problems with pressure relief valves have been experienced in BWR's. These problems are being reviewed by the staff and its l consultants to determine the causes and to recommend means of preventing recurrence.
Recirculation Pum Overs eed 5.4.1 Pa e 5-16 I The applicant described a decoupler design in the PSAR as a means of protecting recirculating pump motors against overspeed. The staff is presently reviewing the problem of the pump overspeed and missile generation. and will shortly complete their review and evaluation of the GE topical report NED0-10677, "Analysis of Recirculation Pump Overspeed . . .".
- 6. Antici ated Transients Without Scram 7.9 Pa e 7-6 The staff is reviewing a topical report, NED0-10349, "Analysis of Anticipated Transients Without Scram," March 1971, submitted by General Electric. If the probability of any of the events considered is determined to be sufficiently high, design modifications may be necessary.
- 7. MSIV Leaka e 9.2.4, Pa e 9-12
'he applicant proposes a seal water system in the PSAR. At our request the applicant has committed to perform a detailed thermal stress and deformation analysis. The results of this investigation will be presented at the operating license stage. In the event that these studies are not conclusive, the applicant will be required to conduct appropriate tests to supplement the analysis.
Non-Generic Items Flood Protection
- a. Probable Maximum Sur e 2.4.5 Pa e 2-17 The applicant proposed to protect against flooding from a cal-OFFICE It SURNAME >
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Harold G.langelsdorf yields a probable maximum surge of 254 feet LSD and we have informed the applicant that this level should be used in the design for NMP-2. The applicant tA continuing his study using a 2-dimensional model. Results from this study will be reviewed prior to construction of the dike and drainage system.
b< Interce tor Ditch 2.4.5 Pa e 2-19 The applicant described an interceptor ditch behind the dike with the capacity of 200,000 cubic feet. Me do not agree with tlie applicant's interceptor ditch capacity and will require sub-stantiation to show 'that the design capacity will avert any flooding that could adversely af'feet safety-related structures or systems prior to construction of the dike and drainage system.
L2o Seismic Desi n of Plant 2.5.2, Pa e 2-31 The initial SSE proposed by the Applicant was a horizontal acceleration of 10$ g based on recent field investigation of the geology in the
. region of the plant. tte and our consultants, however, concluded that there w'as insufficient information on which to base this conclusion.
The applicant agreed to use the 155 g SEE values employed in the design of. the FitzPatrick plant.
- 3. Pi e Breaks in the Recirculation S stem 3.6 Pa e 3-9 The-applicant has adopted . criteria relative to the postulated breaks in the recirculation system different from ours. The design of this system is in the initial phase. At the completion of the design of the pipe system, we will require the applicant to make of the pipe break location and orientation criteria 'omparison with those of the Regulatory position, Those differences not compatible with our position will have to be changed.
Seismic S stem Anal sis 3.7.2 Pa e 3-'ll r
Me will require the applicant to use ti<o horizontal components and one vertical component -for seismic system analysis and to combine the governing response parameters by statistical methods. Me will also require the applicant to use a factor of 1.5 to the peak spectrum values to obtain equivalent static loads.
- 5. Active Valves 319.7, Pa e 3-21 At the request of the staff, the app'licant wil'l identify all active valves and conduct component test programs, supplemented by analytical predicative methods, to assure that these valves will perform their safety function under both normal and accident conditions.
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- 6. Over ressure Protection 5.2.2 Pa e 5-3 To determine the ability of, the pressure relief systems to prevent overpressuriza'tion, we wil'l require the applicant to submit analyses during the operating license stage to demonstrate that the pressure fol]owing the worst transient and assuming failure of one safety/-
relief valve is at least 25 psi less than the ASHE code allowable pressure.
70 ECCS Pum s 6.3.5 Pa e 6-19 The ECCS systems in the Nine Nile Point-2 plant are separated by a six inch curbing that permits leakage from any one system to be identified by observing the operation of a sump pump located in each of these separated areas. Flood protection is provided by locating pump motors and controls several feet above the floor level. In most BWR's each set of pumps is contained in a separate, water-tight room which protects these systems from fiooding 'mall and limits the volume of water lost from the suppression pool so that ECCS pumps suction lines will not be uncovered. Me will require the applicant to provide an equivalent capability to protect against loss of function in systems important to safety due to flooding or to the loss of water supply to the suction of pumps.
- 8. Reactor Tri S stem 7.2, Pa e 7-1 The reactor trip system design described in the PSAR did not provide redundant-manual reactor trip capability. The applicant agreed to modify the design'to incorporate four manual trip push buttons with one-out-of-two-twice logic that is .similar to the automatic trip system, Automatic De ressurization S salem Interlock 7.3, Pa e 7-2 For the, ADS, the applicant will modify the design to be in with IEEE Std 279-1971 with the exception of the permis- full'onformance sive interlocks provided to prevent manual initiation of ADS unless an RHR pump or LPCS pump is operating. Me will require that this permissive interlock be eliminated.
- 10. Hi h Ener Pi e Failure Outside the Containment 7.11 Pa e'-7 and
~BP 10-7 He provided design guidance to the applicant relative to,this problem.'-
In response to this guidance, the applicant submitted high energy line design criteria that are in accordance with the Regulatory guide-lines.
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Mr. Harold G. Hangelsdorf ll. Onsite Electric S stem 8.3.1 Pa e 8-3 The diesel generator provided for the HPCS bus will not IipePtv the 25K voltage drop limit recommended by Regulatory Guide 1.09. The applicant is committed to demonstrate that this diesel generator has the capability for starting fts loss-of>>coolant accfdent loads with acceptable voltage recovery characteristics.
- 12. Testabilit of the Onsfte Emer enc Power Sources 8.3.1 Pa e 8-4 In order to meet GDG 18, testability at power of the diesel generator is required including the starting logic and load sequencing which is required to operate during emergency conditions. The applicant is'committed to provide the required testabflfty.
- 13. S ent Fuel Stora e 9.1.2 Pa e 9-6 During handling over the spent fuel storage area, the potential exists that the cask could strike the edge of the pit, fa'll on the opposite wall of the shipping cask storage area, and roll or tumble into the pool. Me will require the applicant to provide a design to preclude this possibility for our review prior to construction.
Sincerely, Original signed bp Loss A, biooro Voss A. Moore, Assistant Director for Boiling Mater Reactors Directorate of Licensing Distribution:
Docket GCR Reading V. Moore R. C1ark A. Bournia H. Gearin oFFrcE p L:GC~ j L:GCR :AO/BH.
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