|
---|
Category:ACRS Summary Report
MONTHYEARML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C2071974-09-25025 September 1974 Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform. ML17037C4801974-09-13013 September 1974 Letter Transmitting ACRS Report Dated September 10, 1974, on the Application for Conversion of the Provisional Operating License to a Full-Term Operating License for the Nine Mile Point Nuclear Station Unit ML17037C4901974-02-20020 February 1974 Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use ML17037C3691971-03-12012 March 1971 Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level ML17037C3501970-06-19019 June 1970 Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970 1974-09-25
[Table view] 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] |
Text
DISTRIBUTION'EC PDR VAMoore Local PDR DJSkovholt DMuller SEP l3 1974 Docket ORB83 Rdg RMaccary Docket No. 50-220 KRGoller RTedesco GLear HDenton CJDeBevec VStello Iintzing SATeets Niagara I fohawk Power Corporation LVGossick GErtter (DR-7674)
NTN: Mr. Philip D. Raymond. SHanauer MGroff Vice President - Engineering ECase EHughes 300 Erie Boulevard Nest FSchroeder EPeyton York 13202 DKnuth Syracuse, New HKShapar Gentlemen: LRouse, E5M RCDeYoUng The Advisory Committee on Reactor Safeguards has issued their report dated, September 10, 1974, on the applicatian for conversion of the provisional operating license to a full-term operating license for the Nine Mile Point Nuclear Station Unit l. A copy of the report is enclosed for your information.
Sincerely, Original Signed George Lear, Chief Operating Reactors Branch 83 Directorate of Licensing
Enclosure:
ACRS Report dtd September 10, 1974 cc: See next page ORB83 ORBP3 ORB/ 3 dURNAMEW SATee CJDeBevec GLear DATE~ 9/ I /74 ,.9/...lw...,/.74,... 9L.....,...../7.4...,..........
Form hRC-318 (ReT. 9.3 3) 'hECM 0240 Q U, dr oOVERNMENT PRINTINO ORRICEI 1074 52d 1dd
ge wp 1
1
<j C')
~>>fP. /(,)l';()
g
Mr. Philip D. Raymond <<2-cc: 'l0/ enclosure Mr. jrvin E. Upton, Esquire LeBoeuf, Lamb, Leiby 5 MacRae 1757 N Street, N. N.
Washington, D. C. 20036 Mr. Robert P. Jones, Supexvisor Town of Scriba R. D. 84 Oswego, New York 13126 Miss Juanita Kersey, Librarian Oswego City Library 120 E. Second Street Oswego, Nmr York 13126 Dr. Nilliam E.'Seymour Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 99 Washington Street Albany, New Yoxk 12210 CPPICC ~
4IIRNAM2W CATR3P.
Form,AC.3j8 (Rcv. 9 53) LCM 0240 N U, 8 4OVRRNMRNT PRINTINO CPPICRI 1474 524 144
1 I
~ 0 ADVISORY COMMITTEE ON REACTOR 'SAFEGUARDS UNlTED STATES ATOMlc ENERGY COMMJSSJON WASH l NOTON. D.C. 20545 C)
Tl n
September 10, 1974 C) m.
CZ rl m
Honorable-Dixy Lee Ray Chairman U. S. Atomic Energy Commission m Washington, D. C. 20545
Subject:
REPORT ON NINE MILE POINT NUCLEAR STATION UNIT 1
Dear Dr. Ray:
At its 173xd meeting, September 5-7, 1974, the Advisory Committee on Reactor Safeguards completed a review of the application by the Niagara Mohawk Power Corporation for conversion of its Nine Mile Point Nucleax Station Unit 1 provisional operating license to a full-texm opexating license. The "appli-cation also was considered at a Subcommittee meeting in Washington, D. C; on July 29, 1974. During its review, the Committee had the benefit of discus-sions with representatives of the Niagara Mohawk Power"Corporation, General Electric Company, and the AEC Regulatory Staff. The Committee also had the of the documents listed. The Committee previously discussed this 'enefit pxoject in an operating license report of Apxil 17, 1969 and in subsequent reports dated June 16, 1970 and February 6, 1:971.
In its review, the Committee evaluated the operation and performance of this unit with particular emphasis on the response of the applicant to past recommendations for impxovements in safety related systems.
Unit 1 is a non-jet pump boiling water reactor of 1850 MW(t) rated power level. Commercial power operation of the plant was begun in December, 1969.
The operating history of the unit has been generally satisfactory. However, a number of operating problems or design deficiencies have been encountered during the approximately five year period of power operation. Included among these are: cracking of a core spray nozzle safe end; development of cracks in the steam dryer assembly; control rod scram sluggishness; failure of some control rods to remain fully inserted after scram; increased control xod operating restrictions 'found necessary to assure protection for a pos-tulated rod 'drop accident; feedwater control deficiency, with resultant flooding of steam lines; torus baffle dislocation by relief valve steam discharge into the torus; and, failure of a'elief valve to reclose. All of these deficiencies appear to have been satisfactorily corrected. Reactor availability has averaged approximately 66'/..
Honorable Dixy Lee Ray September 10, 1974 Difficulty also has been experienced in respect to repeated occurrences of excessive leakage rates of the main steam isolation valves under test The applicant now proposes to remachine the valve seats and plugs con-'itions.
to an improved configuration and believes that this, together with the probable low levels of residual stresses now existing in these valves, will enable maintenance of acceptable leakage rates in the future. This matter should be followed closely by the Regulatory Staff. 1 A number of design improvements have been accomplished or committed to since operation began. Among the most significant of these from the point of view of safety are the following. The feedwater system has been modified also to serve as an additional emergency core cooling system for small breaks; emergency power for this system is supplied by an offsite source of hydro-electric power. A fuel cask drop protection system has been designed and approved, and installation will be completed before shipment of spent fuel is undertaken. A containment atmosphere dilution (CAD) system for combustible gas control will be installed and available for operation in 1976. An ad-ditional primary pressure boundary leak detection system has been added, and position indication in the control room for the containment vacuum breaker valves has been provided.
Approximately one-fifth of the reactor 7x7 fuel bundles have been replaced with 8x8 fuel; through additional reloads, the core eventually is to consist entirely of 8x8 fuel.
Because of the relatively limited accessibility for in-service inspection of the reactor pressure vessel, the Committee wishes to emphasize again its belief that additional means for assuring continued vessel integrity, in-cluding possible improvement in accessibility, should continue to be actively studied and implemented to the degree practical.
The Committee recommends that the Regulatory Staff and the applicant give further consideration to the possible advisability of additional backfitting of Unit 1 where significant and practical safety improvements can be made.
The Committee believes that, in view of the generally satisfactory operating experience to date and the improvements made in the plant as noted herein, and subject to the above comments and those in previous ACRS reports on this plant, there exists reasonable assurance that the Nine Mile Point Nuclear Station Unit 1, can continue to be operated at power levels up to 1850 MW(t) without undue risk to the health and safety of the public. The Committee concurs in conversion of the present provisional operating license to a full-term operating license.
Sincerely yours, W. R. Stratton Chairman
References:
See Page 3
4' Honorable Dixy Lee Ray 3A September 10, 1974 Referencesi
- 1. Niagara Mohawk Power Company Technical Supplement to Petition for Conversion from Provisional Operating License to Full-Term Operating License dated July 1972.
- 2. Applicant'-s Environmental Report, Operating License Stage, Conversion to Full-Term Operating License, June 1972.
- 3. Amendments 1 through 3 to Application for Full-Term Operating License.
- 4. Directorate of Licensing Safety Evaluation Report dated July 3, 1974,
- 5. Directorate of Licensing letter dated July 3, 1974 concerning list of outstanding items in connection with their review of application for Full>>Term Operating License,
- 6. Niagara Mohawk Power Corporation letter dated November 20, 1972 con-cerning Fuel Densification and'its Effect on Reactor Operation Including Transients and Postulated Loss-of-Coolant Accident.
t II '