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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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IeyBhtory 'Flte Ctl.
NIAGARA MOHAWK POWER CORPORATION
~ci9I'4, NIAGARA I MOHAWK Nine Mile Point Nuclear Station P. 0. Box 32 Lycoming, New York 13093 December 5, 1970 c,KL > '(g~
DDCmED Dr. Peter A. Morris, Director USAEG Division of Reactor Licensing United States Atomic Energy Commission DEt;y >970 0 .g Washington, D. C. 20545 IIgU+TORV
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Dear Dr. Morris:
DOCI~EI I'~~ ~8 Re: Docket Number 50-220 el/ ( Cl~
Provisional Operating License DPR-17 lfe have been requested by the Compliance Section to report electrical output oscillations on the Nine Mile Point generator when approaching 510 Mll(e) gross output. Tests are in progress to identify the origin of the problem which could be one ox a combination of the following:
- 1. Liquid being drained from moisture separators and reheaters is saturated. The extraction heaters to which it is ultimately directed is approximately 60 feet above the drain tank. Therefore, as the liquid rises and the static head becomes less, the latent heat boils off and two-phase slug flow exists. Control of a mixture is not possible with present design, and heater shell levels cannot be maintained constant. Extraction steam being intimately in contact with the shell side of the heater can be affected.
Nozzles have been installed in the drain lines and cooler water injected to provide sub-cooling. On test, two-phase flow appears to have been eliminated. The heater level vascillations have become sinusoidal and therefore, with control modifications, be damped out. Lead-Lag modules will be added to the control system early in 1971. Design studies are being carried forward relative to piping modifications between moisture separators and drain tanks to insure "self-venting".
- 2. Load swinging starts when the turbine admission valve cam shaft reaches a position indicating 83'o valve opening. At this position electrical output cycles about 20 M.N. with a 3 second period.
Steam flow varies in similar fashion causing reactor water level to vary by 6 inches.
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- 2. However,- during the upset, the turbine inlet pressure is controlled to 1 psi. These control valves do not have a perfect linear characteristic through their range and there is a "knee" in the curve at about this valve position. Cams contours have been changed but may still require adjustment. Checks are being made .during load changes relating control rel'ay, cam shaft, and valve movements to steam flow. At their completi.'on, an evaluation will be made by the manufacturer.
- 3. In order to maintain the most stable reactor, operation, the pressure has been controlled to within 0.5 psi at steady state operation. Even with the oscillations previously described, -it varie's onl'y 1.0 psi.- This is excellent regulation, but to achieve it a high degree of sensitivity must be built-in to the control.
Close .regulation can produce "hunting", particularly if a mis-match of sensitivity 'between the system being controlled and the.
control occurs.
Some problems have been encount'ered with the initial pressure regulators, particularly during the start-up test" period.
time, their performance.has been quite'ood. Please refer Since'hat to a report from T. J. Dente to P; A. Burt', "Performance of Initial Pressure Regulators", enclosed herein.
Motivation for the power oscillations could originate from change in sensitivity of control valve response at 83'o opening, as the swings start at this poin't when operating with the second stage of reheat out of service.
However, with the'econd stage of reheat in service, the oscillations are produced irrespective of valve position.
Therefore, either or a combination could start the cycling. Testing has indicated the corrective measures necessary to neutralize the liquid.
removal problem. Testing is continuing to define if adjustment of control valve characteristics is necessary.
and to what extent The possibility of reducing'he initial pressure regulator sensi'tivity is being, looked into.
An early resolution, of the problem is expected.
Very truly yours, P. Allister Burt Superintendent '- Nine Mile Point Enclosure
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INTERNAL "ORRESHNDENCE FORM R2 2 R I JI NIAGARA ', 'MOHAWK Regulatory 'File Cy ~
ois~Rio~ Nine Mile.POint December 3, 1970 FRoM T. J . Dente vo Mr. P. A. Burt, svs~scv Performance ',of Initial Pressure, Regulators
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--5-7 The problem with the Mechanical Pressure Regulator (MPR) and the Electrical Pressure Regulator.(EPR), can be-placed into two categoric's: 1. Those occurring during start-up testing program.and.2. Those'ccurring .since start-up.
During .the. start-up. testing:program .various .problems, were encountered with both .the MPR and the EPR. Primarily,,most of these corrections were 'ones that would be expected in'he'sage of a new piece of equipment. Modifications, were made to the MPR and EPR as follows:
MPR - A needle'.valve was .added to, the sensing line to adjust sensitivity and improve the stability of the system. A bleed. line was added to sensing, line. The one micron filter was changed to a ten micron filter; EPR Capacitor.104C was changed from 1NF t'o SNF" improving the stability.
The pilot valve, bushing and dash pot on the MPR were damaged by dirt particles and had to be replaced.
Following the start-up. program, the plant was shutdown from March 4, 1970 until July 12, 1970. From this date to.the present, modifications were made to the MPR and,EPR,as follows.:
MPR,- The piping to the sensor line ..bellows was, lengthened.
and changed to,stainless steel..from carbon steel.
This eliminated the problem of corrosion products blocking the filters.'engthening the line prevents condensate surges. and provides control dumping.
EPR - Capacitor 104C was increase'd to 6NF from SNF improving stability. Zener diodes" were changed to, cut-the response voltage. from 9 volts to S volts to stop saturation. of the amplifier and stabilize the EPR-MPR take-over.
During this period of time, the EPR held pressure within 1/2,psi. After initial start-up and.with experience, we have been able to match sensitivities between the EPR and MPR so that a smooth transfer. can now be made from one to the other.
3911
0 0
Date Power Level Problem Correction 10/5/69 Hot Standby I'lith the MPR in operation and by-pass valve open switched to EPR bypass valve closed causing high pressure scram 10/18/69 7+o MPR in control with Closed down on sensing 6 psi swing line slightly - MPR stable 11/10/69 15 ~o MPR in control with Installed bleed off line
+ 2 psi oscillations on MPR. Found rotating all bypass valves bushing on MPR stuck with opened depressurizing particles reactor causing scram 11/13/69 Hot Standby i<hile lowering the MPR, Added needle valve to MPR 4 bypass valves opened sensing line and replaced causing low Rx water plugged dash pot, pilot level scram val've and bushing 12/7/69 Hot Standby + 2 psi oscillations Vented sensing line 1 second period with.
EPR in control 12/18/69 50< During start-up tests Filters For M006 valve EPR demonstrations, the plugged. Replaced and EPR takeover of the EPR stab le from the MPR a drop of 7 psi occurred (979 psig to 972 psig) 2/2/70 98o~ During start-up tests on Found that adjustment Pressure Regulators needed on sensing line switched from EPR'to MPR needle valve. Made adjust-and after 10 sec. started ment and MPR stable a 6 psi peak to peak oscillation 2/8/70 98~o MPR in control and Adjusted MPR needle valve started 8 psi peak to and MPR stable peak oscillations 7/8/70 5 o< MPR causing slight Adjusted needle on 7/10/70 cycling in bypass changed sensing valve line valves. GE people From carbon steel to stain-adjusting EPR and MPR less steel on MPR and for bette'r stability change capacitor 104C to 6 NF on EPR
0 0 ~
- Date Power Level Correction
'Problem'hanged 7/20/70 20~o from EPR to Adjustment to MPR MPR and 200 psi peak to peak in pressure occurred - high flux scram level dropped 2 1/2'elow normal Flf flow dropped to 4X10 then to 6X10~
10/19/70 g O~ MPR in control and Adjusted sensor line pressure oscillating needle valve 8 psi peak to peak
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